Готові списки джерел за темами / Fission products Analysis

Зміст

  1. Статті в журналах
  2. Дисертації
  3. Книги
  4. Частини книг
  5. Тези доповідей конференцій
  6. Звіти організацій

Добірка наукової літератури з теми "Fission products Analysis"

Автор: Grafiati
Опубліковано: 4 червня 2021
Оновлено: 12 лютого 2022

Оформте джерело за APA, MLA, Chicago, Harvard та іншими стилями

Оберіть тип джерела:

Ознайомтеся зі списками актуальних статей, книг, дисертацій, тез та інших наукових джерел на тему "Fission products Analysis".

Біля кожної праці в переліку літератури доступна кнопка «Додати до бібліографії». Скористайтеся нею – і ми автоматично оформимо бібліографічне посилання на обрану працю в потрібному вам стилі цитування: APA, MLA, «Гарвард», «Чикаго», «Ванкувер» тощо.

Також ви можете завантажити повний текст наукової публікації у форматі «.pdf» та прочитати онлайн анотацію до роботи, якщо відповідні параметри наявні в метаданих.

Статті в журналах з теми "Fission products Analysis"

1

Petrovski, A. M., T. N. Korbut, E. A. Rudak, and M. O. Kravchenko. "Accounting of the vver-1200 overload influence for fission products activities calculating." Proceedings of the National Academy of Sciences of Belarus, Physical-Technical Series 64, no. 4 (January 11, 2020): 491–96. http://dx.doi.org/10.29235/1561-8358-2019-64-4-491-496.

Повний текст джерела
Анотація:
Current work is aimed at the analysis of the fission products decay influence during fuel reloading, when calculating the accumulated fission products activity for the VVER-1200 reactor fuel campaign. The Bateman problem solution based technique was used for calculations, within the framework of the two fissile nuclides approximation. The fission products producing process for the VVER-1200 reactor stationary campaign is considered, taking into account the reactor shutdown periods for refueling and without taking them into account (instant reload approximation). It was shown, that the instant
Стилі APA, Harvard, Vancouver, ISO та ін.
2

Zhou, Tao, Peng Xu, Tian Qi, Xuemeng Qin, Juan Chen, and Zhongguang Fu. "Calculation and Analysis of the Source Term of the Reactor Core Based on Multivariate Analysis of Variance." Science and Technology of Nuclear Installations 2021 (June 3, 2021): 1–8. http://dx.doi.org/10.1155/2021/8810668.

Повний текст джерела
Анотація:
The calculation of the core source term is affected by various factors, such as fuel consumption, enrichment, specific power, and operation mode. The activity of lanthanides, fission products, and the photon source strength were calculated using the ORIGEN program. The weights of each factor were calculated by multivariate analysis of variance. The results show that the radioactivity of actinides and fission products increased with the increase in fuel consumption. As enrichment increased, the radioactivity of fission products and actinides decreased. The radioactivity of fission products and
Стилі APA, Harvard, Vancouver, ISO та ін.
3

Auxier, John D., Jacob A. Jordan, S. Adam Stratz, Shayan Shahbazi, Daniel E. Hanson, Derek Cressy, and Howard L. Hall. "Thermodynamic analysis of volatile organometallic fission products." Journal of Radioanalytical and Nuclear Chemistry 307, no. 3 (December 17, 2015): 1621–27. http://dx.doi.org/10.1007/s10967-015-4653-9.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
4

Dietz, N. L., and D. D. Keiser. "TEM Analysis of Corrosion Products From a Radioactive Stainless Steel-based Alloy." Microscopy and Microanalysis 6, S2 (August 2000): 368–69. http://dx.doi.org/10.1017/s1431927600034334.

Повний текст джерела
Анотація:
Argonne National Laboratory has developed an electrometallurgical treatment process for metallic spent nuclear fuel from the Experimental Breeder Reactor-II. This process stabilizes metallic sodium and separates usable uranium from fission products and transuranic elements that are contained in the fuel. The fission products and other waste constituents are placed into two waste forms: a ceramic waste form that contains the transuranic elements and active fission products such as Cs, Sr, I and the rare earth elements, and a metal alloy waste form composed primarily of stainless steel (SS), fro
Стилі APA, Harvard, Vancouver, ISO та ін.
5

Kilim, S., E. Strugalska-Gola, M. Szuta, S. Tyutyunnikov, O. Dalkhjav, V. I. Stegailov, I. A. Kryachko, et al. "Am-241 incineration measurements with activation method in the QUINTA neutron field." EPJ Web of Conferences 204 (2019): 04004. http://dx.doi.org/10.1051/epjconf/201920404004.

