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   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Calculation methods and computer codes.
            Methods for solution of isotope kinetics problems and for calculation of fuel cycle parameters.
Analysis of multi-scale spatial separation in a block-type thorium-loaded helium-cooled high-temperature reactor
Jie Huang, Ming Ding
Ann. Nucl. Energy, Vol: 101, No: 0 , published: 01 March 2017
The use of representativity theory in the depletion calculations of SFR blankets
Jean-François Lebrat, Jean Tommasi
Ann. Nucl. Energy, Vol: 101, No: 0 , published: 01 March 2017
BEAVRS full core burnup calculation in hot full power condition by RMC code
Shichang Liu, Jingang Liang, Qu Wu, JuanJuan Guo, Shanfang Huang, Xiao Tang, Zeguang Li, Kan Wang
Ann. Nucl. Energy, Vol: 101, No: 0 , published: 01 March 2017
Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE
Benjamin R. Betzler, Jeffrey J. Powers, Andrew Worrall
Ann. Nucl. Energy, Vol: 101, No: 0 , published: 01 March 2017
Evaluating the effect of cross-over length and mutation rate variations on the performance of DERMAGA
Doddy Kastanya
Ann. Nucl. Energy, Vol: 100, No: P2 , published: 01 February 2017
Optimization of Minor Actinide–Bearing Radial Blankets for Heterogeneous
Timothée Kooyman, Laurent Buiron, Gérald Rimpault
Nucl. Sci. and Eng., Vol: 185, No: 2 , published: 01 February 2017
Development of a set of benchmark problems to verify numerical methods for solving burnup equations
Daniel Lago, Farzad Rahnema
Ann. Nucl. Energy, Vol: 99, No: 0 , published: 01 January 2017
Development and verification of LOOP: A Linkage of ORIGEN2.2 and OpenMC
Anas Gul, K.S. Chaudri, R. Khan, M. Azeem
Ann. Nucl. Energy, Vol: 99, No: 0 , published: 01 January 2017
Physical model of the nuclear fuel cycle simulation code SITON
Á. Brolly, M. Halász, M. Szieberth, L. Nagy, S. Fehér
Ann. Nucl. Energy, Vol: 99, No: 0 , published: 01 January 2017
Diagnosing Undersampling Biases in Monte Carlo Eigenvalue and Flux Tally Estimates
Christopher M. Perfetti, Bradley T. Rearden, William J. Marshall
Nucl. Sci. and Eng., Vol: 185, No: 1 , published: 01 January 2017
Development of a new nuclide generation and depletion code using a topological solver based on graph theory
S. Kasselmann, O. Schitthelm, F. Tantillo, S. Scholthaus, C. Rössel, H.-J. Allelein
Nucl. Eng. Des., Vol: 306, No: 0 , published: 01 September 2016
Решение задач изотопной кинетики с полным числом элементов выхода продуктов деления
Соловьев А.В., Митенкова Е.Ф., Новиков Н.В., Соловьева Е.В.
Атом. энергия, Vol: 120, No: 3 , published: 01 March 2016
A Modal Expansion Equilibrium Cycle Perturbation Method for Optimizing Fast Reactors
Nicholas W. Touran, John C. Lee
Nucl. Sci. and Eng., Vol: 179, No: 1 , published: 25 January 2015
A Systematic Approach to Nuclear Fuel Cycle Analysis and Optimization
Stefano Passerini, Mujid S. Kazimi, Eugene Shwageraus
Nucl. Sci. and Eng., Vol: 178, No: 2 , published: 18 October 2014
Расчет изотопного состава и наведенной активности облученных материалов инновационных электроядерных установок
Ю.А. Коровин, А.В. Максимушкина
Изв. вузов. Ядер. энерг., Vol: 2014, No: 2 , published: 01 June 2014
Трансмутация малых актинидов в спектре нейтронов реактора на тепловых нейтронах
Ю.А. Казанский,М.И. Романов
Изв. вузов. Ядер. энерг., Vol: 2014, No: 2 , published: 01 June 2014
Расчет изотопного состава реакторных установок при моделиро-вании процессов выгорания и остаточного энерговыделения ядерного топлива в программном комплексе CONCORD
