Добірка наукової літератури з теми "Nuclear corpus"
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Статті в журналах з теми "Nuclear corpus"
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Hattingen, E., M. Nichtweiß, S. Blasel, F. E. Zanella, and S. Weidauer. "Corpus callosum." Der Radiologe 50, no. 2 (December 11, 2009): 152–64. http://dx.doi.org/10.1007/s00117-009-1945-5.
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Ryan, Stephanie, and Veronica Donoghue. "Corpus Callosum." American Journal of Roentgenology 176, no. 5 (May 2001): 1328. http://dx.doi.org/10.2214/ajr.176.5.1761328a.
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Raybaud, Charles. "Corpus Callosum." Neuroimaging Clinics of North America 29, no. 3 (August 2019): 445–59. http://dx.doi.org/10.1016/j.nic.2019.03.006.
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남대현. "A Corpus-Based Analysis of Nuclear Science and Engineering English Vocabulary." Language & Information Society 30, no. ll (March 2017): 75–98. http://dx.doi.org/10.29211/soli.2017.30..003.
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Steiner, Johann, Andrea Schmitt, Matthias L. Schroeter, Bernhard Bogerts, Peter Falkai, Christoph W. Turck, and Daniel Martins-de-Souza. "S100B is downregulated in the nuclear proteome of schizophrenia corpus callosum." European Archives of Psychiatry and Clinical Neuroscience 264, no. 4 (February 7, 2014): 311–16. http://dx.doi.org/10.1007/s00406-014-0490-z.
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Einhorn, Nina. "Uterine Cancer (Corpus Uteri)." Acta Oncologica 35, sup7 (January 1996): 81–85. http://dx.doi.org/10.3109/02841869609101667.
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Ho, Mai-Lan, Gul Moonis, Daniel T. Ginat, and Ronald L. Eisenberg. "Lesions of the Corpus Callosum." American Journal of Roentgenology 200, no. 1 (January 2013): W1—W16. http://dx.doi.org/10.2214/ajr.11.8080.
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Warren, M. E., and J. V. Cook. "Agenesis of the corpus callosum." British Journal of Radiology 66, no. 781 (January 1993): 81–85. http://dx.doi.org/10.1259/0007-1285-66-781-81.
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Rykova, V. V. "THE SEMIPALATINSK NUCLEAR TEST SITE RESEARCH: BIBLIOMETRIC ANALYSIS OF THE DOCUMENTARY CORPUS SELECTED OF THE RUSSIAN SCIENCE CITATION INDEX." NNC RK Bulletin, no. 2 (October 17, 2021): 42–46. http://dx.doi.org/10.52676/1729-7885-2021-2-42-46.
Повний текст джерелаАнотація:
The article represents the bibliometric analysis of the documentary corpus devoted to studying the Semipalatinsk nuclear test site selected of the database Russian Science Citation Index. It shows the publication dynamics over a thirty-year period, the specific structure of the documentary corpus; revels that the documents are thematically structured as follows: research of the medical and biological consequences of radiation exposure (genetic consequences of ionizing radiation exposure; diseases induced by radiation exposure); assessment of the consequences of nuclear tests for the environment (environmental monitoring, radiation situation, pollution of separate environment elements), historical and socio-legal aspects of investigating the test site activity consequences.
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Choi, Hyuck Jae, Seung Hyup Kim, Sun Ho Kim, Hyo-Cheol Kim, Chang Min Park, Hak Jong Lee, Min Hoan Moon, and Jun Yong Jeong. "Ruptured Corpus Luteal Cyst: CT Findings." Korean Journal of Radiology 4, no. 1 (2003): 42. http://dx.doi.org/10.3348/kjr.2003.4.1.42.
Повний текст джерелаДисертації з теми "Nuclear corpus"
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Mallea, Rodrigo. "A questão nuclear na relação argentino-brasileira (1968-1984)." Universidade do Estado do Rio de Janeiro, 2012. http://www.bdtd.uerj.br/tde_busca/arquivo.php?codArquivo=6312.
Повний текст джерелаАнотація:
Coordenação de Aperfeiçoamento de Pessoal de Nível SuperiorEste trabalho visa explorar a dinâmica da relação nuclear entre Argentina e o Brasil ao longo do período 1968-1984. Em particular, ele procura analisar a interação de duas dimensões desta relação. A primeira, de ordem bilateral, centra-se no estudo da rivalidade argentino-brasileira e procura medir o seu impacto tanto nas decisões nucleares de cada país como nas tentativas de estabelecer um acordo de cooperação nesta área. A segunda dimensão, de ordem internacional, analisa o impacto que teve sobre o relacionamento argentino-brasileiro a coincidente postura de ambos os países frente o regime de não proliferação nuclear (Tlatelolco e TNP) e a pressão internacional que ambos tiveram que suportar sobre os seus programas nucleares. Com esse objetivo, o trabalho se concentra em uma abordagem histórica guiada por fontes primárias (pesquisa de arquivo e entrevistas pessoais) com o objeto de reconstruir a narrativa histórica e contribuir a novas interpretações sobre o relacionamento argentino-brasileiro no período em questão em base à nova evidencia apresentada. São apresentadas quatro conclusões centrais: (1) mesmo sob uma situação de competição regional e crescente disputa geopolítica na Bacia da Prata, não houve uma corrida armamentista para a obtenção da bomba devido à natureza da rivalidade argentino-brasileira; (2) em todo momento os dois países têm incentivos para cooperar no campo nuclear por causa da sua visão compartilhada respeito à ordem nuclear global e a falta de informação perfeita sobre as atividades nucleares do outro país; (3) a dinâmica da rivalidade regional argentino-brasileira é fundamental para explicar por que, apesar de numerosas tentativas de cooperação nuclear de ambos os lados, escolhem uma lógica de não-cooperação entre as décadas de 1960 e 1970, e posteriormente, passam a uma de cooperação no começo de 1980 (4) a democratização como variável central para explicar o rapprochement nuclear teve um papel menor do que a literatura sugere.
El presente trabajo tiene como objeto explorar la dinámica de la relación nuclear argentino-brasileña entre 1968-1984. En particular, se propone estudiar la interacción de dos dimensiones de esta relación. La primera, de orden bilateral, se centra en un análisis de la rivalidad regional argentino-brasileña con el fin de medir en qué grado ello se trasladó al campo nuclear y qué efectos tuvo sobre las tentativas de alcanzar un acuerdo en dicha área. La segunda, de orden internacional, analiza el impacto que tuvo sobre la relación bilateral argentino-brasileña la coincidente postura de ambos países frente al régimen de no proliferación nuclear (Tlatelolco y TNP) y la presión internacional que ambos debieron soportar sobre sus programas nucleares. Para ello, el trabajo propone una investigación histórica guiada por fuentes primarias (investigación de archivo y entrevistas personales) con el fin de reconstruir la narrativa existente y contribuir a nuevas interpretaciones sobre la relación argentino-brasileña en dicho período. Se presentan cuatro conclusiones centrales: (1) aún en un contexto de competencia regional signado por la creciente disputa geopolítica en la Cuenca del Plata, no existió una carrera armamentista por la bomba debido a la naturaleza de la rivalidad argentino-brasileña; (2) en todo momento ambos países tienen incentivos para cooperar en el campo nuclear por causa de su visión compartida frente al orden nuclear internacional y la falta de información perfecta sobre las actividades nucleares del otro país; (3) la rivalidad regional es central para explicar por qué, a pesar de numerosas tentativas de cooperación nuclear de ambos lados, se pasa de una lógica de nocooperación entre las décadas de 1960 y 1970 a una de cooperación en el comienzo de 1980 y (4) la democratización como principal variable para explicar el rapprochement nuclear argentino-brasileño tiene un rol menor del que sugiere la literatura.
