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   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Reactors calculations.
            Thermal reactors.
Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X
A. Aures, F. Bostelmann, M. Hursin, O. Leray
Ann. Nucl. Energy, Vol: 101, No: 0 , published: 01 March 2017
Isogeometric analysis for the multigroup neutron diffusion equation with applications in reactor physics
J.A. Welch, J. Kópházi, A.R. Owens, M.D. Eaton
Ann. Nucl. Energy, Vol: 101, No: 0 , published: 01 March 2017
Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
M. Hursin, S. Bogetic, A. Dohkane, S. Canepa, O. Zerkak, H. Ferroukhi, A. Pautz
Ann. Nucl. Energy, Vol: 101, No: 0 , published: 01 March 2017
The basic features of a closed fuel cycle without fast reactors
International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016 (ICNRP-2016)
5–9 September 2016, Moscow, Russian Federation
E. A. Bobrov, P.N. Alekseev and P.S.Teplov
J. Phys.: Conf. Ser., Vol: 2017, No: 781 , published: 21 February 2017
Calculation evaluation of multiplying properties of LWR with thorium fuel
International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016 (ICNRP-2016)
5–9 September 2016, Moscow, Russian Federation
I.V.Shamanin,V.M.Grachev,V.V.Knyshev,S.V.Bedenko and N.G.Novikova
J. Phys.: Conf. Ser., Vol: 2017, No: 781 , published: 21 February 2017
Improvement of Modeling HTGR Neutron Physics by Uncertainty Analysis with the Use of Cross-Section Covariance Information
International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016 (ICNRP-2016)
5–9 September 2016, Moscow, Russian Federation
V.F.Boyarinov,A.V.Grol,P.A.Fomichenko and M.Yu.Ternovykh
J. Phys.: Conf. Ser., Vol: 2017, No: 781 , published: 21 February 2017
Test case for VVER-1000 complex modeling using MCU and ATHLET
International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016 (ICNRP-2016)
5–9 September 2016, Moscow, Russian Federation
R.B.Bahdanovich,E.V.Bogdanova,I.D.Gamtsemlidze,S.P.Nikonov and G.V.Tikhomirov
J. Phys.: Conf. Ser., Vol: 2017, No: 781 , published: 21 February 2017
Thorium-based plutonium incineration in the I2S-LWR
Dan Kotlyar, Geoffrey T. Parks, Eugene Shwageraus
Ann. Nucl. Energy, Vol: 100, No: P1 , published: 01 February 2017
Nuclear-data uncertainty propagations in burnup calculation for the PWR assembly
Chenghui Wan, Liangzhi Cao, Hongchun Wu, Wei Shen
Ann. Nucl. Energy, Vol: 100, No: P2 , published: 01 February 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
Assembly-level analysis of heterogeneous Th–Pu PWR fuel
Nurjuanis Zara Zainuddin, Geoffrey T. Parks, Eugene Shwageraus
Ann. Nucl. Energy, Vol: 100, No: P2 , published: 01 February 2017
Effect of 3-D moderator flow configurations on the reactivity of CANDU nuclear reactors
Foad Mehdi Zadeh, St́ephane Etienne, Richard Chambon, Guy Marleau, Alberto Teyssedou
Ann. Nucl. Energy, Vol: 99, No: 0 , published: 01 January 2017
New techniques for designing the initial and reload cores with constant long cycle lengths
Jun Shi, Samuel Levine, Kostadin Ivanov
Ann. Nucl. Energy, Vol: 99, No: 0 , published: 01 January 2017
Comparative economic analysis of the Integral Molten Salt Reactor and an advanced PWR using the G4-ECONS methodology
Ludmila Samalova, Ondrej Chvala, G. Ivan Maldonado
Ann. Nucl. Energy, Vol: 99, No: 0 , published: 01 January 2017
Total sensitivity and uncertainty analysis for LWR pin-cells with improved UNICORN code
Chenghui Wan, Liangzhi Cao, Hongchun Wu, Wei Shen
Ann. Nucl. Energy, Vol: 99, No: 0 , published: 01 January 2017
Radiotoxicity implications and reduction strategies of minor actinide in a boiling water reactor
Gustavo Alonso, Eduardo Martinez, J. Ramón Ramírez, Hector Hernandez
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
Improving the refueling cycle of a WWER-1000 using cuckoo search method and thermal-neutronic coupling of PARCS v2.7, COBRA-EN and WIMSD-5B codes
M. Yarizadeh-Beneh, H. Mazaheri-Beni, N. Poursalehi
Nucl. Eng. Des., Vol: 310, No: 0 , published: 15 December 2016
Многоуровневая иерархия сетей в геометрическом модуле пакета программ MCU
М . И . Гуревич , О . В . Тельковская , Б . К . Чукбар
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2016, No: 3 , published: 31 October 2016
Коэффициенты д иффузии для конечно - разностных схем расчётов РБМК
Р . В . Плеханов , Д . А . Лысов
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2016, No: 3 , published: 31 October 2016
Моделирование запроектной аварии с полным обесточиванием РБМК
Краюшкин А . В ., Захарова Л . Н .