С. В. Мжачих,  А. В. Алексеев, А. Н. Гребенников, Е. А. Гусев, А. А. Ермаков, Е. А. Ириничев, С. С. Касаткин, Н. А. Крутько
Вопр. атом. науки и техн. Сер. Мат. моделир. физ. процессов, Vol: 2014, No: 1 , published: 01 January 2014
Axial discontinuity factors for the nodal diffusion analysis of high conversion BWR cores
E. Fridman, S. Duerigen, Y. Bilodid, D. Kotlyar, E. Shwageraus
Ann. Nucl. Energy, Vol: 62 (2013), No: 0 , published: 01 December 2013
Heterogeneous reactor core transport technique using response matrix and collision probability methods
O. Safarzadeh, A. Minuchehr, A.S. Shirani
Ann. Nucl. Energy, Vol: 62 (2013), No: 0 , published: 01 December 2013
Derivation of a stable coupling scheme for Monte Carlo burnup calculations with the thermal–hydraulic feedback
Jan Dufek, Henryk Anglart
Ann. Nucl. Energy, Vol: 62 (2013), No: 0 , published: 01 December 2013
Comparison of neutron diffusion and Monte Carlo simulations of a fission wave
A.G. Osborne, M.R. Deinert
Ann. Nucl. Energy, Vol: 62 (2013), No: 0 , published: 01 December 2013
Analysis of burn up effects on kinetic parameters in an Accelerator Driven Subcritical TRIGA reactor
M. Hassanzadeh, S.A.H. Feghhi
Ann. Nucl. Energy, Vol: 62 (2013), No: 0 , published: 01 December 2013
Development of time-dependent reaction rates to optimise predictor–corrector algorithm in ALEPH burn-up code
L. Fiorito, A. Stankovskiy, G. Van den Eynde, P.E. Labeau
Ann. Nucl. Energy, Vol: 62 (2013), No: 0 , published: 01 December 2013
Solving Linear Systems with Sparse Gaussian Elimination in the Chebyshev Rational Approximation Method
Maria Pusa, Jaakko Leppanen
Nucl. Sci. and Eng., Vol: 175, No: 3 , published: 07 November 2013
Using Generalized Laguerre Polynomials to Compute the Matrix Exponential in Burnup Equations
Ding She, Ang Zhu, Kan Wang
Nucl. Sci. and Eng., Vol: 175, No: 3 , published: 07 November 2013
Variational assimilation for xenon dynamical forecasts in neutronic using advanced background error covariance matrix modelling
Angélique Ponçot, Jean-Philippe Argaud, Bertrand Bouriquet, Patrick Erhard, Serge Gratton, Olivier Thual
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
Validation of simplified methods for fuel depletion calculations in gas-cooled fast reactors
Cecilia Martín-del-Campo, Ricardo Reyes-Ramírez, Juan-Luis François
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
MCNPX–BUCAL1 code to code verification through burnup analysis
B. El Bakkari, T. El Bardouni, B. Nacir, C. El Younoussi, Y. Boulaich, H. Boukhal
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
The stochastic implicit Euler method – A stable coupling scheme for Monte Carlo burnup calculations
Jan Dufek, Dan Kotlyar, Eugene Shwageraus
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
Адаптивная схема решения уравнений выгорания ядерного топлива с оценкой равновесной концентрации короткоживущих ядер
Д. Г. Модестов
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2013, No: 3 , published: 01 October 2013
Преимущества быстрого реактора с усовершенствованной активной зоной в сравнении с проектом реактора БРЕСТ-300
В. Я. Гольдин, Г. А. Пестрякова
Мат. моделир., Vol: 25, No: 10 , published: 01 October 2013
Core Design, Spent-Fuel Characteristics Assessment, and Fuel Cycle Analysis for Thorium-Uranium Breeding Recycle in Pressurized Water Reactors
Guangwen Bi, Shengyi Si, Chanyun Liu
Nucl. Technol., Vol: 183, No: 3 , published: 12 September 2013
Neutronics and Depletion Methods for Multibatch Fluoride Salt-Cooled High-Temperature Reactors with Slab Fuel Geometry