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Кошкіна, Марина Сергіївна. "Використання програмних засобів корпусної лінгвістики для оптимізації роботи перекладача у сфері ядерної енергетики". Master's thesis, КПІ ім. Ігоря Сікорського, 2018. https://ela.kpi.ua/handle/123456789/27630.
Повний текст джерелаАнотація:
Магістерську дисертацію присвячено розгляду можливостей корпусної лінгвістики, аналізу основних проблем, з якими стикаються перекладачі технічної літератури під час перекладу спеціалізованих текстів, а також пропозиції щодо уникнення перекладацьких помилок, покращення якості та оптимізації процесу перекладу за допомогою альтернативного підходу – застосування засобів корпусної лінгвістики. Дана робота визначає специфіку якісного перекладу та відповідних вимог. Крім того, надано та класифіковано шляхи подолання різних труднощів перекладу на синтаксичному, семантичному та структурному рівнях у формі перекладацьких прийомів. Представлена дослідницька робота містить практичний аналіз перекладу текстів технічного спрямування, результати якого надали широкі можливості для вивчення корпусу як альтернативного рішення для покращення якості перекладу. Дисертація розглядає типи та критерії для створення належного корпусу. Пропонується практичне застосування корпусу на прикладах для окреслення основних його функцій та можливостей, що сприяють досягненню найповнішого рівня еквівалентності та адекватного перекладу. Дана наукова робота містить досвід розробки корпусу the Nuclear Corpus та його вдалої реалізації з використанням найзручніших корпусних менеджерів. Приділено увагу перевагам застосування корпусу під час перекладу, таким як конкорданс, відносна та абсолютна частотність слів, ключові слова, сполучуваність слів, багатокомпонентні групи, контекстуальне вживання слів. Дана робота спонукає до подальшого вдосконалення корпусу відповідно до певних перекладацьких потреб з метою досягнення найвищого рівня еквівалентності тексту перекладу та тексту оригіналу, задоволення очікувань адресатів перекладу. Робота відкриває перспективи для подальшого вивчення корпусу з метою виявлення нових корисних можливостей для полегшення роботи перекладача.This Master’s Thesis is devoted to the consideration of corpus linguistics capabilities, investigation of the main problems encountered by technical translators while translating engineering texts and provision of an alternative solution for them to eliminate translation weaknesses, improve quality, and optimize translation itself. The paper defines features of a good quality translation and its requirements. In addition, the ways to overcome various translation difficulties at syntactic, semantic and structural levels are given in the form of recommended translation techniques which are classified according to specified criteria. The given research paper also provides a practical example of technical translation, the analysis of which gives wide opportunities for studying a corpus as an alternative solution for improving the quality of the translation. The thesis presents types and criteria for a good corpus compilation. Practical usage of a corpus with examples is suggested to outline its main functions and opportunities which can assist any translator in achieving the closest equivalency and adequate translation. The following paper shares experience of developing the Nuclear Corpus and its successful implementation while using the most user-friendly corpus managers. The paper also demonstrates the advantages of corpus application during translation compared to other modern technologies used in the process of translation. This research encourages the idea of further corpus development for the specific translation needs in order to make target texts equivalent at the highest level and meet expectations of the addressees. At the same time, the Master’s Thesis makes it possible to study the issue of a corpus further with the purpose to identify new useful opportunities it can provide to facilitate the work of a translator.
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Shen, Lionel. "Méthodes de veille textométrique multilingue appliquées à des corpus de l’environnement et de l’énergie : « Restitution, prévision et anticipation d’événements par poly-résonances croisées »." Thesis, Sorbonne Paris Cité, 2016. http://www.theses.fr/2016USPCA085/document.
Повний текст джерелаАнотація:
Cette thèse propose une série de méthodes de veille textométrique multilingue appliquées à des corpus thématiques. Pour constituer ce travail, deux types de corpus sont mobilisés : un corpus comparable et un corpus parallèle, composés de données textuelles extraites des discours de presse, ainsi que ceux des ONG. Les informations récupérées proviennent de trois mondes en trois langues différentes : français, anglais et chinois. La construction de ces deux corpus s’effectue autour de deux thèmes d’actualité ayant pour objet, l’environnement et l’énergie, avec une attention particulière sur trois notions : les énergies, le nucléaire et l’EPR. Après un bref rappel de l’état de l’art en intelligence économique, veille et textométrie, nous avons exposé les deux sujets retenus, les technicités morphosyntaxiques des trois langues dans les contextes nationaux et internationaux. Successivement, les caractéristiques globales, les convergences et les particularités de ces corpus ont été mises en évidence. Les dépouillements et les analyses qualitatives et quantitatives des résultats obtenus sont réalisés à l’aide des outils de la textométrie, notamment grâce aux analyses factorielles des correspondances, réseaux cooccurrentiels et poly-cooccurrentiels, spécificités du modèle hypergéométrique, segments répétés ou encore à la carte des sections. Ensuite, la veille bi-textuelle bilingue a été appliquée sur les trois mêmes concepts dans l’objectif de mettre en évidence les modes selon lesquels les corpus multilingues à caractère comparé et parallèle se complètent dans un processus de veille plurilingue, de restitution, de prévision et d’anticipation. Nous concluons notre recherche en proposant une méthode analytique par Objets-Traits-Entrées (OTE)This thesis proposes a series of textometric multilingual information monitoring methods applied to thematic corpora (textometry is also called textual statistics or text data analysis). Two types of corpora are mobilized to create this work: a comparable corpus and a parallel corpus in which the textual data are extracted from the press and discourse of NGOs. The information source was retrieved from three countries in three different languages: English, French and Chinese. The two corpora were constructed on two topical issues concerning the environment and energy, with a focus on three concepts: energy, nuclear power and the EPR (European Pressurized Reactor or Evolutionary Power Reactor). After a brief review of the state of the art on business intelligence, information monitoring and textometry, we first set out the two chosen subjects – the environment and energy – and then the morphosyntactic features of the three languages in national and international contexts. The overall characteristics, similarities and peculiarities of these corpora are highlighted successively. The recounts and qualitative and quantitative analyses of the results were carried out using textometric tools, including factor analysis of correspondences, co-occurrences and polyco-occurrential networks, specificities of the hypergeometric model and repeated segments or map sections. Thereafter, bilingual bitextual information monitoring was applied to the same three concepts with the aim of elucidating how the comparable corpus and the parallel corpus can mutually help each other in a process of multilingual information monitoring, by restitution, forecasting and anticipation. We conclude our research by offering an analytical method called Objects-Features-Opening (OFO)
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Huyghe, Jordan. "Exploitation du corpus de données expérimentales pour la puissance résiduelle des combustibles de réacteurs à eau pressurisée afin d'accroître la maîtrise des biais et incertitudes de calcul avec l'OCS DARWIN2.3." Thesis, Aix-Marseille, 2019. http://www.theses.fr/2019AIXM0359.