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2016, No: 3 , published: 31 October 2016
Инженерные коэффициенты запаса при проектировании топливных загрузок ВВЭР
М . П . Лизоркин , Л . К . Шишков
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2016, No: 3 , published: 31 October 2016
Full-Core Evaluation of Uranium-Based Fuels Augmented with Small Amounts of Thorium in Pressure Tube Heavy Water Reactors
Ashlea V. Colton, Blair P. Bromley
Nucl. Technol., Vol: 196, No: 1 , published: 01 October 2016
A Coarse-Mesh Coupled Neutronics and Thermal Fluids Method for Prismatic Cores
Kevin John Connolly, Alexander J. Huning, Farzad Rahnema, Srinivas Garimella
Nucl. Sci. and Eng., Vol: 184, No: 2 , published: 01 October 2016
The IAEA coordinated research programme on HTGR uncertainty analysis: Phase I status and Ex. I-1 prismatic reference results
Friederike Bostelmann, Gerhard Strydom, Frederik Reitsma, Kostadin Ivanov
Nucl. Eng. Des., Vol: 306, No: 0 , published: 01 September 2016
Метод офсет-мощностной фазовой диаграммы для управления энерговыделением реактора
Аверьянова С.П., Вохмянина Н.С., Злобин Д.А., Филимонов П.Е., Кузнецов В.И., Лаговский В.Б.
Атом. энергия, Vol: 121, No: 3 , published: 01 September 2016
Влияние нуклидного состава топливной загрузки на размножающие и воспроизводящие свойства активной зоны реакторной установки КЛТ-40С
Байбаков Д.Ф., Годовых А.В., Мартынов И.С., Нестеров В.Н.
Изв. вузов. Ядер. энерг., Vol: 2016, No: 2 , published: 01 April 2016
Ториевая реакторная установка малой мощности, работающая в сверхдлинной кампании
Шаманин И.В., Чертков Ю.Б., Беденко С.В.
Изв. вузов. Ядер. энерг., Vol: 2016, No: 2 , published: 01 April 2016
О равновесном изотопном составе торийуран-плутониевого топливного цикла
Маршалкин В.Е., Повышев В.М.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2015, No: 4 , published: 01 September 2015
Uncertainty in the Fast Neutron Fluence in Function of the Fission Source and Its Burnup Dependence
Claude Mounier, Pietro Mosca
Nucl. Sci. and Eng., Vol: 179, No: 2 , published: 25 February 2015
Eigenvalue Implicit Sensitivity to Self-Shielding Calculations in Heterogeneous Geometries
M. Dion, G. Marleau
Nucl. Sci. and Eng., Vol: 179, No: 2 , published: 25 February 2015
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses: Criticality (k eff) Predictions
J. M. Scaglione, D. E. Mueller, J. C. Wagner
Nucl. Technol., Vol: 188, No: 3 , published: 28 December 2014
Impact of Accident-Tolerant Fuels and Claddings on the Overall Fuel Cycle: A Preliminary Systems Analysis
Gilles J. Youinou, R. Sonat Sen
Nucl. Technol., Vol: 188, No: 2 , published: 10 December 2014
Гибридный реактор синтеза-деления с ториевым бланкетом. О его потенциале в топливном цикле ядерных реакторов
Шмелев А.Н., Куликов Г.Г., Курнаев В.А., Салахутдинов Г.Х., Куликов Е.Г., Апсэ В.А.
