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Relevant bibliographies by topics / U 238-u 235

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Academic literature on the topic 'U 238-u 235'

Author: Grafiati

Published: 4 May 2024

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Journal articles on the topic "U 238-u 235"

1

Boulyga, Sergei F., Andreas Koepf, Stefanie Konegger-Kappel, Zsuzsanna Macsik, and Guillaume Stadelmann. "Uranium isotope analysis by MC-ICP-MS in sub-ng sized samples." Journal of Analytical Atomic Spectrometry 31, no. 11 (2016): 2272–84. http://dx.doi.org/10.1039/c6ja00238b.

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This study describes the multi-collector inductively coupled plasma mass spectrometry (MC-ICP-MS) method for the determination of n(²³³U)/n(²³⁸U), n(²³⁴U)/n(²³⁸U), n(²³⁵U)/n(²³⁸U), and n(²³⁶U)/n(²³⁸U) isotope ratios in purified uranium solutions.

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Varga, Z., M. Krachler, A. Nicholl, M. Ernstberger, T. Wiss, M. Wallenius, and K. Mayer. "Accurate measurement of uranium isotope ratios in solid samples by laser ablation multi-collector inductively coupled plasma mass spectrometry." Journal of Analytical Atomic Spectrometry 33, no. 6 (2018): 1076–80. http://dx.doi.org/10.1039/c8ja00006a.

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A multi-collector inductively coupled plasma mass spectrometer (MC-ICP-MS) coupled to a 213 nm ns-laser was used to measure uranium isotope ratios (²³⁴U/²³⁸U, ²³⁵U/²³⁸U, and ²³⁶U/²³⁸U) in six solid nuclear certified reference materials (CRMs).

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Arnason, John G., Christine N. Pellegri, and Patrick J. Parsons. "Determination of total uranium and uranium isotope ratios in human urine by ICP-MS:results of an interlaboratory study." Journal of Analytical Atomic Spectrometry 30, no. 1 (2015): 126–38. http://dx.doi.org/10.1039/c4ja00235k.

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Interlaboratory performance is reported for nine participants analyzing six well-characterized urine reference materials supplemented with ²³⁴U, ²³⁵U, ²³⁶U, and ²³⁸U.

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Sudarmono, E. P. Hastuti, A. Rohanda, A. S. Ekariansyah, Y. Kasesaz, and Suwoto. "Study Analysis of Multiplication Factor on ADS Transmutation System." Journal of Physics: Conference Series 2328, no. 1 (August 1, 2022): 012008. http://dx.doi.org/10.1088/1742-6596/2328/1/012008.

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Abstract New research technology for partition and transmutation (P-T) of minor actinide (MA) contained in high-level waste (HLW) has been carried out to design accelerator-based transmutation system or commonly known as Accelerator Driven Subcritical (ADS) device. The objective of this system is to eliminate or minimize high-level radioactive waste that has long half-life and to develop long-term safety assurance in HLW management. Analysis done by using Origen2.1 and mCnP6 codes. As matrix, Th-232 with optimum weight 75% is used.. Comparing with , analysis results using MCNP shows that the use of PWR nuclear spent fuel for ADS device can be done by reprocessing to eliminate U-238 nuclide, which is the source of the formation of plutonium nuclide and minor actinides. From the results and discussion, it can be concluded that observation on transmutation of transuranic nuclides using ORIGEN2.1 Code on ADS device has been conducted successfully with LMFBR library. 15%-Th232 fuel has been justified as the most optimum ADS fuel based on K-inf reached at EOC on various fuel types. Mass reduction occurs at EOC for U-236, U-235, U-234, Th-232, Np-237, Pu-238, Am-241, Pu-242, and Cm 244. Radionuclides that experience mass changes during cooling time are Pu-238, Pu-240, Am-241, Pa-233, and Cm-244.

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Oettingen, Mikołaj, and Jerzy Cetnar. "Comparative analysis between measured and calculated concentrations of major actinides using destructive assay data from Ohi-2 PWR." Nukleonika 60, no. 3 (September 1, 2015): 571–80. http://dx.doi.org/10.1515/nuka-2015-0102.