Повний текст джерелаАнотація:
La puissance résiduelle est un paramètre dimensionnant à toutes les étapes de l’aval du cycle du combustible, depuis l’arrêt du réacteur jusqu’au stockage final des matières radioactives non valorisables. Une maîtrise du calcul de la puissance résiduelle et de son incertitude est donc nécessaire pour tous les REP du parc nucléaire français : combustibles de type REP-UOx et MOx, sur la plus large plage de refroidissement possible. Le calcul de la puissance résiduelle et de son incertitude est réalisé au CEA avec l’Outil de Calcul Scientifique (OCS) de référence DARWIN2.3. Pour répondre au guide de l’ASN n°28 relatif à la démonstration de sûreté pour la tenue de la première barrière, DARWIN2.3 s’inscrit dans une démarche de vérification, validation & quantification des incertitudes, afin de démontrer la maîtrise du calcul de la puissance résiduelle et de l’incertitude associée. Pour définir cette dernière, la propagation des covariances des données nucléaires sur la puissance résiduelle ou la transposition de la validation expérimentale de l’OCS DARWIN2.3 sont possibles. La démarche de la thèse a consisté à étudier la représentativité des expériences issues du dossier de validation expérimentale de l’OCS DARWIN2.3 ou de la littérature ouverte vis-à-vis de combustibles REP. Cela a permis de définir un domaine de validité pour le calcul de la puissance résiduelle des combustibles REP-UOx et MOx. Le travail de thèse a ensuite consisté à mettre en évidence les lacunes du domaine de validité de DARWIN2.3 pour les combustibles REP-UOx et REP-MOx et à proposer in fine les expériences de mesure de puissance résiduelle qu’il faudrait mener pour combler ces lacunesThe decay heat is a dimensioning parameter at every step of the back-end nuclear cycle, from the reactor shutdown until the final storage of non-recoverable radioactive waste. Accurate control of the calculation of the decay heat and its uncertainty is essential for all the Pressurized Water Reactors (PWRs) in the french reactor infrastructure : PWR-UOx and PWR-MOx fuels, over a wide range of cooling times. The calculation of the decay heat and its uncertainty is performed at CEA with the french reference DARWIN2.3 package. To answer the ASN's guide number 28 relative to the safety demonstration for the first barrier resistance, DARWIN2.3 follows a verification, validation & uncertainty quantification process, in order to prove the control of the decay heat calculation and the associated uncertainty. To define the latter, the propagation of nuclear data covariances to the decay heat or the transposition of the DARWIN2.3's experimental validation are possible. The approach considered for the thesis consisted in studying the representativity of experiments coming from the DARWIN2.3's experimental validation or the literature with PWR fuels. These studies enabled the definition of a 'validity domain' with DARWIN2.3 for the decay heat calculation of PWR-UOx and MOx fuels. Then, the thesis consisted in identifying the gaps in the DARWIN2.3 'validity domain' for the PWR-UOx and PWR-MOx fuels and in identifying the decay heat experiments to be carried out to fill these gaps
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Guimarães, Karin Silvia Franzoni Fornazier. "Experimental and theoretical aspects of the D+ ? K ? ? + ? + decay." Instituto Tecnológico de Aeronáutica, 2013. http://www.bd.bibl.ita.br/tde_busca/arquivo.php?codArquivo=2897.
Повний текст джерелаАнотація:
Este trabalho compreende dois aspectos na abordagem do problema do decaimento D+ ? K ? ? + ? + , um experimental e outro teórico. No que tange a análise experimental, trabalhamos com dados simulados em Monte Carlo provenientes do detetor LHCb, para o decaimento mencionado. O desenvolvimento de um algoritmo numérico alternativo para o ajuste do gráfico de Dalitz foi feito, sendo este baseado em procedimentos executados por outras colaborações. O objetivo deste foi o de veri#car se este mesmo procedimento é viável nesta etapa de análise dos dados do LHCb. Este ajuste utilizou simulações de Monte Carlo para as ressonâncias presentes no decaimento, mas desconsiderou efeitos de fundo, e#ciência e cobertura angular do detector. Com relação aos aspectos teóricos, foi elaborado um modelo de re-espalhamento de três-corpos usando coordenadas na frente de luz para o estado final do D+ ? K ? ? + ? + . Neste modelo a amplitude off-shell é uma solução da equação de Bethe-Salpeter quadridimensional, decomposta na forma de Faddeev e projetada nas coordenadas de frente de luz através da expansão do quasi-potencial. O kernel da equação integral contem a amplitude de espalhamento K? na onda S nos estados de isospin, tanto 1/2 como 3/2, sendo essas ajustadas aos dados experimentais do experimento LASS. A solução das equações integrais tridimensionais na frente de luz para as amplitudes espectadoras, foram obtidas de forma perturbativa até segunda ordem, com uma contribuição em terceira ordem muito pequena. Os resultados numéricos para o módulo da magnitude e fase da amplitude deste decaimento foram comparados com os dados experimentais das colaborações E791 e FOCUS. Os dados experimentais sugerem uma pequena mistura entre o isospin total, 5/2, e o dominante, 3/2. O módulo da amplitude de decaimento não simetrizada, que apresenta um minímo profundo seguido de um crescimento para massas do sistema K? acima de 1.5 GeV, foi reproduzido de forma satisfatória. Podemos observar também que abaixo de 1 GeV o módulo é subestimado, ocorrendo o mesmo no do espaço de fase ao redor de 1.8 GeV.
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Tessier, Sarah. "Contrôle de la sumoylation par les corps nucléaires PML." Thesis, Sorbonne Paris Cité, 2018. http://www.theses.fr/2018USPCC169/document.
Повний текст джерелаАнотація:
Les corps nucléaires PML (CNs) sont des structures sphériques organisées par la protéine PML où, de nombreuses protéines impliquées dans divers processus biologiques tels que la sénescence, la mort cellulaire ou la défense virale, y sont recrutées. Ces protéines ont été identifiées individuellement dans des études spécifiques mais aucune étude n’avait permis la purification des CNs et l’établissement de liste des partenaires de PML de façon systématique. La protéine PML est sensible à l’oxydation et le stress oxydant promeut son assemblage en CNs permettant le recrutement de l’enzyme E2 clé de la conjugaison, UBC9. Les interférons (IFNs), cytokines aux propriétés antivirales induisent l’expression de PML. L’arsenic et les IFNs augmentent l’assemblage des CNs.Dans cette étude nous avons exploré, in vivo, le rôle de PML dans la sumoylation en réponse au stress en utilisant deux modèles de souris et un modèle cellulaire, les cellules souches embryonnaires de souris (mESC), exprimant des versions taguées de SUMO1 ou SUMO2. Nous avons montré que PML augmente rapidement la sumoylation dans les foies de souris KI His6-HA-SUMO1 en réponse aux traitements arsenic/IFN. De façon similaire, dans la leucémie aiguë promyélocytaire (LAP), où les CNs sont désorganisés, l’arsenic promeut la reformation des CNs et la conjugaison par SUMO. L’analyse par spectrométrie de masse quantitative des conjugués His10-SUMO2 a permis de mettre en évidence une liste de protéines sumoylées en réponse au traitement thérapeutique à l’arsenic. Parmi ces protéines, TRIM28/KAP1 et d’autres protéines appartenant au même complexe régulant la chromatine ont été identifiées. TRIM28, qui joue un rôle clé dans la répression des rétrovirus endogènes (ERV) dans les mESC, est sumoylée de façon dépendante de PML dans ces cellules. Les CNs régulent également l’ubiquitinylation et la dégradation dépendante du protéasome, de certaines de ces protéines. Enfin, nous avons montré que les CNs favorisent la formation de chaînes SUMO2/3, expliquant le rôle des CNs dans la dégradation des protéines. Cette étude nous a permis de mettre en évidence que les CNs sont des compartiments nucléaires qui contrôlent la conjugaison de diverses protéines dans des conditions physiologiques de stress cellulaire, montrant pour la première fois leur activité de contrôle de MPT in vivoPML drives assembly of PMLNuclear Bodies (NBs) where it recruits hundreds of serendipitously-identified proteins, among which the key UBC9 E2-sumoylation enzyme. Interferons (through transcriptional PML induction) and arsenic or oxidative stress (through PML aggregation) dramatically enhance NB assembly. Here we directly investigated any role for PML in stress-responsive sumoylation in vivo. We demonstrate that PML very rapidly promotes arsenic/interferon-responsive sumoylation in mouse liver or mouse embryonic stem cells. Similarly, in Acute Promyelocytic Leukemia (APL), where PML NBs are disorganized in the basal state, arsenic therapy promoted NB-reformation and broad SUMO-conjugation. Label free quantitative proteomic analysis of His10-SUMO2-conjugates revealed a comprehensive list of therapy-responsive sumoylated proteins, among which TRIM28 and other proteins belonging to the same epigenetic complex. PML NBs-regulated sumoylation also drives ubiquitination and proteasome-dependent degradation of some targets. Finally, by expressing conjugation-resistant SUMO2, we demonstrate that PML NBs promotes processive SUMO2/3 chain elongation, thus explaining PML role in partner degradation. Collectively, our findings highlight the key activity of NBs in stress-regulated sumoylation/degradation in vivo
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Marchetti, Mara. "Elastic properties characterization of nuclear fuels under extreme conditions." Thesis, Montpellier, 2017. http://www.theses.fr/2017MONTS053/document.
