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Artykuły w czasopismach na temat "PCTRAN"
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Liu, Bing, Jichong Lei, Jinsen Xie i Jianliang Zhou. "Development and Validation of a Nuclear Power Plant Fault Diagnosis System Based on Deep Learning". Energies 15, nr 22 (17.11.2022): 8629. http://dx.doi.org/10.3390/en15228629.
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As artificial intelligence technology has progressed, numerous businesses have used intelligent diagnostic technology. This study developed a deep LSTM neural network for a nuclear power plant to defect diagnostics. PCTRAN is used to accomplish data extraction for distinct faults and varied fault degrees of the PCTRAN code, and some essential nuclear parameters are chosen as feature quantities. The training, validation, and test sets are collected using random sampling at a ratio of 7:1:2, and the proper hyperparameters are selected to construct the deep LSTM neural network. The test findings indicate that the fault identification rate of the nuclear power plant fault diagnostic model based on a deep LSTM neural network is more than 99 percent, first validating the applicability of a deep LSTM neural network for a nuclear power plant fault-diagnosis model.
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Cheng, Yi-Hsiang, Chunkuan Shih, Show-Chyuan Chiang i Tong-Li Weng. "ICONE15-10001 Atmospheric Puff Model Developments in PCTRAN". Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_1.
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Anam, Muhammad Khoirul, Dwi Priyantoro i Syarip Syarip. "PENGATURAN POSISI CONTROL RODS UNTUK MELANJUTKAN OPERASI HTGR PASCA SCRAM DENGAN SIMULATOR PCTRAN-HTR". Jurnal Forum Nuklir 13, nr 2 (29.12.2019): 45. http://dx.doi.org/10.17146/jfn.2019.13.2.5041.
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PENGATURAN POSISI CONTROL RODS UNTUK MELANJUTKAN OPERASI HTGR PASCA SCRAM DENGAN SIMULATOR PCTRAN-HTR. Reaktivitas pada reaktor HTGR diatur dengan batang kendali (CR) yang terdiri dari 16 pasang yang terbagi menjadi dua bagian, yaitu 7 pasang di tengah teras reaktor dan 9 pasang di bagian tepi moderator. Ketika kondisi abnormal terjadi CR secara otomatis akan jatuh tersisip ke dalam teras reaktor sehingga reaktor SCRAM dan berada pada kondisi subkritis. Untuk melanjutkan operasi reaktor pasca SCRAM diperlukan analisis terkait pengaruh reaktivitas negatif dari Xenon dan suhu. Pada penelitian ini telah berhasil dilakukan simulasi penentuan posisi CR yang optimal menggunakan PCTRAN-HTR untuk melanjutkan operasi reaktor dalam dua tingkat daya, yaitu daya rendah (RDE) dengan daya 10 MWth dan daya tinggi 200 MWth. Kedua tingkat daya tersebut dicapai dengan menarik CR ke posisi tertentu sampai kondisinya kritis lagi. Hasil yang telah diperoleh menunjukkan bahwa dengan posisi CR 52 % naik sudah bisa menghasilkan kondisi superkritis untuk daya RDE dan dengan posisi 57 % dan 58 % naik, untuk daya tinggi sehingga status operasi dari start (S) bisa diganti power (P).
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Cheng, Yi-Hsiang, Chunkuan Shih, Show-Chyuan Chiang i Tung-Li Weng. "Introducing PCTRAN as an evaluation tool for nuclear power plant emergency responses". Annals of Nuclear Energy 40, nr 1 (luty 2012): 122–29. http://dx.doi.org/10.1016/j.anucene.2011.10.016.
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Ihrayz, Ezeddin A. M. Ben. "PCTRAN Westinghouse AP1000 Power Control of Pressurized Water Reactor Using Simulink of MATLAB". Open Journal of Energy Efficiency 12, nr 02 (2023): 25–35. http://dx.doi.org/10.4236/ojee.2023.122003.
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Chen, Chun-Yu, Wei-Yi Yang, Chunkuan Shih i Hui-Wen Huang. "ICONE15-10199 THE IMPROVEMENTS AND MODIFICATIONS OF EMERGENCY CORE COOLING SYSTEMS IN PCTRAN-ABWR". Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_92.
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Po, Li-Chi Cliff. "Analysis of the Rancho Seco Overcooling Event Using PCTRAN, the Personal Computer Transient Analyzer". Nuclear Science and Engineering 98, nr 2 (luty 1988): 154–61. http://dx.doi.org/10.13182/nse88-a28495.
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Saha, Arnob, Nashiyat Fyza, Altab Hossain i M. A. Rashid Sarkar. "Simulation of tube rupture in steam generator and transient analysis of VVER-1200 using PCTRAN". Energy Procedia 160 (luty 2019): 162–69. http://dx.doi.org/10.1016/j.egypro.2019.02.132.
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Wang, Ting Yi, Yu Ting Hsu, Shao Wen Chen, Jong Rong Wang, Chun Kuan Shih, Show Chyuan Chiang i Tzu Yao Yu. "The Analysis of Effectiveness of BWR/6 URG Strategies". Applied Mechanics and Materials 865 (czerwiec 2017): 701–6. http://dx.doi.org/10.4028/www.scientific.net/amm.865.701.
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After the Fukushima Daichii accidents, Taiwan Power Company developed a strategy to cope with such extended SBO (Station Blackout) cases at nuclear power plants, which called URG. The MAAP and PCTRAN were used to perform the study for Kuosheng BWR/6 nuclear power plant (NPP) ultimate response guideline (URG). The main actions of URG are the depressurization and low pressure water injection of the reactor and the venting of the containment. This study focuses to confirm the URG efficiency. The analysis results depict that following the URG, the fuel can be covered by the coolant, no exposure. It can also prevent the radiation release and the large evacuation. It indicated that Kuosheng NPP was at the safe situation. It shows that the two-step depressurizations can extend the time of the preparation of alternate water source. The minimum injection rate to prevent the fuel to expose is 192 gpm in MAAP.