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Abstract In the paper, we assess the accuracy of the Monte Carlo continuous energy burnup code (MCB) in predicting final concentrations of major actinides in the spent nuclear fuel from commercial PWR. The Ohi-2 PWR irradiation experiment was chosen for the numerical reconstruction due to the availability of the final concentrations for eleven major actinides including five uranium isotopes (U-232, U-234, U-235, U-236, U-238) and six plutonium isotopes (Pu-236, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242). The main results were presented as a calculated-to-experimental ratio (C/E) for measured and calculated final actinide concentrations. The good agreement in the range of ±5% was obtained for 78% C/E factors (43 out of 55). The MCB modeling shows significant improvement compared with the results of previous studies conducted on the Ohi-2 experiment, which proves the reliability and accuracy of the developed methodology.

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Воробьев, А. С., А. М. Гагарский, О. А. Щербаков, Л. А. Вайшнене, А. Л. Барабанов, and Т. Е. Кузьмина. "Анизотропия угловых распределений осколков деления 232 Th, 233 U, 235 U, 238 U, 239 Pu, 237 Np, Pb и 209 Bi нейтронами промежуточных энергий 1–200 МэВ." Известия Российской академии наук. Серия физическая 84, no. 10 (2020): 1451–57. http://dx.doi.org/10.31857/s0367676520100294.

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Andersen, M. B., D. Vance, J. L. Morford, E. Bura-Nakić, S. F. M. Breitenbach, and L. Och. "Closing in on the marine 238 U/ 235 U budget." Chemical Geology 420 (January 2016): 11–22. http://dx.doi.org/10.1016/j.chemgeo.2015.10.041.

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Susdarwono, Endro Tri. "Reaksi Fisi dan Reaksi Fusi dalam Mekanisme Bom Atom dan Senjata Termonuklir." VEKTOR: Jurnal Pendidikan IPA 2, no. 1 (May 28, 2021): 16–30. http://dx.doi.org/10.35719/vektor.v2i1.19.

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Tujuan penelitian ini membahas mengenai reaksi fisi dan fusi pada bom atom dan senjata termonuklir. Penelitian ini adalah penelitian kualitatif, jenis penelitiannya menggunakan studi analitik komprehensif. Bagian paling vital dari ledakan fisi yang terjadi dalam bom atom tak lain adalah material yang berfisi itu sendiri. Ada dua unsur radioaktif yang biasa dipakai, yakni uranium dan plutonium, masing-masing dengan aneka isotopnya. Mulai dari U-232, U-234, U-235, dan U-238 untuk uranium, hingga Pu-238, Pu-239, dan Pu240 untuk plutonium. Elemen pemicu ledak yang dipakai dalam ledakan termonuklir ialah deuterium (D) alias hydrogen berat atau yang juga popular dengan sebutan ‘air berat’ (heavy water). Dari setiap 5000 atom hydrogen, bisa dipastikan satu isotop di antaranya dalam bentuk deuterium. Inti deuterium (deutron) terdiri dari satu proton (p) dan satu neutron (n). saat berpasangan, dua deutron membentuk inti atom helium (He-4) yang relatif stabil. Dalam semua jenis reaksi ini, inti atom berat terbentuk melalui proses fusi. Kata Kunci: bom atom, reaksi fisi, reaksi fusi, senjata termonuklir The purpose of this research is to discuss fission and fusion reactions in atomic bombs and thermonuclear weapons. This research is a qualitative research. This type of research uses a comprehensive analytical study. The most vital part of the fission explosion that occurs in an atomic bomb is none other than the fission material itself. There are two radioactive elements in common use, uranium and plutonium, each with its different isotopes. They range from U-232, U-234, U-235, and U-238 for uranium, to Pu-238, Pu-239, and Pu240 for plutonium. The explosive trigger element used in thermonuclear explosions is deuterium (D) heavy hydrogen or also popularly known as "heavy water" (heavy water). For every 5000 hydrogen atoms, one can be sure of one of them in the form of deuterium. The nucleus of heuterium (deutron) consists of one proton (p) and one neutron (n). When paired, the two deutrons form a relatively stable nucleus of helium (He-4). In all of these types of reactions, heavy atomic nuclei are formed by fusion. Keywords: atomic bombs, fission reactions, fusion reactions, thermonuclear weapons

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Seifritz, W. "Some comments on Herndon’s nuclear georeactor." Kerntechnik 68, no. 4 (August 1, 2003): 193–96. http://dx.doi.org/10.1515/kern-2003-0079.