Повний текст джерелаАнотація:
Ce travail de recherche vise à étudier les propriétés élastiques par microscopie acoustique du combustible nucléaire dans trois situations particulières: combustible en utilisation normale en réacteur nucléaire, combustible stocké après la période d’irradiation et combustible en conditions extrêmes suite à un accident nucléaire. Les mesures réalisées sur les échantillons irradiés ont conduit à plusieurs résultats majeurs: validation d’une loi corrélant la vitesse des ondes de Rayleigh à la densité du dioxyde d’uranium irradié ou frais; détermination de la porosité dans le combustible irradié; évaluation du gonflement de la matrice en fonction du taux de combustion dans la gamme 0-100 GWdt-1M; développement d'un modèle empirique capable de prévoir la variation de module de Young en fonction du taux de combustion en prenant même en compte la teneur en dopants (Gd2O3, CeO2) ; quantification de l’évolution du module de Young du combustible suite à l'endommagement en stockage ; premières mesures sur du corium. Enfin, grâce au lien entre les propriétés thermiques et élastiques, différentes propriétés thermiques de l'UO2 ont été calculées en mesurant la vitesse de l'onde de surface de Rayleigh seuleThe focus of the present thesis is the determination of the elastic properties of nuclear fuel using high frequency acoustic microscopy. The nuclear fuel is considered under three different conditions: during its normal life in reactor, after its discharge and disposal in interim or long-term storage and subsequently to its severe degradation caused by a nuclear accident. Measurements performed on irradiated fuels allowed to validate a law between the density of fresh and irradiated fuel and the Rayleigh wave velocity; the determination of the irradiated fuel porosity and matrix swelling in the broad burnup range 0-100 GWdt-1M; the development of an empirical model capable of predicting the evolution of Young's modulus versus burnup correcting also for the additives content (Gd2O3, CeO2); Young's modulus evolution due to alpha-decay damage as in-storage condition; first corium measurements. Moreover, several UO2 thermal parameters were calculated only by means of the Rayleigh wave velocity thanks to the link between thermal and elastic properties
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Silbermann-Hoffman, Olivia. "IRM et corps calleux." Université Louis Pasteur (Strasbourg) (1971-2008), 1991. http://www.theses.fr/1991STR1M155.
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Natti, Érica Regina Takano. "Extensão da Aproximação de Campo Médio para a Evolução de Sistemas Férmion-Bóson." Universidade de São Paulo, 1998. http://www.teses.usp.br/teses/disponiveis/43/43131/tde-05122013-184323/.
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Neste trabalho estudamos a extensão da aproximação de campo médio, dada uma condição inicial, para a evolução temporal de um sistema composto de férmions e bósons que interagem. Para isto usamos uma técnica de projeção dependente do tempo através do qual obtemos equações de movimento do tipo cinético para o conjunto de variáveis dinâmicas de um corpo. Na primeira parte do trabalho aplicamos a técnica para um sistema descrito pelo modelo de Jaynes Cummings, o qual descreve a interação da matéria, representada por um sistema de dois níveis, com a radiação, representada por um modo normal do campo quantizado. Obtemos a dinâmica de campo médio e a seguir usando a técnica de projeçào, calculamos correções à esta descrição de campo médio. Além de ser um modelo exatamente solúvel, o que nos permite comparar nossos resultados com a solução exata, o modelo de Jaynes-Cummings corresponde ao plasma escalar relativístico em zero dimensões espaciais. Na segunda parte deste trabalho estudamos o modelo do plasma escalar relativístico. Esta teoria quântica de campos descreve a interação de campos bosônicos escalares e fermiônicos de spin-1/2 através de uma interação do tipo Yukawa. Para o sistema do plasma escalar relativístico obtemos as equações que descrevem a dinâmica de campo médio e a partir das soluções estacionárias, renormalizamos a teoria. Finalmente, estudamos o regime de pequenas oscilações em torno do equilíbrio, obtendo soluções analíticas para a evolução de nossas variáveis. Analisamos também as condições para existência de estados ligados neste regime.In this work we study the extension of the mean-field approximation, given an initial condition, to the time evolution of a fermion-boson system. We use a time-dependent projection where we obtain kinetic-type equations for the set of one-body variables. First, we study the Jaynes-Cummings model which describes the interaction of the matter represented by the two-level system with the radiation represented by the normal mode of the quantized radiation field. We obtain the mean-field dynamics of the system and using the projection technique, we evaluate corrections to this mean-field description. Relevance of the Jaynes-Cummings model stems from the fact that, besides being soluble which possibilities compare our results with the exact solution, it can be seen as corresponding to the relativistic scalar plasma in zero spatial dimensions. Next, we study the relativistic scalar plasma. This quantum field theory describes a system of spin-1/2 fermions interacting through the exchange of scalar particles via a Yukawa-type interaction. In the study of the relativistic scalar plasma, we obtain the mean-field dynamics and from the static solution, we renormalize the theory. Finally, we study the small oscillations regime obtaining analytical solution for one-body variables. We have also examined the condition for the existence of bound-state in this case.
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Calil, Iara Pinheiro. "Caracterização funcional da proteína AtWWP1, componente de uma interconexão de fatores da interação geminivirus-hospedeiro envolvido na formação de corpos subnucleares." Universidade Federal de Viçosa, 2013. http://locus.ufv.br/handle/123456789/4788.