Повний текст джерела
Анотація:
Am-241 sample was irradiated in spallation neutrons produced in ADS setup QUINTA at the JINR in Dubna. The energy was 660 MeV in the proton beam. The incineration study method was based on gamma-ray spectrometry. During the analysis of the spectra, several fission products were identified. Fission product activities yielded the number of fissions. Nevertheless, the lines are assumed to belong to the neutron capture product covered by parasitic Np-238 decay lines. The Np-238 lines as a result of neutron capture by Np-237 made impossible to determine the number of captures in Am-241.
Стилі APA, Harvard, Vancouver, ISO та ін.
6

Hernandez Solis, Augusto, Alexey Stankovskiy, Luca Fiorito, and Gert Van den Eynde. "Depletion uncertainty analysis to the MYRRHA fuel assembly model." EPJ Web of Conferences 239 (2020): 12001. http://dx.doi.org/10.1051/epjconf/202023912001.

Повний текст джерела
Анотація:
In this work, the objective is to perform an uncertainty analysis on a MYRRHA -Rev.1.6 irradiation cycle study, being applied to a depletion scenario of a single fresh fuel assembly while assuming reflective boundary conditions. Such analysis is statistically based on the application of Wilk’s method of building tolerance limits after 100 depletion calculations were performed with the SERPENT2 code. Due to the computational burden of such type of simulations, this propagation of nuclear data covariances study (allowed by the fast computational performance of SERPENT2) was done at constant powe
Стилі APA, Harvard, Vancouver, ISO та ін.
7

Taylor, Zack, Benjamin Collins, and Ivan Maldonado. "MATRIX EXPONENTIAL METHODS FOR PARALLEL COMPUTING OF ISOTOPIC DEPLETION AND SPECIES TRANSPORT FOR MOLTEN SALT REACTOR ANALYSIS." EPJ Web of Conferences 247 (2021): 06047. http://dx.doi.org/10.1051/epjconf/202124706047.

Повний текст джерела
Анотація:
Matrix exponential methods have long been utilized for isotopic depletion in nuclear fuel calculations. In this paper we discuss the development of such methods in addition to species transport for liquid fueled molten salt reactors (MSRs). Conventional nuclear reactors work with fixed fuel assemblies in which fission products and fissile material do not transport throughout the core. Liquid fueled molten salt reactors work in a much different way, allowing for material to transport throughout the primary reactor loop. Because of this, fission product transport must be taken into account. The
Стилі APA, Harvard, Vancouver, ISO та ін.
8

Stempniewicz, M. M., L. Winters, and S. A. Caspersson. "Analysis of dust and fission products in a pebble bed NGNP." Nuclear Engineering and Design 251 (October 2012): 433–42. http://dx.doi.org/10.1016/j.nucengdes.2011.09.049.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
9

Thomas, L. E., and R. J. Guenther. "AEM analysis of condensed-phase xenon in UO2 spent fuel." Proceedings, annual meeting, Electron Microscopy Society of America 46 (1988): 512–13. http://dx.doi.org/10.1017/s0424820100104625.

Повний текст джерела
Анотація:
Release of the abundant fission gases xenon and krypton in UO2 reactor fuels is a limiting factor in normal performance of fuel rods and a concern in possible accidents involving transient overheating of the fuel. Consequently, a knowledge of the fission gas behavior in fuel is of great interest. Although fission gases in fuel are widely believed to exist as gas bubbles or atoms in solution in the UO2, we have obtained evidence by analytical electron microscopy that the xenon and krypton can also exist as a condensed phase, i.e. as a liquid or solid at high internal pressures in the UO2. This
Стилі APA, Harvard, Vancouver, ISO та ін.
10

Chebboubi, A., S. Julien-Laferrière, J. Nicholson, G. Kessedjian, O. Serot, A. Blanc, D. Bernard, et al. "Measurements of Fission Products Yields with the LOHENGRIN mass spectrometer at ILL." EPJ Web of Conferences 242 (2020): 01001. http://dx.doi.org/10.1051/epjconf/202024201001.