Anselmo T. Cisneros, Dan Ilas
Nucl. Technol., Vol: 183, No: 3 , published: 12 September 2013
On the use of predictor–corrector method for coupled Monte Carlo burnup codes
D. Kotlyar, E. Shwageraus
Ann. Nucl. Energy, Vol: 58, No: , published: 01 August 2013
Design a computational program to calculate the composition variations of nuclear materials in the reactor operations
Meysam Mohmmadnia, Ali Pazirandeh, Mostafa Sedighi, Mohammad Hassan Jalili Bahabadi, Shima Tayefi
Ann. Nucl. Energy, Vol: 57, No: , published: 01 July 2013
Optimization of designing the core fuel loading pattern in a VVER-1000 nuclear power reactor using the genetic algorithm
M. Rafiei Karahroudi, S.A. Mousavi Shirazi, K. Sepanloo
Ann. Nucl. Energy, Vol: 57, No: , published: 01 July 2013
Multi-objective loading pattern enhancement of PWR based on the Discrete Firefly Algorithm
N. Poursalehi, A. Zolfaghari, A. Minuchehr
Ann. Nucl. Energy, Vol: 57, No: , published: 01 July 2013
Flattening of burnup reactivity in long-life prismatic HTGR by particle type burnable poisons
Toru Obara, Taiki Onoe
Ann. Nucl. Energy, Vol: 57, No: , published: 01 July 2013
Numerical stability of the predictor–corrector method in Monte Carlo burnup calculations of critical reactors
Jan Dufek, Dan Kotlyar, Eugene Shwageraus, Jaakko Leppänen
Ann. Nucl. Energy, Vol: 56, No: , published: 01 June 2013
Development of the point-depletion code DEPTH
Ding She, Kan Wang, Ganglin Yu
Nucl. Eng. Des., Vol: 258, No: , published: 01 May 2013
Quadratic Depletion Method for Gadolinium Isotopes in CASMO-5
Deokjung Lee, Joel Rhodes, Kord Smith
Nucl. Sci. and Eng., Vol: 174, No: 1 , published: 01 May 2013
Вопросы эволюции изотопных составов при замыкании топливных циклов реакторов на быстрых нейтронах
Симоненко В.А., Макеева И.Р., Волков И.А., Дырда Н.Д.
Вопр. атом. науки и техн. Сер. Материаловед. и нов. матер., Vol: 2013, No: 2 , published: 01 May 2013
Applying second-order adjoint perturbation theory to time-dependent problems
L. Gilli, D. Lathouwers, J.L. Kloosterman, T.H.J.J. van der Hagen
Ann. Nucl. Energy, Vol: 53, No: , published: 01 March 2013
Efficient and accurate depletion calculations via two-block decomposition of nuclide concentration vector
Yoonhee Lee, Nam Zin Cho
Ann. Nucl. Energy, Vol: 53, No: , published: 01 March 2013
Решение задачи нуклидной кинетики с полной матрицей переходов нуклидов
Селезнев Е. Ф., Белов А. А.
Изв. РАН. Энерг., Vol: 2013, No: 3 , published: 01 March 2013
A generalized adjoint framework for sensitivity and global error estimation in time-dependent nuclear reactor simulations
H.F. Stripling, M. Anitescu, M.L. Adams
Ann. Nucl. Energy, Vol: 52, No: , published: 01 February 2013
Modelling fuel behaviour in a reactor park using fuel cycle kinetics
J.A.B. van Rhijn, S.A. Christie, D. Lathouwers, J.L. Kloosterman
Ann. Nucl. Energy, Vol: 51, No: , published: 01 January 2013
Double adjoint method for determining the contribution of composition to reactivity at different times
S.A. Christie, D. Lathouwers, J.L. Kloosterman
Ann. Nucl. Energy, Vol: 51, No: , published: 01 January 2013
Comparison of metaheuristic optimization techniques for BWR fuel reloads pattern design
Juan-Luis François, Juan José Ortiz-Servin, Cecilia Martín-del-Campo, Alejandro Castillo, Jaime Esquivel-Estrada
Ann. Nucl. Energy, Vol: 51, No: , published: 01 January 2013
Development of burnup methods and capabilities in Monte Carlo code RMC
Ding She, Yuxuan Liu, Kan Wang, Ganglin Yu, Benoit Forget, Paul K. Romano, Kord Smith