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Plants are engaged in a continuous co-evolutionary struggle for dominance with their pathogens and the outcomes of these interactions are of particular importance to human activities, as they can have dramatic effects on agricultural systems (Dodds & Rathjen, 2010). Recently, the convergence of molecular studies of plant immunity and pathogen infection strategies is revealing an integrated picture of the plant pathogen interaction (Mukhtar et al., 2011) in which the pathogen effectors interaction converge onto highly connected subgroups of proteins, named hubs. A well-defined hub form plant immune system network corresponds to CSN5A protein, a catalytic subunit of the COP9 signalosome acting as a key regulator in several basic cellular processes. Consistent with the prediction that different effectors from different pathogens target similar connections in plant-pathogen interaction network, it has been shown, independently, that the protein C2 from geminivirus, a DNA virus that infects a wide variety of agronomic crops, interacts to CNS5A (Lozano- Duran et al, 2011). Additionally, it was shown that NIG and the immune receptor NIK, both targets of geminivírus NSP, interact to CSN5A (Machado, 2011; Mukhtar et al., 2011). Based on this information, it is expected that the hub CNS5A is a functional element in the geminivirus-host interaction network. Recently, it was reported that NIG, a cellular partner of CSN5A, also interacts with a unknown function protein, encoded by the locus AT2G41020 in yeast (Machado, 2011). As a possible component from geminivirus-host interaction network converging to CSN5A, AT2G41020 may interact directly or indirectly with virulence factors in defense response or compatibility. The objectives of this research involved biochemical characterization of the protein encoded by the locus AT2G4102, designated AtWWP1, and identification of its possible interactions with viral proteins and host factors. In silico analysis of tWWP1 predicted structure revealed the presence of two WW domains, and a C-terminal domain highly conserved between homologous in plant and animals. Furthermore, it has been shown that AtWWP1 is a nuclear protein capable of forming nuclear bodies via the conserved C-terminal domain. Coimmunoprecipitation and BiFC assays demonstrated that AtWWP1 interacts in vivo with the cytoplasmic protein NIG, redirecting it to nuclear bodies. In order to explore the formative activity of nuclear bodies AtWWP1, the interaction between AtWWP1 and a second protein partner AtMBD2 (methyl CG binding domaincontaining protein) was characterized in vivo. The ability to form nuclear bodies as interaction with AtMBD2 were mapped AtWWP1 occuring via its domain and C-terminal conserved, substantiating the argument that this region of AtWWP1 is responsible for the formation of nuclear bodies. Colocalization assays have shown that nuclear bodies contained in AtWWP1 are distinct from those formed by proteins involved in RNA splicing, but colocalized with nuclear bodies containing CDKC2. Furthermore, it was demonstrated that AtWWP1 does not bind to RNA, but exhibits a binding activity to DNA. These characteristics imply that AtWWP1 should be involved with basic nuclear functions. As a component of a functional hub in geminivirus-host interaction network, it is important to assess whether the viral infection would affect the nuclear bodies formed by AtWWP1.
Estudos moleculares envolvendo o sistema imune de plantas e a infecção por patógenos revelaram um panomara integrado de interações plantapatógeno em que as interações dos efetores de virulência convergem para subconjuntos de proteínas do hospedeiro altamente interconectadas e designadas hubs. Um hub funcional e bem definido do sistema imune de plantas corresponde a interconexões convergentes para a proteína CNS5A que constitui a subunidade catalítica do complexo COP9 signalosome, um regulador chave de diversos processos celulares básicos. Consistente com a previsão de que efetores de diferentes patógenos devem alvejar similares conexões na rede de interações planta-patógeno, foi demonstrado, independentemente, que a proteína C2 de geminivírus, um vírus de DNA que infecta uma grande variedade de culturas agronômicas, interage com a proteína CNS5A. Além disso, foi também demonstrado que tanto a proteína NIG, quanto o receptor imune NIK, ambos alvos da proteína NSP de geminivírus, também interagem com CNS5A. Baseado nestas informações, prevê-se que a interconexão (hub) representada por CNS5A seja um elemento funcional na interação geminivírus-hospedeiro. Recentemente, foi identificado que, além de interagir com CSN5A, a proteína NIG também interage com uma proteína de função desconhecida codificada pelo locus AT2G41020, em leveduras . Como possível componente da rede de interações geminivírus-hospedeiro que converge em CNS5A, AT2G41020 pode interagir direta ou indiretamente com fatores de virulência em resposta de defesa ou de compatibilidade. Sendo assim, os objetivos principais dessa investigação envolveram caracterização bioquímica da proteína codificada pelo locus AT2G41020 e identificação de possíveis interações com proteínas virais e fatores do hospedeiro. Análise in silico da estrutura predita da proteína codificada pelo lócus At2G41020, designada AtWWP1, revelou a presença de dois domínios WW e um domínio C-terminal altamente conservado entre proteínas homólogas de espécies vegetais e animais. Além disso, foi demonstrado que a proteína AtWWP1 é uma proteína nuclear capaz de formar corpos subnucleares via o domínio C-terminal conservado. Ensaios de coimunoprecipitação e BiFC demonstraram que AtWWP1 interage in vivo com a proteína citoplasmática NIG promovendo o seu redirecionamento para corpos nucleares. Com a finalidade de explorar a atividade formadora de corpos nucleares de AtWWP1, a interação entre AtWWP1 e uma segunda proteína parceira AtMBD2 (proteína contendo um domínio de interação com CG metilado) foi caracterizada in vivo. Tanto a capacidade de formar corpos nucleares quanto a interação com AtMBD2 foram mapeadas em AtWWP1 e ocorrem via seu domíno C-terminal conservado, substanciando o argumento de que esta região de AtWWP1 é responsável pela formação de corpos subnucleares. Ensaios de co-localização demonstraram que os corpos nucleares contidos em AtWWP1 são distintos daqueles formados por proteínas envolvidas em splicing do RNA; porém co-localizam com corpos nucleares contendo CDKC2. Além disso, foi demonstrado que AtWWP1 não liga a RNA, mas exibe uma atividade de ligação ao DNA. Estas características implicam que AtWWP1 deve estar envolvida com funções nucleares básicas. Como componente de um hub funcional na interação geminivírus-hospedeiro, torna-se relevante avaliar se a infecção viral afetaria os corpos nucleares formados por AtWWP1.
Книги з теми "Nuclear corpus"
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Phyllis, Hale, and Siegrist James, eds. Proceedings of the Third International Conference on Calorimetry in High Energy Physics: Corpus Christi, Texas, September 29-October 2, 1992. Singapore: World Scientific, 1993.
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2
Corps, United States Marine. MAGTF nuclear, biological, and chemical defense operations. Washington, DC: Headquarters, U.S. Marine Corps, 1998.
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3
Boer, Brian. Optimized core design and fuel management of a pebble-bed type nuclear reactor. Amsterdam: IOS Press, 2008.
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4
Ross, Kyle. MELCOR best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2014.
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Anderson, J. L. Summary of inadequate core cooling instrumentation for U.S. nuclear power plants. Washington, DC: Division of Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1990.
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6
North, Oliver. The Jericho sanction: A novel. Nashville, Tenn: Broadman & Holman, 2003.
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7
Gasser, R. D. Late-phase melt progression experiment, MP-2. Washington, DC: United States Nuclear Regulatory Commission, 1997.
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8
TMI-2: An event in accident management for light-water-moderated reactors. La Grange Park, Ill: American Nuclear Society, 2011.
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9
United States. Department of the Army. Multiservice tactics, techniques, and procedures for nuclear, biological, and chemical (NBC) protection. [Washington, D.C.?]: Army, Marine Corps, Navy, Air Force, 2003.
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Corps, United States Marine. Multiservice procedures for nuclear, biological, and chemical (NBC) defense of theater fixed sites, ports, and airfields. Quantico, VA]: U.S. Marine Corps, 2000.
Знайти повний текст джерелаЧастини книг з теми "Nuclear corpus"
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Yamanaka, Masao. "Sensitivity and Uncertainty of Criticality." In Accelerator-Driven System at Kyoto University Critical Assembly, 215–43. Singapore: Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-0344-0_8.