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Mahal, Jannat, Altab Hossain, Intisher Al Tahmid Omi i Miskat Islam Anika. "Analysis of a pressurised water reactor-based nuclear accident using PCTRAN simulator and fuzzy expert system". International Journal of Nuclear Energy Science and Technology 14, nr 4 (2020): 310. http://dx.doi.org/10.1504/ijnest.2020.10041177.
Pełny tekst źródłaRozprawy doktorskie na temat "PCTRAN"
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Pelo, Herbert Leburu. "Evaluation of an advanced fault detection system using Koeberg nuclear power plant data / H.L. Pelo". Thesis, North-West University, 2013. http://hdl.handle.net/10394/9686.
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The control and protection system of early nuclear power plants (Generation II) have been designed and built on the then reliable analog system. Technology has evolved in recent times and digital system has replaced most analog technology in most industries. Due to safety precautions and robust licensing requirements in the nuclear industry, the analog and digital system works concurrent to each other in most control and protection systems of nuclear power plants. Due to the ageing, regular maintenance and intermittent operation, the analog plant system often gives faulty signals. The objective of this thesis is to simulate a transient using a simulator to reduce the effects of system faults on the nuclear plant control and protection system, by detecting the faults early. The following steps will be performed:
• validating the simulator measurements by simulating a normal operation,
• detecting faults early on in the system
These can be performed by resorting to a model that generates estimates of the correct sensors signal values based on actual readings and correlations among them. The next step can be performed by a fault detection module which determines early whether or not the plant systems are behaving normally and detects the fault. (Baraldi P. et al, 2010.)Thesis (MSc (Engineering Sciences in Nuclear Engineering))--North-West University, Potchefstroom Campus, 2013.
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Faresse, Nourdine. "Identification de PCTA, un nouvel effecteur de la voie de signalisation du TGF-beta". Paris 6, 2007. http://www.theses.fr/2007PA066428.
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La stimulation des cellules au TGF- entraîne l’assemblage des protéines cytoplasmiques Smad2/3 avec Smad4. Ce complexe activé se transloque dans le noyau et régule la transcription des gènes cibles du TGF-. Dans le noyau, le complexe Smad peut soit recruter un co-répresseur tel que TGIF. Le TGIF peut inhiber la transcription dépendante du TGF- par différents mécanismes. Récemment, il a été démontré que le TGIF est capable de séquestrer la protéine cytoplasmique cPML dans le noyau inhibant ainsi la phosphorylation de Smad2/3. Dans cette étude, nous avons identifié un nouveau partenaire du TGIF que nous avons nommé PCTA (PML Competitor for TGIF Association). PCTA s’associe à TGIF dans les cellules de mammifères et cette association est stimulée par le TGF-. L’expression de PCTA stimule la transcription induite par le TGF-, une activité qui est due à l’inhibition de la séquestration nucléaire de cPML à travers une compétition de liaison au TGIF. Par ailleurs, nous avons démontré que la surexpression de PCTA peut inhiber la progression tumorale. Ces résultats nous permettent de classer PCTA comme une nouvelle protéine anti-tumorale effectrice de la voie du TGF-.
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Rossi, Camila. "Os impactos dos programas condicionais de transferência de renda na oferta de trabalho dos jovens nem-nem". Universidade de São Paulo, 2017. http://www.teses.usp.br/teses/disponiveis/11/11132/tde-15082017-182203/.
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Esta pesquisa tem como objetivo estimar os efeitos dos Programas Condicionais de Transferência de Renda (PCTR) no Brasil sobre a oferta de trabalho dos jovens inseridos na situação denominada \"nem-nem\", ou seja, aqueles que não estudam não trabalham e nem estão em busca de emprego. Tendo como base o trabalho de Foguel e Barros (2010) propõe-se verificar se os programas sociais produzem o efeito indesejável de incentivar jovens moradores de domicílios beneficiários a ofertarem menos trabalho, a partir da estimação de modelos de dados em painel aplicados aos microdados da Pesquisa Nacional por Amostra de Domicílios (PNAD/IBGE). Foram construídos dois painéis formados pelo mesmo conjunto de municípios durante dois períodos: de 2001 a 2009 e de 2011 a 2014 e com o desenvolvimento deste projeto foi possível identificar o perfil dos jovens nem-nem no Brasil, os fatores associados a essa condição e a evolução nos últimos anos. Durante todo o período em análise o percentual de jovens nem-nem se manteve relativamente estável, mas apresentou comportamentos distintos entre os grupos avaliados neste trabalho: jovens do sexo masculino, feminino, jovens mães e não mães. De um modo geral, a maioria dos jovens nem-nem se concentra em domicílios de baixa renda, tem baixa escolaridade e destaca-se nessa condição as jovens com filho devido ainda a forte exigência da participação dessas mulheres nas atividades domésticas e cuidados com parentes e/ou crianças. Em relação ao impacto dos PCTR na probabilidade de o domicílio possuir jovens fora do mercado de trabalho e da escola observou-se que apenas para as jovens mães o resultado foi significativo - e nesse caso deve-se considerar a falta de disponibilidade de vagas nas creches e pré-escolas como um intensificador da vulnerabilidade das mulheres nessa condição. Por outro lado, embora os jovens do sexo masculino apresentem o menor percentual de nem-nem entre os grupos analisados, observou-se uma tendência de alta, principalmente entre os menos escolarizados. Dessa forma, políticas públicas de incentivo ao aumento de vagas nas pré-escolas para as crianças devem ser adotadas no sentido de garantir às jovens mães oportunidades de inserção no mercado de trabalho e/ou retorno aos estudos. Deve-se também adotar políticas voltadas para a redução do abandono escolar de jovens do sexo masculino, a fim de evitar círculo vicioso de baixa escolaridade e dificuldade de inserção no mercado de trabalho.This research aims to estimate the effects of the Conditional Cash Transfer (CCT) programmes in Brazil on the labor supply of NEET, that is, youths neither working nor studying or looking for a job. Based on the study of Foguel and Barros (2010), this study verifies if social programs have the undesirable effect of encouraging young people from beneficiary households to offer less work, based on the estimation of panel data models applied to microdata Pesquisa Nacional por Amostra de Domicílios (PNAD / IBGE). Two panels were built by the same set of municipalities during two periods: from 2001 to 2009 and from 2011 to 2014. It was possible to identify the profile of NEET in Brazil, the factors associated with this condition and developments in recent years. Throughout the study period, the percentage of inactive youths remained relatively stable, but presented different behaviors among the groups evaluated in this study: young men, women, young mothers and non-mothers. Generally, the majority of NEET are in on low-income households, have low schooling levels and stands out in this condition the young women with children because they have a large participation in domestic activities and group of children and relative care. Regarding the impact of PCTRs on the probability that there is NEET in the household, it was observed that only for the young mothers the result was significant - and in this case one should consider the lack of availability of day care centers and pre-schools as an intensifier of women\'s vulnerability in this condition. On the other hand, although young males had the lowest percentage of idles among the groups analyzed, there was an increase trend among the less educated youths. Thus, public policies that increase the number of pre-schools for children should be adopted in order to guarantee young mothers\' opportunities to enter into the labor market and/or to return to school. Moreover, it is recommended the implementation of policies to reduce school drop-outs for young males, in order to avoid the vicious cycle of low schooling and difficulty to entering in the labor market.