Вопр. атом. науки и техн. Сер. Термоядер. синтез, Vol: 2014, No: 2 , published: 01 May 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
Sub-channel analysis of 8 × 8 and 9 × 9 BWR fuel assemblies with different two-phase flow models
M. Hashemi-Tilehnoee, M. Rahgoshay
Ann. Nucl. Energy, Vol: 62 (2013), No: 0 , published: 01 December 2013
Evaluating the effects of cooling schedule on the performance of ADORE
Doddy Kastanya
Ann. Nucl. Energy, Vol: 62 (2013), No: 0 , published: 01 December 2013
Analysis of implicit and explicit lattice sensitivities using DRAGON
M.R. Ball, D.R. Novog, J.C. Luxat
Nucl. Eng. Des., Vol: 265, No: 0 , published: 01 December 2013
Convergence analysis of neutronic/thermohydraulic coupling behavior of SCWR
Shichang Liu, Jiejin Cai
Nucl. Eng. Des., Vol: 265, No: 0 , published: 01 December 2013
Experimental Validation of 3-D Reconstructed Pin Power Distributions in Full-Scale BWR Fuel Assemblies with Partial-Length Rods
Flavio Dante Giust, Peter Grimm, Rakesh Chawla
Nucl. Sci. and Eng., Vol: 175, No: 3 , published: 07 November 2013
Reactivity Loss Validation of High-Burnup PWR Fuels with Pile-Oscillation Experiments in MINERVE
P. Leconte, C. Vaglio-Gaudard, R. Eschbach, M. Antony, J. Di-Salvo, A. Pepino
Nucl. Sci. and Eng., Vol: 175, No: 3 , published: 07 November 2013
Monte Carlo studies on the burnup measurement for the high temperature gas cooling reactor
Yan Wei-Hua, Zhang Li-Guo, Zhang Yan, Zhang Zhao, Xiao Zhi-Gang
Chin. Phys. C, Vol: 37, No: 11 , published: 01 November 2013
The criticality of VVER-1000 mock-up with different H3BO3 concentration
Michal Košťál, Vojtěch Rypar, Vlastimil Juříček
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
Neutron and gamma-ray deep penetration calculation through biological concrete shield of VVER-1000 reactor by a new technique based on variance reduction
Alia Alizadeh, Amir Saeid Shirani, Samira Kashi
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
Design of annular fuels for a typical VVER-1000 core: Neutronic investigation, pitch optimization and MDNBR calculation
M. Amin Mozafari, F. Faghihi
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
Design and analysis of an innovative pressure tube light water reactor with variable moderator control
R. Rachamin, E. Fridman, A. Galperin
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
Nuclear reactor core optimization with Parallel Integer Coded Genetic Algorithm
A. Norouzi, M. Aghaie, A.R. Mohamadi Fard, A. Zolfaghari, A. Minuchehr
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
Decay heat removal without forced cooling on a small simplified PBR with an accumulative fuel loading scheme
Dwi Irwanto, Toru Obara
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
Use of sensitivity and uncertainty analysis in reactor design verification. Part I: TSUNAMI analysis
Mohamed Dahmani, Doddy Kastanya
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
Use of sensitivity and uncertainty analysis in reactor design verification Part II: Flux measurement analysis
Doddy Kastanya, Mohamed Dahmani
Ann. Nucl. Energy, Vol: 60 (2013), No: 0 , published: 01 October 2013
Core design options for high conversion BWRs operating in Th–233U fuel cycle
Y. Shaposhnik, E. Shwageraus, E. Elias
Nucl. Eng. Des., Vol: 263, No: 0 , published: 01 October 2013
Расширенное воспроизводство 233U в торий-урановом топливном цикле в реакторах типа ВВЭР с использованием тяжелой воды
В. Е. Маршалкин, В. М. Повышев
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2013, No: 3 , published: 01 October 2013
Прямое численное моделирование турбулентных потоков в тепловыделяющих сборках реактора ВВЭР-440
Ю. В. Юдов
Мат. моделир., Vol: 25, No: 10 , published: 01 October 2013