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AbstractExcess reactivity and control rod worth are generally considered important reactor physics parameters for experimentally examining the neutron characteristics of criticality in a core, and for maintaining safe operation of the reactor core in terms of neutron multiplication in the core. For excess reactivity and control rod worth at KUCA, as well as at the Fast Critical Assembly in the Japan Atomic Energy Agency, special attention is given to analyzing the uncertainty induced by nuclear data libraries based on experimental data of criticality in representative cores (EE1 and E3 cores). Also, the effect of decreasing uncertainty on the accuracy of criticality is discussed in this study. At KUCA, experimental results are accumulated by measurements of excess reactivity and control rod worth. To evaluate the accuracy of experiments for benchmarks, the uncertainty originated from modeling of the core configuration should be discussed in addition to uncertainty induced by nuclear data, since the uncertainty from modeling has a potential to cover the eigenvalue bias more than uncertainty by nuclear data. Here, to investigate the uncertainty of criticality depending on the neutron spectrum of cores, it is very useful to analyze the reactivity of a large number of measurements in typical hard (EE1) and soft (E3) spectrum cores at KUCA.
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Li, Qiang, Zhengguo Hu, and Xuyi Huang. "Gallant Corps that Kill the Devil." In Probing into the World of Nuclei, 69–77. Singapore: Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-0715-8_5.
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Manachi, Maha, Eyad Chatty, Seham Sulaiman, and Zahera Fahed. "General Oncology Care in Syria." In Cancer in the Arab World, 265–84. Singapore: Springer Singapore, 2022. http://dx.doi.org/10.1007/978-981-16-7945-2_17.
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AbstractThe first entity dedicated to cancer was established named “Nuclear Medical Center” with a single radiotherapy unit in 1969. Since then, the concept of oncology has rapidly progressed with the establishment of a division of oncology in the University of Damascus, School of Medicine with six staff members at that time. In 2001, a National Cancer Registry was established with the help of the World Health Organization. Many civil societies related to cancer awareness, early detection, and care of patients bloomed, first being the Syrian Cancer Society.Now cancer diagnosis and treatment facilities are spread all over the county but mainly concentrated in Damascus, Lattakia, and Aleppo. All three main government related medical entities that are the Ministry of Higher Education, Ministry of Health, and the Medical Corps are involved in the process with the help of the private sector also. This progress of course was slowed due to the bloody aggression that engulfed Syria for 10 years of conflict. However, it did not halt the country’s goals and achievements.In 2006, Nuclear Medicine Centre was developed into a comprehensive institution for cancer, Al Bairouni University Hospital (ABUH) to provide free standard of care treatment for all citizens. The Syrian National Committee for cancer control (SNCCC) was established in June 2019 with a mission of strategic planning for better cancer management in collaboration with all stakeholders aiming to raise cancer services to the best possible standard in the post-war era. The chapters’ focus is to discuss cancer care services being provided in the country and future challenges that need to be addressed for high quality oncology care services in Syria.
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Piętka, Bogusław D., and Annamonika Dulewicz. "Detecting Overlapped Nuclei Regions in the Feulgen-Stained Cytological Smears." In Proceedings of the 8th International Conference on Computer Recognition Systems CORES 2013, 621–28. Heidelberg: Springer International Publishing, 2013. http://dx.doi.org/10.1007/978-3-319-00969-8_61.
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Naas, Michael. "E-Phemera: Of Deconstruction, Biodegradability, and Nuclear War." In Eco-Deconstruction. Fordham University Press, 2018. http://dx.doi.org/10.5422/fordham/9780823279500.003.0009.
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This work offers a close reading and analysis of Derrida’s 1989 essay “Biodegradables,” which contains some of Derrida’s most explicit and developed reflections on ecology and the environment, as well as on the related themes of life, survival, waste, biodegradability, remains, and what will remain—or not—after the end. A rather strange “artefact” within the Derridean corpus, “Biodegradables” is, despite its length (some sixty pages), unknown to most readers of Derrida and rarely commented on even by those who know his work well. The aim of this work is thus, in part, to save this important essay from the forgetting or the biodegradation to which it has been consigned in the secondary literature. But it is also, and more importantly, to underscore a thinking of the relationship between ecology and war—and particularly nuclear war—that can be heard haunting the essay from beginning to end. Given current concerns about the proliferation of nuclear weapons and the containment of nuclear waste, it is high time, I argue, that Derrida’s reflections about these issues be retrieved from our cultural landfill and brought back into contemporary environmental theory
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Moody, Simon J. "Military Publicists and Theories of Tactical Nuclear War." In Imagining Nuclear War in the British Army, 1945-1989, 90–116. Oxford University Press, 2019. http://dx.doi.org/10.1093/oso/9780198846994.003.0004.
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Chapter 3 considers some of the first attempts by the Army to imagine nuclear warfare. It provides a survey of the types of articles that appeared in the seven most popular service journals during the 1950s to determine how speculation about the nuclear battlefield shaped organizational thinking about the nuclear battlefield. This body of work, which constituted the emerging theory of tactical nuclear warfare, defined the parameters of the debate about the use of nuclear weapons in the land battle for the remainder of the Cold War. Critical analysis of this text, in addition to that of other published work and unpublished typescripts, suggests an officer corps that possessed the intellectual capacity for organizational innovation. The chapter maintains that the intellectual reference points for thinking about future warfare reflected the culture of an officer corps bloodied in two world wars and struggling to find a role in a changing world.
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Quaini, Andrea. "Phase Diagram of Corium Systems." In Comprehensive Nuclear Materials, 554–90. Elsevier, 2020. http://dx.doi.org/10.1016/b978-0-12-803581-8.11636-4.
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Moody, Simon J. "Conclusion." In Imagining Nuclear War in the British Army, 1945-1989, 206–14. Oxford University Press, 2019. http://dx.doi.org/10.1093/oso/9780198846994.003.0008.
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This chapter demonstrates that the British Army possessed the intellectual capacity for organizational innovation after 1945. It argues that the officer corps understood the significance of the nuclear revolution and arrived at logical conclusions as to how tactical nuclear weapons might affect land warfare. Its ability to think critically about the challenges posed by nuclear weapons calls into question the traditional narrative of the post-war British Army as an anti-intellectual organization, tied to out-of-date methods and a stagnant military doctrine. The chapter concludes that although the Army played an important role in NATO strategy, it displayed a cognitive dissonance about the logical inconsistencies of nuclear deterrence.
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Nayak, Arun, and Parimal Kulkarni. "Ex-vessel molten corium coolability." In Severe Accidents in Nuclear Reactors, 165–242. Elsevier, 2021. http://dx.doi.org/10.1016/b978-0-12-822304-8.00008-5.
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"Corium Thermodynamics and Thermophysics." In Nuclear Safety in Light Water Reactors, 657–73. Elsevier, 2012. http://dx.doi.org/10.1016/b978-0-12-388446-6.15001-4.
Повний текст джерелаТези доповідей конференцій з теми "Nuclear corpus"
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Torres-Rincon, Juan, and Edward Shuryak. "Nuclear correlations and modifications of the nucleon-nucleon potential due to the QCD critical mode." In Corfu Summer Institute 2018 "School and Workshops on Elementary Particle Physics and Gravity". Trieste, Italy: Sissa Medialab, 2019. http://dx.doi.org/10.22323/1.347.0176.
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Frolov, Kyrill N., Michel Duclot, and Christophe Journeau. "Interface Stability Criteria for Ex-Vessel Corium Solidification." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49529.