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Enel, Morgane. "Nouvelles perspectives pour les complexes de lanthanides dérivés du squelette PCTA[12] : synthèse, propriétés photophysiques et relaxométriques". Thesis, Toulouse 3, 2017. http://www.theses.fr/2017TOU30337/document.
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Le ligand PCTA[12], un macrocycle à 12 chaînons intégrant dans sa structure un noyau pyridine intracyclique et trois groupements aminoacide acétique, constitue une alternative intéressante aux ligands traditionnels tels que le DTPA, le NOTA ou le DOTA pour des applications en imagerie biomédicale. Sa potentialité à agir comme agent de contraste pour l'IRM a déjà été reportée, et certains de ses dérivés ont été évalués avec succès pour l'imagerie optique ou nucléaire. En raison de ces résultats encourageants, la synthèse de familles de dérivés du ligand PCTA[12] a été entreprise en vue de l'amélioration des propriétés des différents complexes Ln(III) (Ln = Eu, Gd, Tb) qui leurs sont issus. Dans un premier temps, la synthèse multi-étape du PCTA[12] a été reconsidérée et a permis d'atteindre un rendement global de 64% en ligand contre un rendement maximum de 36% pour les méthodologies classiques. La stratégie développée a, par la suite, été employée à la synthèse de ligands à fonctions mixtes acétate/amide ou acétate/phosphinate, mais également de ligands bifonctionnels chélatants porteurs de fonctions hydroxyle, ester, acide carboxylique, hydroxyméthyle ou amine. L'introduction de groupements chromophores de type carbostyrile et benzimidazole en position para de la pyridine a pu être réalisée et une amélioration des propriétés photophysiques a été observée dans le cas du complexe d'europium à motif benzimidazole ((λex = 322 nm et Փ = 9,2%). La dernière modification a consisté en la substitution du noyau pyridine du ligand PCTA[12] par un noyau phénol. La synthèse du composé désiré conduit à la formation conjointe du dimère correspondant. Une amélioration conséquente des propriétés relaxométriques (r1 = 5,7 s-1.mM-1 et τM = 3,1 ns) et fluorescentes (Փ = 22%) des complexes Gd(III) et Tb(III) de la forme monomère a été mise en évidence. Le complexe de terbium du macrocycle dimère analogue a, quant à lui, permis l'obtention d'un excellent rendement quantique de fluorescence de 43% en milieu aqueuxThe PCTA[12] ligand is a 12-membered macrocycle containing an intracyclic pyridine ring and three amino acid acetic groups in its structure, and is an interesting alternative to traditional ligands such as DTPA, NOTA or DOTA for biomedical imaging applications. Its potential to act as a contrast agent for MRI has already been reported, and some of its derivatives have been successfully evaluated for optical or nuclear imaging. Because of these encouraging results, the synthesis of families of derivatives of the PCTA[12] ligand has been undertaken in order to improve the properties of their derived Ln (III) complexes (Ln = Eu, Gd, Tb). At first, the multi-step synthesis of PCTA[12] was reconsidered and able to reach an overall yield of 64% ligand against a maximum yield of 36% for conventional methodologies. The strategy developed was subsequently used to synthesize acetate/amide or acetate/phosphinate mixed-function ligands, but also chelating bifunctional ligands bearing hydroxyl, ester, carboxylic acid, hydroxymethyl or amine functions. The introduction of carbostyril or benzimidazole chromophores at the para-position of the pyridine moiety has been carried out and an improvement in the photophysical properties was observed in the case of the benzimidazole europium complex ((λex = 322 nm and Փ = 9.2%). The last modification consisted in the substitution of the pyridine moiety of the PCTA[12] ligand by a phenol core. The synthesis of the desired compound leads to the formation of the corresponding dimer. A consequent improvement of the relaxometric (r1 = 5.7 s-1.mM-1 and τM = 3.1 ns) and fluorescence (Փ = 22%) properties of the Gd(III) and Tb(III) complexes of the monomeric form has been demonstrated. The terbium complex of the dimeric macrocycle has, for its part, made it possible to obtain an excellent fluorescence quantum yield of 43% in aqueous medium
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Yong-Sang, Jennyfer. "Synthèse de nouveaux agents chélatants PCTA du 68Ga - Application au marquage de lipoprotéines pour l’imagerie TEP de la plaque d’athérosclérose". Thesis, La Réunion, 2017. http://www.theses.fr/2017LARE0062.