Ann. Nucl. Energy, Vol: 51, No: , published: 01 January 2013
Startup of “CANDLE” burnup in a Gas-cooled Fast Reactor using Monte Carlo method
M. Kheradmand Saadi, A. Abbaspour, A. Pazirandeh
Ann. Nucl. Energy, Vol: 50, No: , published: 01 December 2012
Burnup span sensitivity analysis of different burnup coupling schemes
M. Kheradmand Saadi, A. Abbaspour, A. Pazirandeh
Ann. Nucl. Energy, Vol: 47, No: , published: 01 September 2012
Application of a hybrid method based on the combination of genetic algorithm and Hopfield neural network for burnable poison placement
F. Khoshahval, A. Fadaei
Ann. Nucl. Energy, Vol: 47, No: , published: 01 September 2012
Nominal Range Sensitivity Analysis of peak radionuclide concentrations in randomly heterogeneous aquifers
F. Cadini, J. De Sanctis, A. Cherubini, E. Zio, M. Riva, A. Guadagnini
Ann. Nucl. Energy, Vol: 47, No: , published: 01 September 2012
Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE
Germina Ilas, Ian C. Gauld, Georgeta Radulescu
Ann. Nucl. Energy, Vol: 46, No: , published: 04 August 2012
Accuracy assessment of a new Monte Carlo based burnup computer code
B. El Bakkari, T. ElBardouni, B. Nacir, C. ElYounoussi, Y. Boulaich, O. Meroun, M. Zoubair, E. Chakir
Ann. Nucl. Energy, Vol: 45, No: , published: 04 July 2012
Quadratic inner element subgrid scale discretisation of the Boltzmann transport equation
C.M.J. Baker, A.G. Buchan, C.C. Pain, B. Tollit, M.D. Eaton, P. Warner
Ann. Nucl. Energy, Vol: 45, No: , published: 04 July 2012
A Burnup-Dependent Isomeric Production Branching Ratio Treatment
W. Haeck, B. Cochet, L. Aguiar
Nucl. Sci. and Eng., Vol: 171, No: 1 , published: 04 May 2012
Mathematical Modeling and Its Applications for Mass Flow in a Nuclear Fuel Cycle
Raphael Craplet, Joonhong Ahn
Nucl. Technol., Vol: 177, No: 3 , published: 04 March 2012
Simplified models for pebble-bed HTR core burn-up calculations with Monteburns2.0©
E. Bomboni, N. Cerullo, G. Lomonaco
Ann. Nucl. Energy, Vol: 40, No: , published: 04 February 2012
An integrated simulation framework for the performance assessment of radioactive waste repositories
F. Cadini, J. De Sanctis, A. Cherubini, E. Zio, M. Riva, A. Guadagnini
Ann. Nucl. Energy, Vol: 39, No: , published: 04 January 2012
Spent fuel pool storage calculations using the ISOCRIT burnup credit tool
Vefa N. Kucukboyaci, William J. Marshall
Ann. Nucl. Energy, Vol: 39, No: , published: 04 January 2012
Theory and calculation of 135Xe concentration time evolution for the nuclear power plant CNA II
Osvaldo Moreira
Ann. Nucl. Energy, Vol: 39, No: , published: 04 January 2012
Теория подобия в нейтронной кинетике и её использование для решения прикладных задач РФЯЦ — ВНИИЭФ
Н.Б. Бабичев, П.С. Бондарев, В.П. Незнамов
Успехи физ. наук, Vol: 181, No: 9 , published: 14 September 2011
Функции ценности в задаче расчета выгорания топлива в ВВЭР
Семенов В.Н.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2010, No: 4 , published: 15 February 2010
Моделирование изотопной кинетики методом Монте-Карло
Давиденко В.Д./Цибульский В.Ф.
Атом. энергия, Vol: 109, No: 4 , published: 10 February 2010
Особенности резонансного поглощения нейтронов в торийсодержащих размножающих системах, вызванные изменением отношения объемов замедлителя и топлива
Шаманин И.В./Годовых А.В./Селезнев П.А.
Изв. вузов. Ядер. энерг., Vol: 2009, No: 1 , published: 09 December 2009
Аналитические оценки содержания изотопов слабообогащенного регенерированного урана в многопоточных оптимальных каскадах
Палкин В.А./Маслюков Е.В.