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In case of a severe accident at a nuclear power plant (NPP) involving the reactor core melt-down and the subsequent reactor pressure vessel (RPV) melt-through, confident solidification of ex-vessel corium is considered to be the imperative condition of safe retention of corium within the plant containment in the long term. The rate-determining process for solidification of ex-vessel coriums in the long-term is the chemical diffusion in the liquid phase at the solid-liquid interface. The process of chemical diffusion in the diffusive boundary layer can evolve and take on different rates, depending on the boundary conditions and the melt composition. The chemical diffusion coefficient models presented to date in the literature resort to correlations of the former to the self-diffusion coefficients among other intrinsic properties. The general feature of such models is that they predict in the tracer limit that the main diagonal coefficients tend towards the self-diffusion coefficients whereas the cross-over terms cancel out. It is revealed in this study that this particular feature is characteristic of prototypic corium melts, mixtures of several major as well as minor components. Following the corium-concrete interaction, the multicomponent ex-vessel corium melts would contain certain fractions of silica. Accordingly, they are considered in this paper as silicate oxide melts. As a first contribution, this paper comes up with a development of interface stability criteria for its application to solidification of silicate oxide melts. For ex-vessel corium melts, not far removed from equilibrium solidification conditions (long-term retention), the extension of the FICK’s law due to ONSAGER can be applied to description of the diffusive mass transfer. This formalism implies that the diffusive fluxes are linear combinations of the products of the phenomenological diffusion coefficients and the driving forces (gradients). In this regard, the near equilibrium solidification of corium containing N components is determined by a (N−1)(N−1) chemical diffusion matrix comprising the proper and cross-over coefficients. On the other hand, by comparison to the constitutional super cooling criterion of the interface stability in the course of solidification, a relationship between the macroscopic solidification conditions and the phenomenological coefficients can be established. This analysis, earlier developed for liquid metal solidification, has received attention in this study in view of its extension onto the solidification of multicomponent oxide melts. The important conclusion whatsoever is that the crossover terms can’t be neglected as easily as in the case of liquid metal alloys, particularly for silicate melts. As in prototypic corium compositions certain tracer diffusion coefficients can be relatively easily obtained from an experiment, this paper suggests an empirical method for determination of corium constituents’ self-diffusivities from controlled solidification tests.
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Min, B. T., H. D. Kim, J. H. Kim, S. W. Hong, and I. K. Park. "Particle Size Characteristics of Molten Corium Quenched in Water." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48773.
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During a hypothetical severe accident in a nuclear reactor, a steam explosion might occur when molten corium interacts with water. The strength of a steam explosion affects the integrity of the containment of a nuclear reactor and is highly dependant on the characteristics of the melt-water-steam mixture. Since a break-up and fragmentation process during a pre-mixing are important mechanisms for a steam explosion behavior and affect the debris size distribution, the particle size characteristics of quenched corium have been investigated. For several years, series of experiments have been performed using prototypical corium in the TROI test facility with a high frequency induction heating using cold crucible technology. The molten corium was discharged into the cold water and the quenched debris particles were collected, sieved and examined for the effect of a size distribution on a steam explosion. The small corium droplets do not seem to contribute to a steam explosion owing to solidification at an early stage before the explosion but the large droplets contribute to it owing to their liquid state. It was also shown that single oxides and binary oxides with an eutectic composition (UO2/ZrO2 = 70/30 at weight percentage) led to steam explosions, but a binary oxide with a non-eutectic one did not. The mass mean diameters of the debris of the steam explosive composition was less than that of the non-steam explosive composition. Zirconia was the most energetic steam-explosive material in these tests, and an eutectic composition of corium also lead to a steam explosion, but a non-eutectic composition corium hardly led to a steam explosion. The particle sizes of the molten corium participating in a steam explosion were shown to be mainly 3–6 mm depending on the material and composition.
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Ha, Kwang Soon, Hwan Yeol Kim, Jongtae Kim, and Jong Hwa Park. "An Evaluation of a Direct Corium Cooling Method for the Ex-Vessel Melt Retention." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29141.
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An evaluation of the ex-vessel core catcher system of a sample advanced light water reactor was presented. The core catcher was designed to cool down the molten corium through a combined injection of water and gas from the bottom of the molten corium, which could be effective in the reduction of rapid steam generation and in the suppression of a steam explosion. By using the MELCOR code, a scenario analysis was performed for a representative severe accident scenario of the ALWR, that is, the 6-inches large break loss of coolant accident without safe injection. The corium spreading regime was estimated by an asymptotic calculation. The composition of the molten corium, the decay power level, and the sacrificial concrete ablation depth with time were obtained by a sacrificial concrete ablation analysis. The corium cooling history in the core catcher during the coolant injection was evaluated to calculate the temporal steam generation rate by considering an energy conservation equation. These were used as the major inputs for the temporal calculations of containment pressure which was performed by using the GASFLOW code. Several cases with change of water and gas injection rates were calculated. It was confirmed that the bottom water injection system was an effective corium cooling method in the ex-vessel core catcher to preclude a possible steam explosion and to suppress the quick release of steam.
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Louie, David L. Y., Yifeng Wang, Rekha Rao, Alec Kucala, and Jessica Kruichak. "Injectable Sacrificial Material System to Contain Ex-Vessel Molten Corium in Nuclear Accidents." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81440.
Повний текст джерелаАнотація:
An ongoing Sandia National Laboratories’ (SNL) research study is evaluating a potential design of an injectable sacrificial material (SM) system that could contain and cool corium ejected from a reactor vessel lower head failure during a potential severe accident involving melting fuel at a commercial light water nuclear reactor (LWR). An injectable system could be installed at any existing LWR, without significant modification to the cavity or to the drywell pedestal region of the plant. The conceptual design under consideration is a passive system. The SM is being optimized to quickly cool the corium mixture while creating gas to form porosity in the solid, such that subsequent water flooding can penetrate the structure and provide additional cooling. The SM would form a barrier and limit corium-concrete interactions. This three-year project takes a joint experimental and computational approach. In this paper, we will first discuss the success of our small-scale experiments conducted on the interactions between the surrogate corium material (SCM) and SM, used to evaluate the injectable concept. A larger experimental study, currently underway, will further validate the injectable concept, with a focus on accurately measuring interactions. This paper details the modeling study and its progress, including modeling the experiments on a surrogate system and extending the model to bench-scale corium flow from validation experiments. The project’s modeling studies will use the SNL engineering code suite SIERRA Mechanics to understand the interaction of injectable SM and molten corium and predict corium spreading. Spreading is modeled using a level set method to track the front in conjunction with a pressure-stabilized finite element method on the fully three-dimensional mass, momentum, and energy conservation equations. Using this diffuse-interface method, the corium spreading front can be tracked and an appropriate pseudo-solidification viscosity models can be implemented to accurately model the corium spreading physics. Finally, an injectable SM delivery system is discussed along with its deployment to the six-common commercial LWR designs currently operating in the United States. At the end of this project, a simplified model based on SIERRA simulations will be developed for implementation into MELCOR, a severe reactor analysis code, developed at SNL for the U.S. Nuclear Regulatory Commission. This will allow us to demonstrate the ability of the injectable SM system to mitigate the ex-vessel corium spreading, provide containment and negate the release of radionuclides.
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Journeau, Christophe, Viviane Bouyer, Nathalie Cassiaut-Louis, Pascal Fouquart, Pascal Piluso, Gérard Ducros, Stéphane Gossé, et al. "SAFEST Roadmap for Corium Experimental Research in Europe." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60916.