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Abstract Light was thrown on the nuclear aspects of Herndon’s georeactor. His thesis is that a power producing droplet of liquid uranium, possessing a radius of about 5 km, operated during the last 4.5 billions of years in the center of the Earth and producing 3–6 TW of thermal power. It could be shown that indeed initial criticality was possible due to the high U-235/U-238 enrichment of approximately 30% at that time. Furthermore, the U-238/Pu-239/U-235 conversion cycle guarantees also a stabilized U-235/U-238 enrichment of about 10% during the whole history of Earth. For this, a constant critical neutron flux in the realm of 108 n/(cm2s) has to be present to convert U-238 via the Pu-239 route and its eddecay into U-235 with a conversion ratio of exactly unity. Herndon’s georeactor is compared with other exotic fission reactors in Nature, too, but the decisive answer whether such a georeactor really exists needs further – particularly chemical, thermodynamical and geological – research work.

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Голубев, В. Н., Н. Н. Тарасов, И. В. Чернышев, А. В. Чугаев, Г. В. Очирова, and Б. Т. Кочкин. "Пострудные процессы миграции урана в месторождениях “песчаникового” типа: 234 U/ 238 U, 238 U/ 235 U и U–Pb-изотопная систематика руд месторождения Намару, Витимский район, Северное Забайкалье." Геология рудных месторождений 63, no. 4 (2021): 297–310. http://dx.doi.org/10.31857/s001677702104002x.

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Dissertations / Theses on the topic "U 238-u 235"

1

Braid, Ryan A. "The Calibration of a Fission Chamber at 14 MeV: Accelerator based Neutron Beam Detection." Ohio University Art and Sciences Honors Theses / OhioLINK, 2010. http://rave.ohiolink.edu/etdc/view?acc_num=ouashonors1276710315.

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Miller, Zachariah W. "A MEASUREMENT OF THE PROMPT FISSION NEUTRON ENERGY SPECTRUM FOR ²³⁵U(n,f) AND THE NEUTRON-INDUCED FISSION CROSS SECTION FOR ²³⁸U(n,f)." UKnowledge, 2015. http://uknowledge.uky.edu/physastron_etds/29.

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Two measurements have been made, addressing gaps in knowledge for 235U(n,f) and 238U(n,f). The energy distribution for prompt fission neutrons is not well-understood below 1 MeV in 235U(n,f). To measure the 235U(n,f) prompt fission neutron distribution, a pulsed neutron beam at the WNR facility in Los Alamos National Laboratory was directed onto a 235U target with neutron detectors placed 1 m from the target. These neutron detectors were designed specifically for this experiment and employed a unique geometry of scintillating plastic material that was designed to reject backgrounds. Fission fragments were detected using an avalanche counter. Coincidences between fission fragment production and neutron detector events were analyzed, using a double time-of-flight technique to determine the energy of the prompt fission neutrons. A separate measurement was made, investigating the neutron-induced fission cross section for 238U(n,f). This measurement also used the pulsed neutron beam at the WNR facility. The neutron flux was normalized to the well-known hydrogen standard and the fission rate was observed for beam neutrons in the energy range of 130-300 MeV. Using an extrapolation technique, the energy dependence of the cross section was determined. These new data filled a sparsely populated energy region that was not well-studied and were measured relative to the hydrogen standard, unlike the majority of available data. These data can be used to constrain the fission cross section, which is considered a nuclear reaction standard.

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Chen, Yong. "Delayed neutron emission measurements for U-235 and Pu-239." Thesis, [College Station, Tex. : Texas A&M University, 2006. http://hdl.handle.net/1969.1/ETD-TAMU-1134.

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Godoy, J. M. [Verfasser]. "Entwicklung einer Analysenmethode fuer die Bestimmung von U-238, U-234, Th-232, Th-230, Th-228, Ra-228, Ra-226, Pb-210 und Po-210 und ihre Anwendung auf Umweltproben / J.M. Godoy." Karlsruhe : KIT-Bibliothek, 2014. http://d-nb.info/1196112010/34.

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Jaeger, U. [Verfasser]. "Herstellung und Untersuchung der protonenueberschuessigen Plutonium-Isotope 232 bis 235 / U. Jaeger." Karlsruhe : KIT-Bibliothek, 2010. http://d-nb.info/1187253537/34.

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Pons-Branchu, Edwidge. "Datation haute résolution de spéléothèmes (230 Th/234 U et 226 Ra/238 U) : application aux reconstitutions environnementales autour des sites du Gard et du Meuse/Haute Marne." Aix-Marseille 3, 2001. http://www.theses.fr/2001AIX30094.