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Les maladies cardiovasculaires représentent la première cause de mortalité et de morbidité dans le monde. L’athérosclérose est à l’origine de 50 % des décès dans les pays industrialisés. Cette pathologie multifactorielle est caractérisée par l’accumulation de lipides dans la paroi des artères formant une plaque d’athérome. Les manifestations cliniques dues à la rupture de cette plaque dépendent du territoire vasculaire touché, allant de l’accident vasculaire cérébral ischémique à l’infarctus du myocarde. Pour pallier ce problème majeur de santé publique dont la prévalence est deux fois supérieure à l’Île de La Réunion par rapport à la Métropole, nous proposons de développer de nouveaux outils de diagnostic par l’imagerie utilisant la tomographie par émission de positon (TEP). À ce jour, aucun outil ne permet la détection précoce de ces plaques d’athérome. Nous avons choisi de marquer deux types de lipoprotéines (HDL et LDL) pour imager ces plaques. Elles possèdent toutes les deux des rôles opposés mais ont en commun un tropisme avéré pour la plaque d’athérome. Nos travaux ont permis la synthèse puis le radiomarquage d’un nouvel agent chélatant PCTA du Gallium 68 couplé à un biovecteur phospholipidique, la 1,2-distéaroyl-sn-glycéro-3-phosphoéthanolamine (DSPE), qui a ensuite été insérée au niveau de la couche lipidique des lipoprotéines afin d’étudier sa biodistribution dans des modèles in vivo murin et ex vivo humain d’athéroscléroseCardiovascular disease is the leading cause of mortality and morbidity worldwide. Atherosclerosis accounts for 50% of deaths in industrialized countries. This multifactorial pathology is characterized by the accumulation of lipids within the arterial wall forming an atheromatous plaque. Clinical manifestations due to plaque rupture depend on the affected vascular territory, ranging from ischemic stroke to myocardial infarction. In order to overcome this major public health problem, which is twice more prevalent in Reunion Island relative to Mainland France, we aimed at developing new diagnostic tools using tomography by positron emission (PET) imaging. To date, no specific tool allows the early detection of atheromatous plaques. We chose to label two types of lipoproteins (HDLs and LDLs) in order to image these plaques. They both have opposite roles but have in common a proven tropism for atheromatous plaque. Our work allowed the synthesis and the radiolabelling of a new Gallium 68 PCTA chelating agent coupled to the phospholipid biovector, 1,2-distearoyl-sn-glycero-3phosphoethanolamine (DSPE), which was then inserted in the lipid layer of lipoproteins in order to study its biodistribution in mouse in vivo and in human ex vivo models of atherosclerosis
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Feuillâtre, Hélène. "Détermination automatique de l'incidence optimale pour l'observation des lésions coronaires en imagerie rotationnelle R-X". Thesis, Rennes 1, 2016. http://www.theses.fr/2016REN1S039/document.
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Les travaux de cette thèse s’inscrivent dans le cadre du planning de traitements minimalement invasifs des lésions des artères coronaires. Le cardiologue réalise un examen coronarographique, puis dans la continuité, une angioplastie transluminale. L’angiographie rotationnelle à rayons X permet de visualiser sous différentes incidences 2D la lumière des artères coronaires sur plusieurs cycles cardiaques et aussi d’obtenir une reconstruction 3D+T des arbres coronaires. A partir de cette séquence, notre objectif est de déterminer automatiquement une incidence optimale 2D du segment sténosé compatible avec les angles du C-arm afin d’aider le cardiologue lors de l’intervention.Différentes étapes sont considérées pour calculer la position angulaire optimale du C-arm. Afin de suivre la zone de lésion durant le cycle cardiaque, une première méthode est proposée pour mettre en correspondance tous les arbres de la séquence 3D+T. Tout d’abord, un appariement deux à deux des arbres successifs est réalisé afin de construire un arbre d’union. Ces derniers sont ensuite fusionnés afin d’obtenir un arbre mosaïque représentant l’arbre le plus complet de la séquence. L’utilisation de mesures de similarités géométriques et hiérarchiques ainsi que l’insertion de nœuds artificiels permet de prendre en compte les différents mouvements non-rigides des artères coronaires subits au cours du cycle cardiaque et les variations topologiques dû à leurs extractions. Cet appariement nous permet de proposer une deuxième méthode afin d’obtenir une vue angiographique 2D optimale de la zone de lésion tout le long du cycle cardiaque. Cette incidence est proposée spécifiquement pour trois types de région d’intérêt (segment unique, segment multiple ou bifurcation) et est calculée à partir de quatre critères (raccourcissement, chevauchement interne et externe ou angle d’ouverture de bifurcation). Une vue 2D déployée du segment projeté avec le moins de superposition avec les structures vasculaires avoisinantes est obtenue. Nous donnons également la possibilité au cardiologue d’avoir une incidence optimale privilégiant soit le déploiement du stent ou soit le guidage d’outils de la racine de l’arbre à la zone sténosée. Nos différents algorithmes ont été évalués sur une séquence réelle de 10 phases segmentées à partir d’un CT et de 41 séquences simuléesThe thesis work deals with the planning of minimally invasive surgery of coronary artery lesions. The physician performs a coronarography following by a percutaneous transluminal angioplasty. The X-ray rotational angiography permits to visualize the lumen artery under different projection angles in several cardiac cycles. From these 2D projections, a 3D+T reconstruction of coronary arteries can be obtained. Our goal is to determine automatically from this 3D+T sequence, the optimal angiographic viewing angle of the stenotic segment. Several steps are proposed to compute the optimal angular position of the C-arm. Firstly, a mosaic-based tree matching algorithm of the 3D+T sequence is proposed to follow the stenotic lesion in the whole cardiac cycle. A pair-wise inexact tree matching is performed to build a tree union between successive trees. Next, these union trees are merged to obtain the mosaic tree which represents the most complete tree of the sequence. To take into account the non-rigid movement of coronary arteries during the cardiac cycle and their topology variations due to the 3D reconstruction or segmentation, similarity measures based on hierarchical and geometrical features are used. Artificial nodes are also inserted. With this global tree sequence matching, we propose secondly a new method to determine the optimal viewing angle of the stenotic lesion throughout the cardiac cycle. This 2D angiographic view which is proposed for three regions of interest (single segment, multiple segment or bifurcation) is computed from four criteria: the foreshortening, the external and internal overlap and the bifurcation opening angle rates. The optimal view shows the segment in its most extended and unobstructed dimension. This 2D view can be optimal either for the deployment of the stent or for the catheter guidance (from the root to the lesion). Our different algorithms are evaluated on real sequence (CT segmentation) and 41 simulated sequences
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張進捷. "PCTRAN Model Modification and Comparisons for KuoSheng Operational Transients". Thesis, 2012. http://ndltd.ncl.edu.tw/handle/92976002285453653284.