Атом. энергия, Vol: 107, No: 6 , published: 17 May 2009
Описание программы GETERA
Пряничников А.В.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2009, No: 3 , published: 25 January 2009
Программа MCU-FCP для расчета переноса нейтронов методом вероятностей первых столкновений
Гомин Е.А./Гуревич М.И./Калугин М.А./и др.
Атом. энергия, Vol: 105, No: 2 , published: 25 December 2008
Нейтронно-физический анализ перспективных топливных циклов реакторов типа CANDU с позиций эффективности использования природных ресурсов и показателей безопасности
Со Мин Мин/Наумов В.И.
Изв. вузов. Ядер. энерг., Vol: 2008, No: 3 , published: 10 December 2008
Экономичный расчет многогруппового уравнения переноса нейтронов для пересчета усредненных по спектру сечений
Аристова Е.Н./Гольдин В.Я.
Мат. моделир., Vol: 20, No: 11 , published: 16 November 2008
Регулирование нейтронного спектра электроядерной мишени путем изменения ее начального изотопного состава
Хорасанов Г.Л.\Иванов А.П.\Блохин А.И.
Вопр. атом. науки и техн. Сер. Ядер. константы, Vol: 2005, No: 1-2 , published: 01 January 2005
Способ расчета поканального высотного профиля выгорания топлива в 3D расчетах РБМК
Чичулин Н.Л.\Ионов А.И.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2004, No: 3 , published: 01 January 2004
Представление осколков деления двумя эффективными осколками. Ч. ~I~I. Верификационные расчеты
Волков Ю.В.\Дугинов О.Б.
Изв. вузов. Ядер. энерг., Vol: 2004, No: 3 , published: 01 January 2004
Optimization layer by layer networks for in-core fuel management optimixation computations in PWRs
Jang C.S., Shim H.J., Kim C.H.
Ann. Nucl. Energy, Vol: 28, No: 11 , published: 15 July 2001
Self-stabilizing criticality wave
van Dam H.
Ann. Nucl. Energy, Vol: 27, No: 16 , published: 01 November 2000
Long-term control of excess reactivity by burnable particles
van Dam H.
Ann. Nucl. Energy, Vol: 27, No: 8 , published: 15 May 2000
Xenon transient analysis for direct use of spent pressurized water reactor fuel in CANDU reactors (DUPIC)
Jeong C.J., Choi H.
Ann. Nucl. Energy, Vol: 27, No: 3 , published: 01 February 2000
Analysis of the burnup credit benchmark with an updated WIMS-D library
Aldama D.L., Trkov A.
Ann. Nucl. Energy, Vol: 27, No: 2 , published: 15 January 2000
Verification of HERLIOS and HELIOS/AFEN against PWER critical experiments loaded with high plutonium content MOX fuels
Joo H.-K., Jung H.-G., Kim T.-K. et al.
Ann. Nucl. Energy, Vol: 26, No: 10 , 1999
Advanced U-Np-Pu fuel to achieve long-life core in heavy water reactor
Nikitin K., Saito M., Artisyuk V. et al.
Ann. Nucl. Energy, Vol: 26, No: 15 , 1999
A perturbation method for pointwise nuclide depletion calculations
Yang W.S.
Ann. Nucl. Energy, Vol: 26, No: 4 , 1999
A method to avoid spatial treatment in xenon poisoning calculation while providing conservative reactivity estimates
Toshinsky V.G., Sekimoto H., Toshinsky G.I.
Ann. Nucl. Energy, Vol: 26, No: 5 , 1999
Application of nonlinear optimization to reactor core fuel reloading
Quist A.J., van Geemert R., Hoogenboom J.E. et al.
Ann. Nucl. Energy, Vol: 26, No: 5 , 1999
A new approach to the use of genetic algorithms to solve the pressurized water reactor`s fuel management optimization problem
Chapot J.L.C., Da Silva F.C., Schirru R.
Ann. Nucl. Energy, Vol: 26, No: 7 , 1999
An economically optimum PWR reload core for a 36-month cycle
Garcia-Delgado L., Driscoll M.J., Meyer J.E. et al.
Ann. Nucl. Energy, Vol: 26, No: 8 , 1999
Multiobjective fuel management optimization for self-fuel-providing LMFBR using genetic algorithms
Goshinsky V.G., Sekimoto H., Toshinsky G.I.