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Nous avons réalisé l'étude de spéléothèmes du Gard et de la région de l'Est du bassin de Paris. La datation fine a été appliquée aux reconstitutions environnementales actuelles et passées pour les derniers 250 ka. Cette approche vise dans un premier temps à valider les datations U/Th réalisées a haute résolution et sur de petites quantités de matière, sur la période de temps très récente (0- 10ka BP) pour laquelle cette méthode est difficile à utiliser. Parallèlement, nous avons teste sur cette période de temps récente et sur les mêmes échantillons, la datation par excès de 226 Ra. Pour toute la gamme d'application des datations U/Th, nous avons teste plusieurs modes de corrections des âges, pour prendre en compte les biais liés à la présence de matériel détritique dans ces carbonates impurs. .
We have investigated the Gard and the eastern Paris basin environmental reconstruction by using U-series dating of speleothems. The first aim of this study was to validate the high resolution U-series dating of small size samples over the recent period (0- 10 kyr) for which this method is of difficult use. For this period, we also have tested the 226 Ra dating techniques for the U/Th dated speleothem. For the whole period on which U/Th is valid, several correction methods were compared in order to take into account bias due to detrital material within these impure carbonates. These methodological investigations enabled to investigate several research axes. We discussed the origin of speleothems breaking from a Gard cave. Speleothem U/Th dating has been used for a chronological scale for the Eastern Paris basin karstification. We have shown the importance of the presence and the erosion of a non carbonated cover overlying the karstified limestone on the speleothem uranium composition. .

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MALHEIRO, LUCIANO H. "Disponibilidade de sup(238)U e sup(232)Th na utilização de fosfogesso na agricultura." reponame:Repositório Institucional do IPEN, 2014. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11787.

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Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2014-11-10T10:38:01Z No. of bitstreams: 0
Made available in DSpace on 2014-11-10T10:38:01Z (GMT). No. of bitstreams: 0
Dissertação (Mestrado em Tecnologia Nuclear)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

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SANTOS, JÚNIOR José Araújo dos. "Avaliação radiométrica do U-238, Ra-226, Th-232 e K-40 em uma área anômala do agreste de Pernambuco." Universidade Federal de Pernambuco, 2009. https://repositorio.ufpe.br/handle/123456789/9472.

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Made available in DSpace on 2014-06-12T23:14:47Z (GMT). No. of bitstreams: 2 arquivo8682_1.pdf: 3542962 bytes, checksum: 0fce1e7a36648011d3e5160e27dc78da (MD5) license.txt: 1748 bytes, checksum: 8a4605be74aa9ea9d79846c1fba20a33 (MD5) Previous issue date: 2009
Conselho Nacional de Desenvolvimento Científico e Tecnológico
Estudos radiométricos e radioecológicos vêm sendo desenvolvidos mundialmente, em busca do mapeamento de áreas com elevados níveis de radioatividade, um pré-requisito essencial na investigação da exposição à radioatividade ambiental. Nesse trabalho foram estudadas amostras de rochas e solo derivado de uma área efetivamente anômala em urânio no município de Pedra, Pernambuco, utilizando análises não destrutivas, com aplicação da espectrometria gama de alta resolução com detector HPGe, para os radionuclídeos das séries do 238U e do 232Th, assim como o 40K, calculando-se suas atividades específicas. Os valores de 238U variaram de menor que 2,8 a 79.092 Bq.kg-1; os de 226Ra de menor que 0,6 a 144.438 Bq.kg-1; os de 232Th de 6,9 a 1.903 Bq.kg-1 e os de 40K de menores que 4,7 a 2.274 Bq.kg-1. Uma estimativa dos teores, das taxas de doses gamas naturais e do rádio equivalente foram realizadas com base nos valores das atividades específicas. Os teores médios em solo foram 3,3 mg.kg-1 de 238U; 0,7 ng.kg-1 de 226Ra; 39,3 mg.kg-1 de 232Th e 3,4 mg.kg-1 de 40K; em rochas graníticas, os valores médios foram 2,0 mg.kg-1 de 238U; 0,6 ng.kg-1 de 226Ra; 40,2 mg.kg-1 de 232Th e de 3,1 mg.kg-1 de 40K; enquanto nas rochas cálcio-silicáticas anfibolíticas, as médias para 238U, 226Ra e 232Th foram 3.132 mg.kg-1; 1.886 ng.kg-1 e 119 mg.kg-1, respectivamente. A taxa de dose equivalente efetiva devida a radiação gama natural a 1 m da superfície e o rádio equivalente estimados, apresentaram, respectivamente, valores médios de 204 μSv.a-1 e 393 Bq.kg-1 para solo; 195 μSv.a-1 e 328 Bq.kg-1 para as rochas graníticas e de 20.993 μSv.a-1 e 70.124 Bq.kg-1 para as rochas cálcio-silicáticas anfibolíticas. Além disso, foi estimada a disponibilidade do urânio natural no solo da área com base na razão Th/U. No solo, o urânio apresentou baixa mobilidade (Th/U igual a 4,6) para pelo menos 80% dos pontos amostrados. Os resultados permitiram monitorar a exposição gama externa à qual os indivíduos que residem próximos a essas áreas estão expostos. Estima-se uma taxa de dose máxima superior a 43 vezes o limite recomendado para indivíduos do público, que é de 1 mSv.a-1. Recomenda-se que essas áreas sejam pouco utilizadas ou evitadas, de forma minimizar exposições desnecessárias