Повний текст джерелаАнотація:
SAFEST (Severe Accident Facilities for European Safety Targets) is a European project networking the European corium experimental laboratories with the objective to establish coordination activities, enabling the development of a common vision and research roadmaps for the next years, and of the management structure to achieve these goals. In this frame, a European roadmap on corium experimental research has been written to define research challenges to contribute to further reinforcement of Gen II and III NPP safety. It is based on the research priorities determined by SARNET SARP group as well as those from the recently formulated in the NUGENIA Roadmap for severe accidents and the recently published NUGENIA Global Vision report. It also takes into account issues identified in the analysis of the European stress tests and from the interpretation of the Fukushima accident. 19 relevant issues related to corium have been selected during these prioritization efforts. These issues have been compared to a survey of the European corium experimental facilities and corium analysis laboratories. Finally, the coherence between European infrastructures and R&D needs has been assessed and a table linking issues and infrastructures has been derived. It shows a few lacks in EU corium infrastructures, especially in the domains of core late reflooding impact on source term, Reactor Pressure Vessel failure and corium release, Spent Fuel Pool accidents, as well as the need for a large mass (100–500 kg) prototypic corium facility.
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Passalacqua, Roberto. "Direct Containment Heating: A Solved Risk Issue." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22050.
Повний текст джерелаАнотація:
In case of a High Pressure Melt Ejection (HPME) heated gas and corium may be expelled from the bottom head of a reactor vessel reaching the containment atmosphere, leading to a Direct Containment Heating (DCH). In addition, released gases might burn (e.g. hydrogen) causing a high load of the reactor containment building. Corium dispersal phenomena also strongly affect consequences of Molten Core-Concrete Interaction (MCCI) since the corium mass, which remains within the cavity, may remarkably diminish. Several computer codes are able to simulate the response of nuclear plants during hypothetical severe accidents: MELCOR, MAAP, ESCADRE and ASTEC have the capability to describe corium slump into the reactor cavity, vessel gases blow-down and possible corium entrainment. In this paper the various steps of model development, validation, plant-specific applications, etc., are described in the attempt of establishing a risk-oriented methodology with the target of solving this particular risk-issue. ENEA mature expertise in level-2 PSA analyses shows that the DCH phenomenology can be considered a solved risk issue. The applied methodology gives also hints and/or guidelines for solving similar risk issues in current PSA (level 2) analysis.
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Tourniaire, B., J. M. Seiler, J. M. Bonnet, and M. Amblard. "Liquid Ejection Through Orifices by Sparging Gas: The PERCOLA Program." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22431.
Повний текст джерелаАнотація:
Corium coolability after a severe PWR accident involving core meltdown and RPV failure is one of the main items in nuclear safety. The case considered here is a situation in which the corium is supposed to spread over a concrete floor and is flooded by water. In this frame, many researches are performed to study the physical phenomena which may enhance the heat transfer between the corium and the water pool. Among them, the melt entrainment above the corium crust by the sparging gas released by the concrete ablation appears as a potentially efficient cooling mechanism. The main target of the experimental program PERCOLA is to provide qualitative and quantitative information on this entrainment phenomenon. The first part of this paper is devoted to a general description of the experimental program and to the presentation of the main results. In a second part, the attention is focused on the modelling of the liquid entrainment phenomenon and to the comparison between the experimental data and the calculation results of two different entrainment models.
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Khurshid, Ilyas, Amidu Muritala Alade, Yacine Addad, and Imran Afgan. "A New Insight Into Molten Corium Concrete Interaction With Concrete Ablation Analysis for Mitigation Scheme." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-65217.
Повний текст джерелаАнотація:
Abstract The study presents the use of CORQUENCH simulator to simultaneously model the molten corium, composition of concrete, molten corium heat transfer models and solve the related chemical reactions. Using this modeling technique, the chemical reaction capabilities of CORQUENCH were successfully utilized which enabled the modeling of interaction between molten corium and concrete. The developed model was validated against experimental data and the results showed that the temperature of corium, composition of concrete and water injection time have a pronounced effect on mitigating depth of ablation and reactor integrity in case of a nuclear accident. In addition, the composition of concrete is the main controlling factor to mitigate ablation in the investigated case study. An alternative to concrete, could be a certain igneous rock (tested in this study), can lead to comparatively low rates of ablation due to its high thermal resistant properties. Furthermore, the injection of water (as a cooling agent) into the reactor cavity should also be optimized to enhance corium quenching to avoid ablation via basement melt-through. As a consequence of concrete ablation by molten corium, the depth of ablation is expected to decrease to zero ablation with the suggested material in the selected case study. The concrete ablation mechanisms during MCCI are very case-dependent on the concrete solidus, liquidus and ablation temperature, respectively.
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Chen, Bin. "Core-Catcher Coolability Analysis With Coupled THEMA and RELAP Codes." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48624.
Повний текст джерелаАнотація:
Core-catcher concept is widely used as a mitigation measure for containment protection under severe accident condition. Preliminary design of core-catcher is combined with ex-vessel corium behavior and corium cooling. The loose coupling of THEMA and RELAP codes provides a convenient method to evaluation the coolability of core catcher with a realistic ex-vessel corium characteristic by couple the corium and concrete basemat parameters like spreading area heat flux and etc. calculated by THEMA code and thermal-hydraulic transient behavior of coolant which flows through the basemat and is calculated by RELAP. In this paper the calculation results of coupling methodology is compared with experiment result and simulation of finite element model. The calculation results are consistent to the BENSON test rig, which demonstrates the heat removing capability of EPR core-catcher. However, it also reveals the flow instability in coolant channel, which penalizes the core-catcher coolability. But with an improved design of core-catcher with pre-filling water and core-catcher seal, which we presented in this paper, effect of flow instability can be mitigated, especially for the inlet and outlet of coolant channel.
Звіти організацій з теми "Nuclear corpus"
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Louie, David, Yifeng Wang, Rekha R. Rao, Alec Kucala, Kyle Ross, Jessica Nicole Kruichak, and William Robert Chavez. A New Method to Contain Molten Corium in Catastrophic Nuclear Reactor Accidents. Office of Scientific and Technical Information (OSTI), October 2019. http://dx.doi.org/10.2172/1573134.
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May, C. G. Demonstration and evaluation of the CORPEX{trademark} Nuclear Decontamination Process, Technical task plan No. SR152005. Final Report. Office of Scientific and Technical Information (OSTI), April 1997. http://dx.doi.org/10.2172/537272.
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Sohal, Manohar Singh, and Larry James Siefken. A Heat Transfer Model for a Stratified Corium-metal Pool in the Lower Plenum of a Nuclear Reactor. Office of Scientific and Technical Information (OSTI), August 1999. http://dx.doi.org/10.2172/911498.
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M. S. Sohal and L. J. Siefken. A Heat Transfer Model for a Stratified Corium-Metal Pool in the Lower Plenum of a Nuclear Reactor. Office of Scientific and Technical Information (OSTI), August 1999. http://dx.doi.org/10.2172/761806.
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Webb, B. J. COBRA-IV PC: A personal computer version of COBRA-IV-I for thermal-hydraulic analysis of rod bundle nuclear fuel elements and cores. Office of Scientific and Technical Information (OSTI), January 1988. http://dx.doi.org/10.2172/5655065.
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Was, G. S. Feasibility of a novel approach for fast, economical determination of radiation damage in nuclear reactor cores. [Annual report, November 1, 1992--October 30, 1993]. Office of Scientific and Technical Information (OSTI), July 1993. http://dx.doi.org/10.2172/10192509.
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