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碩士國立清華大學
核子工程與科學研究所
100
PCTRAN code, developed by the MST Research, can simulate nuclear power plant operation and transient accidents. The software has introduced different versions for various nuclear power plant types, including PCTRAN KuoSheng version for simulation of KuoSheng Nuclear Power Station (KSNPS). Actual operating data from Kuosheng has not been used for verifications of PCTRAN KuoSheng model yet. Therefore, we took three transient cases of start-up tests prior to commercial operation for KSNPS to verify PCTRAN KuoSheng model. They are (1) load rejection test in 100% power, (2) recirculation pump trip test in 68% power, and (3) feedwater pump trip in 96% power. For completeness, we then added two transient cases simulated in KSNPS Simulator. They are (1) manual scram in 100% power, (2) all of Main Steam Isolation Valves (MSIV) closing in the same time in 100% power. From comparisons of simulation results of PCTRAN KuoSheng and actual data of above transient cases, we identified the causes for the discrepancies. Then, we corrected the parameters and modified program of PCTRAN KuoSheng and conducted simulations of five transient cases again. In conclusion, the modified PCTRAN KuoSheng has shown its acceptable consistency compared with the existing data from KuoSheng Nuclear Power Station.
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Lin, Fangcheng, i 林芳正. "Investigations of Control system and Thermal-Hydraulic modeling in PCTRAN". Thesis, 2003. http://ndltd.ncl.edu.tw/handle/56601177843256355459.
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碩士國立清華大學
工程與系統科學系
91
ABSTRACTS PCTRAN is a reactor transient and accident simulation software program that operates on a personal computer. It was developed by Taiwan Power Company and Micro-Simulation Technology (MST). PCTRAN have high resolution color display and interactive control capability enable versatile, high speed simulation, yet low cost transient simulation. We can use it to simulate various transients and events in order to assess the safety of nuclear power plants. In the present thesis, we will descriptive all of the PCTRAN model structure that it is include source code, VB interface and the data base structure correlation. We also detail investigations into PCTRAN system control blocks. Due to the fact that PCTRAN can not include all of the plant systems and transient initiation events, the operator should be familiar with plant basics in order to complete a reasonable and logical PCTRAN simulation run with its built-in existing functions. Under current basic PCTRAN structures, we can add or modify necessary VB objects and source codes to develop a proper tool for transient analysis in a nuclear power plant.
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JANBANDHU, ANKIT H. "SIMULATION AND COMPARISON OF DIFFERENT MALFUNCTIONS OF A PRESSURIZED WATER REACTOR USING PCTRAN". Thesis, 2016. http://dspace.dtu.ac.in:8080/jspui/handle/repository/15071.
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Nuclear power has the characteristics of large unit capacity and high security requirements, therefore they are prone to have an impact, and even threaten the safe operation of the power grid since the nuclear power plants are connected to the grid. The nuclear power industry relies more heavily on theoretical analysis of design and safety features than does any other high-technology industry. Before the Three Mile Island accident, much of the safety analysis of commercial reactors focused on a hypothetical accident involving the rupture of a large pipe supplying cooling water to the reactor core. The design basis loss of coolant accident was thought to be worse than any event that would ever happen. Water and steam would be expelled rapidly at the break and the core would be left temporarily uncovered and poorly cooled. Transient analysis of a pressurized water reactor (PWR) using the Personal Computer Transient Analyzer (PCTRAN) simulator was carried out. PCTRAN analyses consists a synergistic integration of a numerical model i.e. a full scope high fidelity simulation system which uses point reactor neutron kinetics model and movable boundary two phase fluid models to simplify the calculation of the program, so it could achieve real-time simulation on a personal computer. Here various types of malfunctions such as Inadvertent Rod Insertion, Loss of coolant Accident with Turbine Trip, Fuel Handling accident in Auxiliary Building, Loss of Coolant Accident with Locked Rotor, and Turbine Trip were simulated. Furthermore, all these malfunctions were carried out at 100% power at the end of cycle and at 75% power at the end of cycle. Again, each malfunction has been compared in different power levels which are very useful for concluding, so that we could know that at which power level the power plant should be operated and is least affected by the above malfunctions. By performing these simulations, the upcoming fault analysis has already been done so that these can be prevented during the practical conditions and can ensure the safe and continuous working of the plant.
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Yang, Chao Yu, i 楊朝裕. "PCTRAN Transient Analysis of KuoSheng Nuclear Power Plant and Code Improvements". Thesis, 2005. http://ndltd.ncl.edu.tw/handle/13622868411907262513.
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碩士國立清華大學
工程與系統科學系
93
ABSTRACT This thesis used PCTRAN, a fast-running nuclear power plant simulation code, to analyze potential transients and accidents of the second nuclear power plant in Taiwan. The signals and mechanisms generated when accidents occur are also clarified. Therefore, this work is mainly separated into two parts, which are the improvements of PCTRAN code and the case studies. In the first part, some improvements to the code were made referring to the KSNPP’s publications. The improvements include the water levels, HPCS setpoints, SRV setpoints, turbine trip logic, and turbine stop valve logic. In the second part, this modified code is used for case studies throughout this thesis. The case studies investigated the change of signals and parameters, such as scram, turbine trip, feedwater trip, SRV open, and parameters which are reactor power, mean steam flow, feedwater flow, and water levels.
Książki na temat "PCTRAN"
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Rösch, Katharina. Mutationssuche im Prostate Carcinoma Tumor Antigen 1 (PCTA-1) Gen, einem Kandidatengen für das hereditäre prostatakarzinom beim Mensch, lokalisiert auf dem PcaP Locus in 1q42.3-43. [S.l.]: [s.n.], 2001.