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Toulhoat, Pierre. "Hydrogeochimie de l'uranium, de ses descendants et d'elements associes (lanthanides) : application a la prospection miniere." Paris 6, 1987. http://www.theses.fr/1987PA066648.

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On etudie le comportement de l'uranium et de ses descendants dans les eaux naturelles et on quantifie les phenomenes de fixation en presence de complexants en solution. D'autre part, dans un but de prospection, on etudie les traceurs de mineralisations que sont **(234)u et **(206)pb, les phenomenes d'adsorption/desorption gouvernant en grande partie les modeles de prospection proposes, bases sur la mesure des rapports d'activite **(234)u/**(236)u et de la composition isotopique du plomb dans les eaux

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Hawa, A. H. [Verfasser], and A. von [Verfasser] Baeckmann. "Simultane Bestimmung von U-235 - und Pu-239 - Spuren durch γ-spektrometrische Analyse der Spaltedelgase nach Neutronenaktivierung / A. H. Hawa, A. von Baeckmann." Karlsruhe : KIT-Bibliothek, 2012. http://d-nb.info/1190100649/34.

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Books on the topic "U 238-u 235"

1

Scheibert, Horst. Deutscher 8-Rad-Panzerspa hwagen [Acht-Rad-Panzerspa hwagen] der Gs-Baureihe: Sd. Kfz. 231, 232, 263 u. 233. Friedberg (Dorheim): Podzun-Pallas-Verlag, 1985.

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Loifer, ʻOded Lipa. Sefer Mishpeṭe ha-mamon: Onaʼah u-meḳaḥ ṭaʻut : leḳeṭ u-veʼure halakhot be-dine onaʼah u-meḳaḥ ṭaʻut, simanim 227-234 ... siman 237. Bene Beraḳ: ʻO. L. Loifer, 1998.

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Hawkes, N. P. 238 u photonuclear studies with 5-10 MeV photons. Birmingham: University of Birmingham, 1985.

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Germany's last mission to Japan: The failed voyage of U-234. Annapolis, Md: Naval Institute Press, 2000.

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Tominaga, Takako. Shinkai kara no koe: U-boat 234-gō to Tomonaga Hideo Kaigun Gijutsu Chūsa. Tōkyō: Shin Hyōron, 2005.

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Shvadron, Shalom Mordecai. Sefer Mishpaṭ Shalom: ʻal Ḥoshen mishpaṭ (mi-si. 175-si. 237) : hilkhot Mitsranut, Shutafin ṿe-shiluḥin, Miḳaḥ u-mimkar, Onaʾah u-miḳaḥ ṭaʻut. Yerushalayim: Mekhon "Daʻat Torah", 1990.

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Shvadron, Shalom Mordecai. Sefer Mishpaṭ Shalom: ʻal Ḥoshen mishpaṭ (mi-si. 175-si. 237) : hilkhot Mitsranut, Shutafin ṿe-shiluḥin, Miḳaḥ u-mimkar, Onaʼah u-miḳaḥ ṭaʻut. Yerushalayim: Mekhon "Daʻat Torah", 1990.

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Karo, Joseph ben Ephraim. Sefer Misḥar ka-halakhah: Hilkhot onaʼah u-miḳaḥ ṭaʻut : Shulḥan ʻarukh Ḥoshen mishpaṭ si. 227-si. 234. Bene Beraḳ: Bet Midrash Le-dine Mamonot Zikhron Mosheh, 2001.

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Rogge, A. E. Two Hohokam canals at Sky Harbor International Airport, Phoenix, Arizona: Archaeological data recovery at site AZ U:9:237 (ASM). [Phoenix, Ariz.]: City of Phoenix Parks and Recreation Dept., Pueblo Grande Museum, 2002.