Повний текст джерела
Анотація:
The CEA in collaboration with ILL and LPSC has developed a measurement program on symmetric and heavy mass fission product distributions. The combination of measurements with ionisation chamber and Ge detectors is necessary to describe precisely the heavy fission product region in mass and charge. Recently, new measurements of fission yields and kinetic energy distributions, for different fissioning systems (233,235 U(nth, f),241 Am(2nth, f) and 239,241 Pu(nth, f), were performed with recoil spectrometer LOHENGRIN. The focus has been done on the self-normalization of the data to provide new ab
Стилі APA, Harvard, Vancouver, ISO та ін.
Більше джерел

Дисертації з теми "Fission products Analysis"

1

EL-HAJJE, REFAAT Safety Science Faculty of Science UNSW. "A SIMULTANEOUS MEASUREMENT OF THE ANGULAR DISTRIBUTION, MASS AND KINETIC ENERGY OF 235U AND 232Th FISSION FRAGMENTS." Awarded by:University of New South Wales. School of Safety Science, 2000. http://handle.unsw.edu.au/1959.4/17612.

Повний текст джерела
Анотація:
Simultaneous measurements of the angular distribution, mass distribution and average total kinetic energy of fission fragments produced by the neutron-induced fission of 235U and 232Th have been made using a gridded ionisation chamber. The neutron energy range used was thermal to 1.9 MeV for 235U and 1.4 to 1.7 MeV for 232Th. The following topics were investigated: the interdependence of the fission fragment angular and mass distribution; the anomalous behaviour of fragment anisotropy for 235U(n,f) at neutron energies En below 150 keV; the possible existence of a third symmetric mass peak for
Стилі APA, Harvard, Vancouver, ISO та ін.
2

SATO, IVONE M. "Determinacao dos produtos de fissao em rejeito liquido de atividade alta por fluorescencia de raio-x .Correcao da interferencia espectral pela razao das intensidades." reponame:Repositório Institucional do IPEN, 1988. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9888.

Повний текст джерела
Анотація:
Made available in DSpace on 2014-10-09T12:32:29Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:10:17Z (GMT). No. of bitstreams: 1 03229.pdf: 4303799 bytes, checksum: 4489c15ec829a1386b6e29cbdf98907e (MD5)<br>Tese (Doutoramento)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
Стилі APA, Harvard, Vancouver, ISO та ін.
3

Belhabib, Tayeb. "Comportement thermique des défauts lacunaires induits par l’hélium et les gaz de fission dans le dioxyde d’uranium." Thesis, Orléans, 2012. http://www.theses.fr/2012ORLE2071/document.

Повний текст джерела
Анотація:
Dans les nouvelles centrales nucléaires dites 4ème génération, comme d’ailleurs les anciennes, le dioxyde d’uranium devra opérer dans des milieux hostiles de températures et d’irradiation avec la présence des produits de fission (PF) et des particules alpha (α). Le fonctionnement dans ces conditions extrêmes induira des déplacements d’atomes et dégradera les propriétés thermiques et mécaniques du combustible UO2. La compréhension du comportement des défauts lacunaires, des PF et de l’hélium est cruciale pour prévoir le comportement du dioxyde d’uranium au sein de ces futures installations nucl
Стилі APA, Harvard, Vancouver, ISO та ін.
4

Junior, Iberê Souza Ribeiro. "Determinação de fatores de interferência de produtos de fissão do urânio na Análise por Ativação Neutrônica." Universidade de São Paulo, 2014. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-22092014-144404/.

Повний текст джерела
Анотація:
A análise por ativação com nêutrons é um método utilizado na determinação de diversos elementos em diferentes tipos de matrizes. Entretanto, quando a amostra contém altos teores de U ocorre o problema de interferência devido aos produtos de fissão do isótopo 235U. Um dos métodos de tratar este problema é fazer a correção usando fatores de interferência devido à fissão do U para os radionuclídeos utilizados nas análises dos elementos. No presente estudo foram determinados os valores dos fatores de interferência devido à fissão do U para os radioisótopos 141Ce, 143Ce,140La, 99Mo, 147Nd, 153Sm e
Стилі APA, Harvard, Vancouver, ISO та ін.
5

GERALDO, BIANCA. "Utilização de métodos radioanalíticos para a determinação de isótopos de urânio, netúnio, plutônio, amerício e cúrio em rejeitos radioativos." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9942.