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Chahar, Sombir. Intraday Trading Strategies Without Indicators for Crude Oil: Pure Price Pction. Independently Published, 2020.
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Books, Golden. Miss America Pazazz Pctr/Poste. Golden books, 1990.
Znajdź pełny tekst źródłaCzęści książek na temat "PCTRAN"
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Kucukboyaci, Vefa, Alireza Haghighat i Glenn E. Sjoden. "Performance of PENTRAN™ 3-D Parallel Particle Transport Code on the IBM SP2 and PCTRAN Cluster". W Recent Advances in Parallel Virtual Machine and Message Passing Interface, 36–43. Berlin, Heidelberg: Springer Berlin Heidelberg, 2001. http://dx.doi.org/10.1007/3-540-45417-9_10.
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Bures, Miroslav. "PCTgen: Automated Generation of Test Cases for Application Workflows". W New Contributions in Information Systems and Technologies, 789–94. Cham: Springer International Publishing, 2015. http://dx.doi.org/10.1007/978-3-319-16486-1_78.
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Ghirelli, M., E. Aggazzotti Cavazza, F. Mattioli, A. Ghidini, S. Bottero i L. Presutti. "Step-by-Step Partial Cricotracheal Resection (PCTR)". W Atlas of Airway Surgery, 83–97. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-49739-6_7.
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Parenti, Susanna. "Spectral Diagnostics of Cool Prominence and PCTR Optically Thin Plasmas". W Solar Prominences, 61–77. Cham: Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-10416-4_3.
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Serruys, Patrick W., Victor Ulmans, Guy R. Heyndrickx, Marcel v.d. Brand, Pim J. De Feyter, William Wijns, Brian Jaski i Paul G. Hugenholtz. "Elective PCTA of totally occluded coronary arteries not associated with acute myocardial infarction: short and long term results". W Improvement of Myocardial Perfusion, 150–65. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5032-0_20.
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"9. The Preparatory Committee for the Tibet Autonomous Region (PCTAR)". W A History of Modern Tibet, Volume 3, 282–305. University of California Press, 2019. http://dx.doi.org/10.1525/9780520956711-015.
Pełny tekst źródłaStreszczenia konferencji na temat "PCTRAN"
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Racheal, Suubi, Yongkuo Liu, Miyombo Ernest i Abiodun Ayodeji. "A Systematic Review of PCTRAN-Based Pressurized Water Reactor Transient Analysis". W 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-65663.
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Abstract The impact of nuclear accidents has been a topic of debate since the construction of the first nuclear reactor, and still stands as a key issue of public concern. Several codes and simulators have been used to study the transient progression in pressurized water reactors, and to evaluate the technical measures adopted to scale down the risk of accidents. However, some of these codes are not suitable for multipurpose research and training as they require significant user expertise, leading to analysis uncertainties largely from the code user effect. This paper presents a bird-eye view of one of the most widely used nuclear reactor transient analyzer — the Personal Computer Transient Analyzer (PCTRAN). This paper discusses the comparative advantages of the simulator from the users’ perspective, with specific attention to its utilization both for research and training. The paper also demonstrates the ease of usage by simulating common transient in a pressurized water reactor. Finally, observations and possible improvements to the code to increase its usability in research, education and training are discussed. This work aims to evaluate the robustness of the simulator towards better utilization for research and training, especially in nuclear newcomer countries.
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Huang, Hui-Wen, Chunkuan Shih, Swu Yih, Yen-Chang Tzeng i Ming-Huei Chen. "Digital Instrumentation and Control Failure Events Derivation and Analysis by Frame-Based Technique". W 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89117.
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A frame-based technique, including physical frame, logical frame, and cognitive frame, was adopted to perform digital I&C failure events derivation and analysis for generic ABWR. The physical frame was structured with a modified PCTran-ABWR plant simulation code, which was extended and enhanced on the feedwater system, recirculation system, and steam line system. The logical model is structured with MATLAB, which was incorporated into PCTran-ABWR to improve the pressure control system, feedwater control system, recirculation control system, and automated power regulation control system. As a result, the software failure of these digital control systems can be properly simulated and analyzed. The cognitive frame was simulated by the operator awareness status in the scenarios. Moreover, via an internal characteristics tuning technique, the modified PCTran-ABWR can precisely reflect the characteristics of the power-core flow. Hence, in addition to the transient plots, the analysis results can then be demonstrated on the power-core flow map. A number of postulated I&C system software failure events were derived to achieve the dynamic analyses. The basis for event derivation includes the published classification for software anomalies, the digital I&C design data for ABWR, chapter 15 accident analysis of generic SAR, and the reported NPP I&C software failure events. The case study of this research includes (1) the software CMF analysis for the major digital control systems; and (2) postulated ABWR digital I&C software failure events derivation from the actual happening of non-ABWR digital I&C software failure events, which were reported to LER of USNRC or IRS of IAEA. These events were analyzed by PCTran-ABWR. Conflicts among plant status, computer status, and human cognitive status are successfully identified. The operator might not easily recognize the abnormal condition, because the computer status seems to progress normally. However, a well trained operator can become aware of the abnormal condition with the inconsistent physical parameters; and then can take early corrective actions to avoid the system hazard. This paper also discusses the advantage of Simulation-based method, which can investigate more in-depth dynamic behavior of digital I&C system than other approaches. Some unanticipated interactions can be observed by this method.
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Chen, Xirong, Pengyu Chen, Jinsen Xie, Wenbin Xiong, Yanan Zhao, Wenjie Zeng i Tao Yu. "PCTran-Cloud: an Accident Simulator for Nuclear Power Plants Based on Cloud Technology". W 2022 4th International Conference on Artificial Intelligence and Advanced Manufacturing (AIAM). IEEE, 2022. http://dx.doi.org/10.1109/aiam57466.2022.00129.
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Hasan Tanim, Md Mehedi, Md Feroz Ali, Md Asaduzzaman Shobug i Shamsul Abedin. "Analysis of Various types of Possible Fault and Consequences in VVER-1200 using PCTRAN". W 2020 International Conference for Emerging Technology (INCET). IEEE, 2020. http://dx.doi.org/10.1109/incet49848.2020.9153969.