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Afarideh, Hossein. A study of fission in [superior] 238 U induced by Monoenergetic neutrons and heavy ions and oflight particle emission in [superior] 252 Cf spontaneous fission. Birmingham: University of Birmingham, 1988.

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Book chapters on the topic "U 238-u 235"

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Sukhoruchkin, S. I., and Z. N. Soroko. "Excited Nuclear States for U-238 (Uranium)." In Supplement to I/25 A-E, 4089–97. Berlin, Heidelberg: Springer Berlin Heidelberg, 2015. http://dx.doi.org/10.1007/978-3-662-47801-1_710.

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Sukhoruchkin, S. I., and Z. N. Soroko. "Excited Nuclear States for U-238 (Uranium)." In Supplement to I/25 A-G, 4064–80. Berlin, Heidelberg: Springer Berlin Heidelberg, 2016. http://dx.doi.org/10.1007/978-3-662-48747-1_718.

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Sukhoruchkin, S. I., and Z. N. Soroko. "Neutron Resonance Parameters for U-238 (Uranium)." In Neutron Resonance Parameters, 4644–782. Berlin, Heidelberg: Springer Berlin Heidelberg, 2009. http://dx.doi.org/10.1007/978-3-540-87866-7_338.

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Sukhoruchkin, S. I., and Z. N. Soroko. "Excited Nuclear States for U-238 (Uranium)." In Nuclei with Z = 74 - 103, 4786–806. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-30699-0_640.

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Sukhoruchkin, S. I., and Z. N. Soroko. "Neutron Resonance Parameters for U-238 (Uranium)." In Supplement to Volume I/24, 3013–100. Berlin, Heidelberg: Springer Berlin Heidelberg, 2015. http://dx.doi.org/10.1007/978-3-662-45603-3_340.

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Sukhoruchkin, S. I., and Z. N. Soroko. "Excited Nuclear States for U-235 (Uranium)." In Supplement to I/25 A-E, 4076–88. Berlin, Heidelberg: Springer Berlin Heidelberg, 2015. http://dx.doi.org/10.1007/978-3-662-47801-1_709.

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Sukhoruchkin, S. I., and Z. N. Soroko. "Excited Nuclear States for U-235 (Uranium)." In Supplement to I/25 A-G, 4048–63. Berlin, Heidelberg: Springer Berlin Heidelberg, 2016. http://dx.doi.org/10.1007/978-3-662-48747-1_717.

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Sukhoruchkin, S. I., and Z. N. Soroko. "Neutron Resonance Parameters for U-235 (Uranium)." In Neutron Resonance Parameters, 4414–619. Berlin, Heidelberg: Springer Berlin Heidelberg, 2009. http://dx.doi.org/10.1007/978-3-540-87866-7_335.

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Sukhoruchkin, S. I., and Z. N. Soroko. "Excited Nuclear States for U-235 (Uranium)." In Nuclei with Z = 74 - 103, 4720–42. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-30699-0_637.

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Sukhoruchkin, S. I., and Z. N. Soroko. "Neutron Resonance Parameters for U-235 (Uranium)." In Supplement to Volume I/24, 2909–91. Berlin, Heidelberg: Springer Berlin Heidelberg, 2015. http://dx.doi.org/10.1007/978-3-662-45603-3_337.

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Conference papers on the topic "U 238-u 235"

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Ohno, Takeshi, Ami Yoshida, Gou Kitamura, Yuta Ijichi, and Yusuke Fukami. "Temporal changes of ²³⁵U/²³⁸U and ²³⁶U/²³⁸U isotopic ratios in Tokyo Bay from the 1960s to the 2000s." In Goldschmidt2023. France: European Association of Geochemistry, 2023. http://dx.doi.org/10.7185/gold2023.19223.

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Andersen, Morten, Jasper Thomas, Gordon Hudson, and Corey Archer. "The impact of weathering on ²³⁸U/²³⁵U systematics in the critical zone." In Goldschmidt2021. France: European Association of Geochemistry, 2021. http://dx.doi.org/10.7185/gold2021.7613.

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Takeda, Seiji, and Hideo Kimura. "Estimate of Clearance Levels for Metal Materials Contaminated With Uranium." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40117.

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Clearance levels for the solid materials contaminated with uranium were estimated based on deterministic dose calculation approach for metal reuse scenario. The activity concentrations for major radionuclides, U-234, U-235 and U-238, were calculated to be 1.5Bq/g, 1.4Bq/g and 1.8Bq/g, respectively. In order to confirm the validity of the calculated concentrations, the authors estimated the uncertainties on scenario description after metal recycling and on parameter values used in the deterministic calculation. The validity of the calculated activity concentrations by the deterministic approach was confirmed from the results of both the analysis for an additional scenario on the landfill disposal of residue of slag after metal recycling and the Monte Carlo-based analysis for parameter uncertainties.