Повний текст джерела
Анотація:
Made available in DSpace on 2014-10-09T12:33:04Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:06:06Z (GMT). No. of bitstreams: 0<br>Dissertação (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
Стилі APA, Harvard, Vancouver, ISO та ін.
6

RIBEIRO, JUNIOR IBERE S. "Determinação de fatores de interferência de produtos de fissão do urânio na análise por ativação neutrônica." reponame:Repositório Institucional do IPEN, 2014. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11801.

Повний текст джерела
Анотація:
Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2014-11-10T11:38:41Z No. of bitstreams: 0<br>Made available in DSpace on 2014-11-10T11:38:41Z (GMT). No. of bitstreams: 0<br>Dissertação (Mestrado em Tecnologia Nuclear)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
Стилі APA, Harvard, Vancouver, ISO та ін.
7

Dickinson, Shirley. "Infrared spectroscopic and mass spectrometric studies of high-temperature molecules relevant to severe nuclear reactor accidents." Thesis, University of Southampton, 1990. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.255768.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
8

Kennedy, William B. (William Blake) 1979. "Analysis of the MIT research reactor fission product and actinide radioactivity inventories." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/32723.

Повний текст джерела
Анотація:
Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Physics, 2004.<br>MIT Institute Archives copy: leaves 92-111 bound in reverse order.<br>Includes bibliographical references (leaf 57).<br>The current analysis of the MITR core radioactivity inventory eliminates unnecessary assumptions made in previous estimates of the inventory, and revises the list of contributory isotopes to include all actinide and fission product isotopes necessary for a proper accident source term calculation. The result is a power-history-dependent inventory that increases with bum-up, and comprises 41 actini
Стилі APA, Harvard, Vancouver, ISO та ін.
9

Halonen, Kimmo. "Gamma spectrum analysis of fission product release during accidental conditions: focus on ruthenium release during air ingress." Thesis, KTH, Fysik, 2012. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-103715.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
10

Belhabib, Tayeb. "Comportement thermique des défauts lacunaires induits par l'hélium et les gaz de fission dans le dioxyde d'uranium." Phd thesis, Université d'Orléans, 2012. http://tel.archives-ouvertes.fr/tel-00831705.

Повний текст джерела
Анотація:
Dans les nouvelles centrales nucléaires dites 4ème génération, comme d'ailleurs les anciennes, le dioxyde d'uranium devra opérer dans des milieux hostiles de températures et d'irradiation avec la présence des produits de fission (PF) et des particules alpha (α). Le fonctionnement dans ces conditions extrêmes induira des déplacements d'atomes et dégradera les propriétés thermiques et mécaniques du combustible UO2. La compréhension du comportement des défauts lacunaires, des PF et de l'hélium est cruciale pour prévoir le comportement du dioxyde d'uranium au sein de ces futures installations nucl
Стилі APA, Harvard, Vancouver, ISO та ін.
Більше джерел

Книги з теми "Fission products Analysis"

1

Holliger, Philippe. The new OKLO reaction zones: U-Pb dating and in situ characterization of fission products by ion analysis : report on Progress 1991. Grenoble: Centre d'Études Nucléaires de Grenoble, 1993.

Знайти повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
2

Leonard, Soffer, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., eds. Accident source terms for light-water nuclear power plants: Final report. Washington, DC: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1995.

Знайти повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
3

Leonard, Soffer, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., eds. Accident source terms for light-water nuclear power plants: Final report. Washington, DC: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1995.

Знайти повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.

Частини книг з теми "Fission products Analysis"

1

Gouget, Karine, Fulvia Verde, and Antoni Barrientos. "In Vivo Labeling and Analysis of Mitochondrial Translation Products in Budding and in Fission Yeasts." In Membrane Trafficking, 113–24. Totowa, NJ: Humana Press, 2008. http://dx.doi.org/10.1007/978-1-59745-261-8_8.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
2

Zohuri, Bahman. "Fission Product Buildup and Decay." In Neutronic Analysis For Nuclear Reactor Systems, 483–99. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-04906-5_15.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
3

Zohuri, Bahman. "Fission Product Buildup and Decay." In Neutronic Analysis For Nuclear Reactor Systems, 491–507. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-42964-9_15.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
4