Reactivity Effects of Spatial Homogenization of Thermal Feedback Regions in Monte Carlo Reactor Calculations
Benjamin R. Hanna, Daniel F. Gill, David P. Griesheimer
Nucl. Technol., Vol: 183, No: 3 , published: 17 September 2013
Verification of a Depletion Method in SCALE for the Advanced High-Temperature Reactor
Ryan Kelly, Dan Ilas
Nucl. Technol., Vol: 183, No: 3 , published: 17 September 2013
WIMS/PANTHER Analysis of UO2/MOX Cores Using Embedded Supercells
Martin Knight, Paul Bryce, Sheldon Hall
Nucl. Technol., Vol: 183, No: 3 , published: 17 September 2013
Pressurized Water Reactor ENDF/B-VII Cross-Section Libraries for ORIGEN-ARP
Carolyn McGraw, Germina Ilas
Nucl. Technol., Vol: 183, No: 3 , published: 17 September 2013
Reactivity Impact of 16O Thermal Elastic-Scattering Nuclear Data for Some Numerical and Critical Benchmark Systems
Ken S. Kozier, Dan Roubtsov, Arjan J. M. Plompen, Stefan Kopecky
Nucl. Technol., Vol: 183, No: 3 , published: 17 September 2013
Development of a Three-Dimensional Pseudo Pin-by-Pin Calculation Methodology in ANC
Baocheng Zhang, Larry Mayhue, Harish Huria, Boyan Ivanov
Nucl. Technol., Vol: 183, No: 3 , published: 17 September 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
Transition to CASMO-5M and SIMULATE-3K for Stability Analyses of the Swiss Boiling Water Reactors
Abdelhamid Dokhane, Stefano Canepa, Hakim Ferroukhi
Nucl. Technol., Vol: 183, No: 3 , published: 12 September 2013
Core design study for power uprating of integral primary system PWR
Syeilendra Pramuditya, Minoru Takahashi
Ann. Nucl. Energy, Vol: 59 (2013), No: 0 , published: 01 September 2013
Neutronic calculations of AFPR-100 reactor based on Spherical Cermet Fuel particles
A. Benchrif, A. Chetaine, H. Amsil
Ann. Nucl. Energy, Vol: 59 (2013), No: 0 , published: 01 September 2013
Automatic multi-cycle reload design of pressurized water reactor using particle swarm optimization algorithm and local search
Chaung Lin, Shao-Chun Hung
Ann. Nucl. Energy, Vol: 59 (2013), No: 0 , published: 01 September 2013
Variable moderation high performance light water reactor (VMHWR)
G. Jahanfarnia, S. Tashakor, A.A. Salehi, A. Abbaspour Tehrani Fard
Ann. Nucl. Energy, Vol: 58, No: , published: 01 August 2013
Calculating the inventory of heavy metals in the fuel assemblies of VVER-1000 during the first cycle
M. Rahgoshay, M. Hashemi-Tilehnoee
Ann. Nucl. Energy, Vol: 58, No: , published: 01 August 2013
A new SCWR fuel assembly with two-row fuel rods between the hexagonal moderator channels
Lianjie Wang, Dong Qin, Qing Li, Bangyang Xia
Ann. Nucl. Energy, Vol: 58, No: , published: 01 August 2013
Computation of ex-core detector weighting functions for VVER-440 using MCNP5
Gabriel Farkas, Jozef Lipka, Ján Haščík, Vladimír Slugeň
Nucl. Eng. Des., Vol: 261, No: 0 , published: 01 August 2013
Coupled code calculation of rod withdrawal at power accident
Davor Grgić, Vesna Benčik, Siniša Šadek
Nucl. Eng. Des., Vol: 261, No: 0 , published: 01 August 2013
Neutronics assessment of thorium-based fuel assembly in SCWR
Shichang Liu, Jiejin Cai
Nucl. Eng. Des., Vol: 260, No: , published: 01 July 2013
Investigation of PWR core optimization using harmony search algorithms
M. Aghaie, T. Nazari, A. Zolfaghari, A. Minuchehr, A. Shirani
Ann. Nucl. Energy, Vol: 57, No: , published: 01 July 2013
In-core fuel management for AHWR
Amit Thakur, Baltej Singh, P.D. Krishnani
Ann. Nucl. Energy, Vol: 57, No: , published: 01 July 2013
Calculation of the fuel composition and the thermo-neutronic parameters of the Bushehr’s VVER-1000 reactor during the initial startup and the first cycle using the WIMSD5-B, CITATION-LDI2 and WERL codes
Yashar Rahmani, Ali Pazirandeh, Mohammad B. Ghofrani, Mostafa Sadighi