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Warren, Glen A., Joseph A. Caggiano, William Bertozzi, Stephen E. Korbly, Robert J. Ledoux, and William H. Park. "On the search for nuclear resonance fluorescence signatures of ²³⁵U and ²³⁸U above 3 MeV." In 2008 IEEE Nuclear Science Symposium and Medical Imaging conference (2008 NSS/MIC). IEEE, 2008. http://dx.doi.org/10.1109/nssmic.2008.4775222.

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Hashemi, Mohammad, Rafael Macián-Juan, and Martin Ohlerich. "Neutronics Analysis of RBMK-1000 Reactor Using OpenMC: Criticality and Depletion Analysis at 3D Assembly Level." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-90636.

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Abstract This article presents the first results of the neutronics analysis of RBMK-1000 at the 3D assembly level using the OpenMC code as an early stage of the long-term large academic research project. The goal of the large academic research project is to develop a Multi-group Monte Carlo computational module around the OpenMC code using Python programming language. The results of this paper include the criticality calculation and depletion analysis of RBMK-1000. The effective multiplication factor value (keff) has been determined. In depletion calculation, the fission reaction rates of U-235, U-236, U-238, production of fissionable materials, and two fission product poisons Xe-135 and Sm-149 have been investigated. There is ongoing work for benchmarking the first results from OpenMC against Serpent 2 Monte Carlo code. The parametric design data of RBMK-1000 have been taken from the OECD - Nuclear Energy Agency (NEA) SFCOMPO 2.0 (Spent Fuel Isotopic Composition) database that includes measured isotopic concentrations of spent nuclear fuel, with operational histories and design data. The case study was the Leningrad-1 NPP. The ENDF/B-VII.1 data library has been used in this analysis. Moreover, this is the first time to date that the OpenMC code has been used in neutronic studies of the RBMK reactors.

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Tan, Kai, Ruihan Li, Jian Li, Jingang Liang, and Ding She. "Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-91659.

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Abstract The NUIT (Nuclide Inventory Tool) is a reactor core nuclide inventory calculation code, which has been developed by Institute of Nuclear and New Energy Technology (INET), Tsinghua University. NUIT is able to compute instantaneous and integral values of various physical parameters including isotope composition, decay heat, particle spectrum, and radioactivity in fuel burnup, material activation, and decay calculations. The validation of the NUIT is an important process to ensure the correctness and applicability of the newly developed code. Presently, there is a lack of validation of the nuclide density calculation function of NUIT. Hence, this work is to validate this function of the NUIT code based on the PWR spent fuel isotopic compositions benchmark issued by the Oak Ridge National Laboratory in the SCALE program. In this work, the 103 spent fuel samples from 9 PWR plants are used to validate the nuclide composition calculation function of the NUIT, in which the initial enrichment of U-235 ranges from 2.453% to 4.657%, and the burnup ranges from 7.8 GWd/MTU to 60.7 GWd/MTU. The results show that NUIT’s nuclide density calculation results are in good agreement with the experimental values in general and the average error is about 10% for all nuclide density calculation cases. The typical nuclides, such as U-235, U-238, and Pu-239, etc., have an average calculation error of less than 5%, and most of the average errors of other actinide nuclides and fission products, such as Am, Cm, and Pu, etc., are within 10%∼40%, which meets the requirements of the radioactive source term analysis for the reactor core. Meanwhile, the comparison results show that the calculation accuracy of NUIT is comparable to other radioactive source term programs such as SCALE and OpenMC. The validation results further demonstrate NUIT’s capabilities in nuclide composition calculations.

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Neudecker, Denise. "New nuclear data proposed for the <sup>238</sup>U nu-bar, <sup>235</sup>U nu-bar and PFNS [Slides]." In Nuclear Data Week(s) 2022, CSWEG Meeting, Upton, Long Island, NY (United States), 31 Oct - 11 Nov 2022. US DOE, 2022. http://dx.doi.org/10.2172/1923375.

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Röttger, S., M. S. Allie, F. D. Brooks, A. Buffler, V. Dangendorf, J. P. Meulders, R. Nolte, et al. "Measurement of [sup 235]U, [sup 238]U, [sup 209]Bi and [sup nat]Pb fission cross sections using quasi-monenergetic neutrons with energies from 30 MeV to 200 MeV." In 4TH INTERNATIONAL WORKSHOP ON NUCLEAR FISSION AND FISSION-PRODUCT SPECTROSCOPY. AIP, 2009. http://dx.doi.org/10.1063/1.3258256.