Mondot, J., J. P. Chauvin, and J. P. West. "Validation of Fission Product Capture Cross Sections by the Analysis of Thermal and Epithermal Integral Experiments." In Nuclear Data for Science and Technology, 29–34. Berlin, Heidelberg: Springer Berlin Heidelberg, 1992. http://dx.doi.org/10.1007/978-3-642-58113-7_6.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
5

Ponomarev-Stepnoi, N. N., and A. A. Khrulev. "Effect of the Annealing Temperature on Escape of Metal Fission Products from Different Media (Features of Experimental Data Analysis)." In Fission Product Transport Processes in Reactor Accidents, 735–62. CRC Press, 2020. http://dx.doi.org/10.1201/9781003070344-61.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
6

"SAFETY ANALYSIS NEEDS AND MAIN PHENOMENA TO BE STUDIED." In The Phebus Fission Product Project, 115–18. CRC Press, 2003. http://dx.doi.org/10.1201/9781482286779-14.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
7

"SAFETY ANALYSIS NEEDS AND MAIN PHENOMENA TO BE STUDIED." In The Phebus Fission Product Project, 115–18. CRC Press, 2003. http://dx.doi.org/10.1201/9781482286779-14.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
8

"SURVEY OF SEVERE ACCIDENT EXPERIMENTS AND ANALYSES IN JAPAN." In The Phebus Fission Product Project, 32–43. CRC Press, 2003. http://dx.doi.org/10.1201/9781482286779-6.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
9

"SURVEY OF SEVERE ACCIDENT EXPERIMENTS AND ANALYSES IN JAPAN." In The Phebus Fission Product Project, 32–43. CRC Press, 2003. http://dx.doi.org/10.1201/9781482286779-6.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
10

Arutunjan, R. V., L. A. Bolshov, V. V. Vitukov, V. M. Goloviznin, A. M. Dykhne, V. P. Kiselev, S. V. Klementova, et al. "Theoretical Analysis and Numerical Modeling of Heat Transfer and Fuel Migration in Underlying Soils and Constructive Elements of Nuclear Plants during an Accident Release from the Core." In Fission Product Transport Processes in Reactor Accidents, 789–98. CRC Press, 2020. http://dx.doi.org/10.1201/9781003070344-64.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.

Тези доповідей конференцій з теми "Fission products Analysis"

1

WANG, ENHONG, N. T. BREWER, J. H. HAMILTON, A. V. RAMAYYA, J. K. HWANG, Y. X. LUO, J. O. RASMUSSEN, S. J. ZHU, G. M. TER-AKOPIAN, and YU TS OGANESSIAN. "FOUR-FOLD DATA ANALYSIS OF 252Cf FISSION PRODUCTS." In Proceedings of the Fifth International Conference on ICFN5. WORLD SCIENTIFIC, 2013. http://dx.doi.org/10.1142/9789814525435_0084.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
2

Tian Chenyang, Guo Huiping, Lv Ning, Zhao Kuo, Ma Wenyan, Xu Peng, Zuo Guangxia, Lv Wenhui, and Li Jinjun. "Analysis on delayed gamma spectra of products from uranium fission." In 2015 12th IEEE International Conference on Electronic Measurement & Instruments (ICEMI). IEEE, 2015. http://dx.doi.org/10.1109/icemi.2015.7494172.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
3

Cao, Jianzhu, Tao Liu, Yuanyu Wu, Hong Li, and Yuanzhong Liu. "Analysis of Radioactive Source Term for Modular HTGR During Normal Operation." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30075.

Повний текст джерела
Анотація:
The methods of radioactive source term analysis are introduced in detail for the modular high temperature gas cooled reactor in China. Radioactive fission products and activation products produced in the reactor are described. For fission products, the emphasis is on the process from production through release to the environment for noble gas, iodine and long-lived metallic nuclides. For activation products, it mainly introduces the behaviors of H-3 and C-14. Especially the permeation process from primary circuit to secondary circuit is described for H-3. Using the preliminary design parameter
Стилі APA, Harvard, Vancouver, ISO та ін.
4

Yun, J. I., K. Y. Suh, and C. S. Kang. "Heat and Fission Product Transport in a Molten U-Zr-O Pool With Crust." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22438.