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Huang, Hui-Wen, Chunkuan Shih, Hung-Chih Hung, Shu-Chuan Chen, Li-Hsin Wang i Ben-Ching Liao. "Development of ABWR Feedwater Pump and Controller Model". W 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48955.
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This work developed a stand-alone ABWR (Advanced Boiled Water Reactor) feedwater pump and controller model which was incorporated with a simplified reactor vessel and steam line model. The purpose of this work is to improve the existing model in PCTran-ABWR, a nuclear power plant (NPP) simulation code. INER has been using this computer code as an NPP simulation model for Software Safety Analysis (SSA) and software Fault Injection (FI) of digital instrumentation and control (I&C) research for years. The feedwater pump model includes three turbine-driven feed water pumps and one motor-driven feed water pump. The feedwater controller includes a one-element / three-element water level controller and a specific feedwater speed controller for each feedwater pump. The feed water turbines are driven by the steam from main steam line. As a result, the reactor dome pressure can affect the driving force of the three turbine-driven feed water pumps. It means if the dome pressure becomes low enough, the turbine-driven feed water pumps cannot function normally. The reactor dome pressure transient also affects the pressure difference of feedwater pump discharge pressure and the reactor dome pressure, which can actually affect the feedwater flow rate and reactor water level. The time-lag of feedwater control valve is also considered in this model. Hence, the slower response of turbine-driven feed water pump than that of motor-driven feed water pump can be observed. A number of test cases namely step change of dome pressure, load rejection, and four tests of feedwater pumps transfer were performed in this work to demonstrate the feasibility of dynamic response of this model. Therefore, this model will be implemented into the existing PCTran-ABWR plant simulation code to improve the response of feedwater pump and controller model. This stand-alone model can also be a feedwater control strategy tool to observe the possible responses of various feedwater control architectures.
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Juste Vidal, Belen Jeanne, Rafael Miró, Teresa Barrachina i Gumersindo Verdú. "Capacitación en funcionamiento y seguridad de las centrales nucleares mediante el aprendizaje activo basado en simuladores de reactores". W INNODOCT 2022. Valencia: Editorial Universitat Politècnica de València, 2023. http://dx.doi.org/10.4995/inn2022.2022.15712.
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En la última década, y principalmente debido al avance tecnológico, se ha demostrado la efectividad de explorar nuevas estrategias de enseñanza. La tendencia más extendida es proporcionar un papel más "activo" a los estudiantes para promover su motivación de aprendizaje y mejorar su retención de contenidos. Entre otras técnicas, cabe destacar el uso de simuladores computacionales, que permiten potenciar la implicación de los alumnos en el aprendizaje. Esta metodología se está aplicando en una asignatura del Máster Universitario en Ingeniería Industrial de la UPV. El objetivo principal es optimizar la enseñanza a través de la "experiencia", y se ha demostrado cómo esta práctica tiene un enfoque más efectivo que las clases teóricas para enseñar los fundamentos de la tecnología nuclear. La biblioteca de simuladores de reactores PCTRAN utilizada, incluye modelos de centrales nucleares PWR y BWR convencionales y avanzadas. Basados principalmente en los modelos convencionales, se llevan a cabo diferentes ejercicios enfocados en el funcionamiento normal del reactor, maniobras de caída de potencia y apagado del reactor, diferentes transitorios de operación, así como la simulación de accidentes. Estos ejercicios ayudan a los estudiantes a aprender las complejas interacciones del sistema dentro de una planta de energía nuclear, alcanzando un aprendizaje activo, que en última instancia aumenta la tasa de retención.---------------------------------------------------------In the last decade, and mainly due to technological advancement, the effectiveness of exploring new teaching strategies has been demonstrated. The most widespread trend is to provide a more "active" role to students to promote their learning motivation and to improve their content retention. Among other techniques, it is worth mentioning the use of computational simulators, which allow to enhance the involvement of students in learning. This methodology is being applied in one subject of the Master's Degree in Industrial Engineering of the UPV. The main goal is to optimize teaching through "experience," and it has been shown how this practice has a more effective approach than theoretical classes to teach the fundamentals of nuclear technology. The library of PCTRAN (Personal Computer Transient Analyzer) reactor simulators used includes models of conventional and advanced PWR (Pressure Water Reactor) and BWR (Boiling Water Reactor) nuclear power plants. Based mainly on conventional models, different exercises are carried out focused on the normal operation of the reactor, maneuvering of reactor power drop and shutdown, different operating transients and simulation of accidents. These exercises help students learn the complex system interactions within a nuclear power plant, achieving active learning, which ultimately increases the retention rate.
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Juste Vidal, Belen Jeanne, Rafael Miró, Teresa Barrachina i Gumersindo Verdú. "Capacitación en funcionamiento y seguridad de las centrales nucleares mediante el aprendizaje activo basado en simuladores de reactores". W INNODOCT 2022. Valencia: Editorial Universitat Politècnica de València, 2023. http://dx.doi.org/10.4995/inn2022.2023.15712.