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Trkov, Andrej, Roberto Capote, and Marco Pigni. "Validation of Recent Changes in Actinide Evaluations U-235, U-233, Pu-239 [Slides]." In Nuclear Data Week 2020, Cross Section Evaluation Working Group (CSEWG) Meeting, Held Virtually, Brookhaven, NY (United States), 30 Nov - 4 Dec 2020. US DOE, 2020. http://dx.doi.org/10.2172/1905866.

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Lin, Mu, Olaf Dellwig, Peter Steier, Karin Hain, Robin Golser, Jixin Qiao, and Xiaolin Hou. "Reconstruction of the Deposition History of Anthropogenic Uranium in Baltic Sea Sediments Using U-233/U-236 and U-236/U-238 as Tracers." In Goldschmidt2020. Geochemical Society, 2020. http://dx.doi.org/10.46427/gold2020.1565.

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Reports on the topic "U 238-u 235"

1

Lane, Taylor, and Edward J. Parma. Delayed Fission Gamma-ray Characteristics of Th-232 U-233 U-235 U-238 and Pu-239. Office of Scientific and Technical Information (OSTI), August 2015. http://dx.doi.org/10.2172/1213030.

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Meadows, J. W. The fission cross sections of /sup 230/Th, /sup 232/Th, /sup 233/U, /sup 234/U, /sup 236/U, /sup 238/U, /sup 237/Np, /sup 239/Pu and /sup 242/Pu relative /sup 235/U at 14. 74 MeV neutron energy. Office of Scientific and Technical Information (OSTI), December 1986. http://dx.doi.org/10.2172/6769505.

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Tony Hill. Analysis of TPC Single Sextant U-238/U-235 Engineering In-Beam Data. Office of Scientific and Technical Information (OSTI), September 2012. http://dx.doi.org/10.2172/1060961.

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Poenitz, W. P., D. W. Maddison, J. M. Gasidlo, S. G. Carpenter, and R. J. Armani. /sup 235/U(n,f), /sup 238/U(n,gamma), /sup 238/U(n,f) and /sup 239/Pu(n,f) reaction rate measurement calibrations at ZPPR. Office of Scientific and Technical Information (OSTI), January 1987. http://dx.doi.org/10.2172/6819232.

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Chandler, J. R. Evaluation of {sup 235}U, {sup 238}U, {sup 6}Li, and {sup 27}Al Cross Sections. Office of Scientific and Technical Information (OSTI), May 2001. http://dx.doi.org/10.2172/781333.

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Zucker, M. S., and N. E. Holden. Neutron multiplicity for neutron induced fission of /sup 235/U, /sup 238/U, and /sup 239/Pu as a function of neutron energy. Office of Scientific and Technical Information (OSTI), January 1986. http://dx.doi.org/10.2172/6982219.

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Schier, W. A., and G. P. Couchell. Beta and gamma decay heat measurements between 0. 1s--50,000s for neutron fission of [sup 235]U, [sup 238]U and [sup 239]Pu. Office of Scientific and Technical Information (OSTI), January 1993. http://dx.doi.org/10.2172/6870652.

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Neudecker, Denise, Naohiko Otuka, Robert J. Casperson, Nathaniel S. Bowden, Luke Snyder, Kyle Thomas Schmitt, Morgan Curtis White, and Patrick Talou. Information Files of ²³⁸U(n,f)/²³⁵U(n,f) NIFFTE fissionTPC Cross-sections for the Neutron Data Standards Project. Office of Scientific and Technical Information (OSTI), May 2018. http://dx.doi.org/10.2172/1438098.

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Schier, W. A., and G. P. Couchell. Beta and gamma decay heat measurements between 0.1s--50,000s for neutron fission of {sup 235}U, {sup 238}U and {sup 239}Pu. Progress report, June 1, 1992--February 28, 1993. Office of Scientific and Technical Information (OSTI), May 1993. http://dx.doi.org/10.2172/10142756.

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Schier, W. A., and G. P. Couchell. Beta and gamma decay heat measurements between 0.1s-50,000s for neutron fission of {sup 235}U, {sup 238}U and {sup 239}Pu. Progress report, March 1, 1993--January 31, 1994. Office of Scientific and Technical Information (OSTI), June 1994. http://dx.doi.org/10.2172/10154432.

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