Повний текст джерела
Анотація:
Heat transfer and fluid flow in a molten pool are influenced by internal volumetric heat generated from the radioactive decay of fission product species retained in the pool. The pool superheat is determined based on the overall energy balance that equates the heat production rate to the heat loss rate. Decay heat of fission products in the pool was estimated by product of the mass concentration and energy conversion factor of each fission product. For the calculation of heat generation rate in the pool, twenty-nine elements were chosen and classified by their chemical properties. The mass con
Стилі APA, Harvard, Vancouver, ISO та ін.
5

Porcheron, Emmanuel, and Pascal Lemaitre. "Analysis of Aerosol Collection by Droplets: Application to Fission Products Removal in Case of Severe Accident." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48582.

Повний текст джерела
Анотація:
TOSQAN is an experimental program undertaken by the Institut de Radioprotection et de Suˆrete´ Nucle´aire (IRSN) in order to perform thermal hydraulic containment studies. The TOSQAN facility is a large enclosure devoted to simulate typical accidental thermal hydraulic flow conditions in nuclear Pressurized Water Reactor (PWR) containment. The TOSQAN facility, which is highly instrumented with non-intrusive optical diagnostics, is particularly adapted to nuclear safety CFD code validation. The present work is devoted to study the interaction of a water spray injection used as a mitigation mean
Стилі APA, Harvard, Vancouver, ISO та ін.
6

Blaise, P., S. Cathalau, N. Thiollay, P. Fougeras, V. Laval, H. Philibert, J. M. Girard та J. P. Hudelot. "Fission Products Particular Peak Measurement for UO2-Gd2O3-MOX γ-Scanning Renormalization in 100% MOX ABWR Mock-Up Cores". У 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49464.

Повний текст джерела
Анотація:
This paper presents the principles of the peak check measurements by gamma spectrometry. One details the main equations used for the analysis of the raw data as the calculation of the different sources of uncertainties and their propagation on the result. The method is illustrated with actual examples from the French-Japanese BASALA ABWR 100% MOX experimental program. • For each individual fission rate, the systematical uncertainty due to the radioactive decay data is smaller than the statistical uncertainty due to the counting process. • The main part of the final uncertainty on the scaling f
Стилі APA, Harvard, Vancouver, ISO та ін.
7

Kim, Young Min, M. S. Cho, Y. W. Lee, and W. J. Lee. "Development of a Fuel Performance Analysis Code COPA." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58040.

Повний текст джерела
Анотація:
A fuel performance analysis code for a very high temperature gas-cooled reactor (VHTR) COPA (Coated Particle) is being developed at the Korea Atomic Energy Research Institute (KAERI). The COPA code consists of nine modules: BURN, TEMTR, TEMPEB, TEMBL, MECH, FAIL, FPREL, ABAQ, and MPRO. The BURN determines neutron flux and fluence at a location of a reactor core, and then calculates a fuel burnup, a fission rate per volume and a fission product inventory throughout a fuel particle and a fuel element. The TEMTR, TEMPEB and TEMBL calculate the temperature distributions in a coated fuel particle,
Стилі APA, Harvard, Vancouver, ISO та ін.
8

Li, Ran, and Jiyang Yu. "Development of PCCSAP-3D Code for Passive Containment: Models of Noncondensable Gases, Aerosols and Fission Products." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15606.

Повний текст джерела
Анотація:
PCCSAC-3D is a code originally developed for AC600 containment thermo-hydraulic analysis. Its validated capabilities include simulating the behaviors of steam-air mixture and liquid water under the unique conditions of an AC600/AP1000 containment after a DBA. The film-tracking model applied gives it the ability to simulate the liquid film both outside and inside the steel containment. Refined with some new models, the new version of the code, named PCCSAP-3D, can cover hydrogen behavior, fission products behavior (in the form of gas and aerosol) and iodine behavior. In the module of noncondens
Стилі APA, Harvard, Vancouver, ISO та ін.
9

Kienzler, Bernhard, and Ernesto González-Robles. "State-of-the-Art on Instant Release of Fission Products From Spent Nuclear Fuel." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96044.