Ann. Nucl. Energy, Vol: 26, No: 9 , 1999
Методика расчета нейтронно-физических характеристик ячейки активной зоны реактора
Маршалкин В.Е., Горбатенко Т.М., Повышев В.М., Житник А.К.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 1998, No: 3 , published: 01 January 1998
Справочно-информационная система ядерно-физических свойств нуклидов и радиоактивных цепочек распада
Пляскин В.И., Косилов Р.А., Мантуров Г.Н.
Изв. вузов. Ядер. энерг., Vol: 1998, No: 6 , published: 01 January 1998
Higher order generalized perturbation theory for boiling water reactor in-core fuel management optimization
Moore Brian R., Turinsky Paul J.
Nucl. Sci. and Eng., Vol: 130, No: 1 , 1998
Determination of the uncertainty in assembly average burnup
Cacciapouti R.J., Lam G.M., Theriault P.A., Delmolino P.M.
Trans. Amer. Nucl. Soc. 1994. 70, N, Vol: 79, No: , 1998
ALIGR technique for reactor fuel burnup calculations using the Monte Carlo method
Kalugin M.A., Maiorov L.V.
Trans. Amer. Nucl. Soc. 1994. 70, N, Vol: 79, No: , 1998
Modelling and verification of the PWR burnable Poison designs by ELCOS code system
Galperin A., Grimm P., Raizes V.
Ann. Nucl. Energy, Vol: 22, No: 5 , published: 01 May 1995
Deux methodes de decomposition de domaine pour la resolution d`equations aux derivees partielles avec conditions de periodicite: Application a la theorie de l` homogeneisation
Charpentier I., Maday Y.
C. R. Acad. Sci. Ser. 1, Vol: 321, No: 3 , 1995
Solution of depletion chain equations using nonsingular Bateman coefficients
Vukadin Z.
Nucl. Sci. and Eng., Vol: 117, No: 2 , 1994
F[N] method for solving transport problems
Garcia R.D.M., Siewert C.E., Thomas J.R.
Trans. Amer. Nucl. Soc. 1994. 70, N, Vol: 71, No: , 1994
Аппpоксимация зависимостей концентpации нуклидов от вpемени пpостыми аналитическими функциями
Буpак А.О., Еpемина А.Н., Рудак Э.А.
Атом. энергия, Vol: 94, No: 6
Пpогpамма SHERHAN для моделиpования выгоpания в тpехмеpном pеактоpе
Кочуpов Б.П.
Атом. энергия, Vol: 95, No: 1
Тpансмутация амеpиция в тяжеловодном pеактоpе
Кваpацхели А.Ю., Конев В.Н., Кочуpов Б.П.
Атом. энергия, Vol: 95, No: 1
Тpансмутация долгоживущих актиноидов в энеpгетических pеактоpах
Беpгельсон Б.Р., Геpасимов А.С., Тихомиpов Г.В.
Атом. энергия, Vol: 95, No: 4
Спpавочно-инфоpмационная интеpактивная система "Тpансмутация нуклидов в ядеpных pеактоpах"
Пляскин В.И., Косилов Р.А., Мантуpов Г.Н.
Вопp. атом. науки и техн. Сер. Ядеp. константы., Vol: 00, No: 1-2
Развитие программного обеспечения для оценки точности моделирования кампании ядерного реактора и оценки реакторного эксперимента
Иванов Е.А.
Изв. вузов. Ядер. энерг., Vol: , No: 1
Simulation of mixed-oxide and low-enriched uranium fuel burnup in a pressurized water reactor and validation against distructive analysis results
Murphy B.D., Primm R.T., III
Nucl. Sci. and Eng., Vol: 142, No: 3
Sensitivity analysis of nuclide importance to one-group neutron cross sections
Sekimoto Hiroshi, Nemoto Atsushi, Yoahimura Yoshikane
Nucl. Sci. and Eng., Vol: 138, No: 3
Методика расчета нейтронно-физических параметров и изотопной кинетики ячейки тепловых реакторов и ее тестирование
Маршалкин В.Е., Повышев В.М., Житник А.К. и др.
Вопр. атом. науки и техн. Сер. Теор. и прикл. физ., Vol: , No: 1
Расчет выгорания с использованием программы ORIGEN в вычислительном комплексе CONKEMO
Забродская С.В., Хомяков Ю.С., Цибуля А.А.
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