Pełny tekst źródłaStreszczenie:
En la última década, y principalmente debido al avance tecnológico, se ha demostrado la efectividad de explorar nuevas estrategias de enseñanza. La tendencia más extendida es proporcionar un papel más "activo" a los estudiantes para promover su motivación de aprendizaje y mejorar su retención de contenidos. Entre otras técnicas, cabe destacar el uso de simuladores computacionales, que permiten potenciar la implicación de los alumnos en el aprendizaje. Esta metodología se está aplicando en una asignatura del Máster Universitario en Ingeniería Industrial de la UPV. El objetivo principal es optimizar la enseñanza a través de la "experiencia", y se ha demostrado cómo esta práctica tiene un enfoque más efectivo que las clases teóricas para enseñar los fundamentos de la tecnología nuclear. La biblioteca de simuladores de reactores PCTRAN utilizada, incluye modelos de centrales nucleares PWR y BWR convencionales y avanzadas. Basados principalmente en los modelos convencionales, se llevan a cabo diferentes ejercicios enfocados en el funcionamiento normal del reactor, maniobras de caída de potencia y apagado del reactor, diferentes transitorios de operación, así como la simulación de accidentes. Estos ejercicios ayudan a los estudiantes a aprender las complejas interacciones del sistema dentro de una planta de energía nuclear, alcanzando un aprendizaje activo, que en última instancia aumenta la tasa de retención.---------------------------------------------------------In the last decade, and mainly due to technological advancement, the effectiveness of exploring new teaching strategies has been demonstrated. The most widespread trend is to provide a more "active" role to students to promote their learning motivation and to improve their content retention. Among other techniques, it is worth mentioning the use of computational simulators, which allow to enhance the involvement of students in learning. This methodology is being applied in one subject of the Master's Degree in Industrial Engineering of the UPV. The main goal is to optimize teaching through "experience," and it has been shown how this practice has a more effective approach than theoretical classes to teach the fundamentals of nuclear technology. The library of PCTRAN (Personal Computer Transient Analyzer) reactor simulators used includes models of conventional and advanced PWR (Pressure Water Reactor) and BWR (Boiling Water Reactor) nuclear power plants. Based mainly on conventional models, different exercises are carried out focused on the normal operation of the reactor, maneuvering of reactor power drop and shutdown, different operating transients and simulation of accidents. These exercises help students learn the complex system interactions within a nuclear power plant, achieving active learning, which ultimately increases the retention rate.
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Huang, Hui-Wen, Chunkuan Shih, Hung-Chih Hung, Kai-Lan Chang, Shu-Chuan Chen, Yu-Jen Pan, Mao-Sheng Tseng, Ming-Huei Chen i Tsung-Chieh Cheng. "Development and D3 Application of ABWR Feedwater System Model". W 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75104.
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This work developed an Advanced Boiling Water Reactor (ABWR) feedwater pump and controller model, which was incorporated into Personal Computer Transient Analyzer (PCTran)-ABWR, a nuclear power plant simulation code. The feedwater pump model includes three turbine-driven feedwater pumps and one motor-driven feedwater pump. The feedwater controller includes a one-element / three-element water level controller and a specific feedwater speed controller for each feedwater pump. The performance tests, including inadvertent closure of all turbine control valves and one feedwater pump trip at 100% power, demonstrate the feasibility of dynamic response of incorporated model. Furthermore, a diversity and defense-in-depth analysis is performed to demonstrate the feasibility for motor-driven feedwater pump as an Emergency Core Cooling System (ECCS) automatic diverse back-up. In Lungmen Nuclear Power Plant (NPP), a diverse manual initiation means for the High Pressure Core Flooder (HPCF) loop C is designed as the back-up of digitalized Engineered Safety Features Actuation System (ESFAS). If the Motor-Driven Feedwater Pump (MDFWP) can be an automatic digital diverse back-up for ESFAS, Lungmen NPP would be more robust to defend against software common cause failure (CCF).
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Sun, Pengpeng, Yong Liu, Guohua Wu i Zhiyong Duan. "Research on Fault Diagnosis of Reactor Coolant Accident in Nuclear Power Plant Based on Radial Basis Function and Fuzzy Neural Network". W 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16138.
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Abstract Nuclear power plants (NPPs) are widely used in the world. After three nuclear accidents, people propose higher of the safety and reliability on NPPs. Reactor coolant system (RCS) in the NPP directly affects whether the heat can be exported and radioactivity can be inclusive. It plays an important role of the NPPs safety. So, it is great significance of fault diagnosis for RCS in NPP. Although many scholar had carried out research on fault diagnosis of NPPs, different networks may lead to different results in a system. Therefore, this paper chooses a system and uses different neural networks (NN) for comparative analysis which can provide advice for follow-up research. In the paper, RCS has been analyzed and typical fault have been analyzed through PCTRAN simulator. On this basis, two kinds of NN combined with fuzzy systems: radial basis function (RBF) and back propagation (BP) are used for fault diagnosis and comparative analysis. Loss of coolant accident, single pump failure, loss of feed water are set for simulation experiment. Simulation experiment shows that BP network’s hidden layer nodes is less than RBF-NN, but iteration speed of BP network is faster; accuracy of fault diagnosis based on BP-NN is higher than RBF-NN; fuzzy-NN for fault diagnosis is faster than NN.
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Tseng, Mao-Sheng, Hui-Wen Huang, Ming-Huei Chen, Tsung-Chieh Cheng, Hsiang-Han Chung, Tzeng-Hsi Liu, Wen-Lung Yang, Ming-Chung Lee i Mao-Yuan Chen. "The Application of FPGA for Anticipated Transients Without Scram Mitigation System". W 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29029.
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The digitalized Instrumentation and Control (I&C) system of nuclear power plants (NPP) could provide operator easily Human-Machine Interface (HMI) and more powerful overall operation capability. However, some software errors may cause a kind of Common Cause Failure (CCF). As a consequence, the event of Anticipated Transients Without Scram (ATWS) will occur. In order to assure that the plant can be shutdown safely and to follow the requirements of 10CFR50.62, the utility builds up various ATWS mitigation features in NPP. The features include Fine Motion Control Rod Drive Run In, Alternate Rod Insertion, Standby Liquid Control System, Reactor Internal Pump Trip or Runback, Feedwater Flow Runback and Inhibition of Automatic Depressurization System. This research developed an evaluation method of diverse back-up means for computerized I&C system. A diverse backup of digital I&C system is the most important means to defend against CCF and un-detectable software faults. Institute of Nuclear Energy Research (INER) is developing a computerized I&C test facility, which is incorporated a commercial grade I&C systems with Personal Computer Transient Analyzer (PCTran)/Advanced Boiling Water Reactor (ABWR), a NPP simulation computer code. By taking the technology of Field Programmable Gate Array (FPGA) to implement the methods of ATWS mitigation, the research built up a diverse back-up of digital I&C system to expect to defend against CCF and undetectable software faults. According to the testing and evaluation, the work can be achieved the analysis of Diversity and Defense-in-Depth (D3).