Повний текст джерела
Анотація:
Within the EURATOM FP7 Collaborative Project “Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel (CP FIRST-Nuclides)”, a State-of-the-Art Report was prepared. The fast / instant release fraction (IRF) is defined as a fraction of the inventory of radionuclides that may be rapidly released from the fuel and fuel assembly materials at the time of canister breaching. In the context of safety analysis for a repository, the time span for mobilization of this fraction can be considered instantaneously, even if the process takes some time in experiments. Radionuclides cont
Стилі APA, Harvard, Vancouver, ISO та ін.
10

Tang, Changbing, Yongjun Jiao, Wenjie Li, Tao Qing, Yifei Miao, and Ping Chen. "Numerical Simulation of Different Sizes Missing Pellet Surface Effects on Thermal-Mechanical Behaviors in Nuclear Fuel Rods." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60116.

Повний текст джерела
Анотація:
Nuclear fuel rods is mainly composed of uranium dioxide pellets and zirconium alloy cladding, there is a gap between pellets and cladding, which is filled with helium. Under the reactor operation conditions, pellets produce a lot of heat by nuclear fission reactions and at the same time also produce lots of radioactive fission products. Cladding serve as the first barrier to accommodate radioactive fission product, needs to maintain its structural integrity under the reactor operation conditions. Cladding stresses can be effectively limited by controlling power increase rates. However, pellet
Стилі APA, Harvard, Vancouver, ISO та ін.

Звіти організацій з теми "Fission products Analysis"

1

Demkowicz, Paul A., Jason M. Harp, Philip L. Winston, and Scott A. Ploger. Analysis of Fission Products on the AGR-1 Capsule Components. Office of Scientific and Technical Information (OSTI), March 2013. http://dx.doi.org/10.2172/1097137.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
2

Petrova, Petya H., and Pavlin P. Groudev. Analysis of the Fission Products Behaviour in the Phebus FPT1 Experiment by Using the ASTEC V2.1 Code. "Prof. Marin Drinov" Publishing House of Bulgarian Academy of Sciences, May 2019. http://dx.doi.org/10.7546/crabs.2019.05.05.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
3

Simpson, Michael F., Supathorn Phongikaroon, and Jinsuo Zhang. Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products. Office of Scientific and Technical Information (OSTI), March 2018. http://dx.doi.org/10.2172/1432793.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
4

Chapman, Carolyn R. Analysis of the Fission Yeast Rad3+ Gene Product. Fort Belvoir, VA: Defense Technical Information Center, January 1999. http://dx.doi.org/10.21236/ada368445.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
5

Horne, Steven M., and Kevin R. Jackman. Multispectral Gamma-Ray Analysis Using Clover Detectors with Application to Uranium Fission Product Analysis. Office of Scientific and Technical Information (OSTI), April 2013. http://dx.doi.org/10.2172/1077011.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
6

Martin, R. C. ANALYSIS OF FISSION PRODUCT RELEASE DATA FOR GERMAN FUEL SPHERE HFR-K3/3. Office of Scientific and Technical Information (OSTI), September 1993. http://dx.doi.org/10.2172/10199681.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
7

Suh, K. Y. Modeling of in-vessel fission product release including fuel morphology effects for severe accident analyses. Office of Scientific and Technical Information (OSTI), October 1989. http://dx.doi.org/10.2172/7261581.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
8

Harp, Jason M. Analysis of Individual Compact Fission Product Inventory and Burnup for the AGR-1 TRISO Experiment using Gamma Spectrometry. Office of Scientific and Technical Information (OSTI), December 2010. http://dx.doi.org/10.2172/1494149.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
9

Rest, J. The DART dispersion analysis research tool: A mechanistic model for predicting fission-product-induced swelling of aluminum dispersion fuels. User`s guide for mainframe, workstation, and personal computer applications. Office of Scientific and Technical Information (OSTI), August 1995. http://dx.doi.org/10.2172/149983.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
10

McCartney, M. A., and M. G. Plys. Modifications for the development of the MAAP-DOE code: Volume 1, A mechanistic model for core-concrete interactions and fission product release in integrated accident analysis Task 3. 4. 3. Office of Scientific and Technical Information (OSTI), November 1988. http://dx.doi.org/10.2172/6300751.

Повний текст джерела
Стилі APA, Harvard, Vancouver, ISO та ін.
Також вас можуть зацікавити розширені добірки на тему "Fission products Analysis" для конкретних типів джерел:
Статті в журналах Дисертації
Ми пропонуємо знижки на всі преміум-плани для авторів, чиї праці увійшли до тематичних добірок літератури. Зв'яжіться з нами, щоб отримати унікальний промокод!

До бібліографії