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
Evaluation of compressible flow in spherical fueled reactors using the porous media model
A.F. Pilehvar, M. Aghaie, M.H. Esteki, A. Zolfaghari, A. Minuchehr, A. Daryabak, A. Safavi
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
Uncertainty and sensitivity analyses applied to the DRAGONv4.05 code lattice calculations and based on JENDL-4 data
Augusto Hernández-Solís, Christophe Demazière, Christian Ekberg
Ann. Nucl. Energy, Vol: 57, No: , published: 01 July 2013
Development of a model for the approximation of the neutron and photon flux in a BWR spent fuel assembly
Riccardo Rossa, Paolo Peerani
Ann. Nucl. Energy, Vol: 57, No: , published: 01 July 2013
Prediction of Pebble Motion in Pebble-Bed Reactors Using Monte Carlo Molecular Dynamics Simulation
Kyoung O. Lee, Robin P. Gardner
Nucl. Sci. and Eng., Vol: 174, No: 3 , published: 01 July 2013
MOCUM solutions to the 2-D hexagonal HTTR benchmark problems
Xue Yang, Nader Satvat
Ann. Nucl. Energy, Vol: 56, No: , published: 01 June 2013
PWR power distribution flattening using Quantum Particle Swarm intelligence
M. Jamalipour, M. Gharib, R. Sayareh, F. Khoshahval
Ann. Nucl. Energy, Vol: 56, No: , published: 01 June 2013
Physics study of deep-burning of spent fuel transuranics using commercial LWR cores
Ser Gi Hong, Sang Yoon Park, Kyung Hoon Lee, Jin Young Cho, Chang Keun Jo, Won Jae Lee, Francesco Venneri
Nucl. Eng. Des., Vol: 259, No: , published: 01 June 2013
Comparison of thermal scattering processing options for S(α,β) cards in MCNP
Štefan Čerba, Jose Ignacio Marquez Damian, Jakub Lüley, Branislav Vrban, Gabriel Farkas, Vladimír Nečas, Jan Haščík
Ann. Nucl. Energy, Vol: 55, No: , published: 01 May 2013
Neutronic design of a very high temperature reactor core with low graphite content
Dionisio Telésforo-Reyes, Juan-Luis François, Cecilia Martín-del-Campo, Arturo G. Reinking-Cejudo
Ann. Nucl. Energy, Vol: 55, No: , published: 01 May 2013
APOLLO2 and TRIPOLI4 solutions of the OECD VVER-1000 LEU and MOX assembly benchmark
N. Petrov, G. Todorova, N.P. Kolev
Ann. Nucl. Energy, Vol: 55, No: , published: 01 May 2013
TRU management and 235U consumption minimization in fuel cycle scenarios with AP1000 and VHTRs
Marie-Hermine M. Cuvelier, Pavel V. Tsvetkov
Ann. Nucl. Energy, Vol: 55, No: , published: 01 May 2013
Concept of a high temperature integrated multi-modular thermal reactor
Vishal Patel, Pavel Tsvetkov
Ann. Nucl. Energy, Vol: 55, No: , published: 01 May 2013
Continuous firefly algorithm applied to PWR core pattern enhancement
N. Poursalehi, A. Zolfaghari, A. Minuchehr, H.K. Moghaddam
Nucl. Eng. Des., Vol: 258, No: , published: 01 May 2013
Coupled neutronics/thermal-hydraulics for analysis of molten salt reactor
Zhangpeng Guo, Jianjun Zhou, Dalin Zhang, Khurrum Saleem Chaudri, Wenxi Tian, Guanghui Su, Suizheng Qiu
Nucl. Eng. Des., Vol: 258, No: , published: 01 May 2013
The axial power distribution validation of the SCWR fuel assembly with coupled neutronics-thermal hydraulics method
Xi Xi, Zejun Xiao, Xiao Yan, Yongliang Li, Yanping Huang
Nucl. Eng. Des., Vol: 258, No: , published: 01 May 2013
Introduction of Thorium-Based Fuels in High Conversion Pressurized Water Reactors
V. Vallet, B. Gastaldi, J. Politello, A. Santamarina, L. Van Den Durpel
Nucl. Technol., Vol: 182, No: 2 , published: 01 May 2013
Differential harmony search algorithm to optimize PWRs loading pattern
N. Poursalehi, A. Zolfaghari, A. Minuchehr
Nucl. Eng. Des., Vol: 257, No: , published: 01 April 2013
A method for VVER-1000 fuel rearrangement optimization taking into account both fuel cladding durability and burnup
S.N. Pelykh, M.V. Maksimov, G.T. Parks
Nucl. Eng. Des., Vol: 257, No: , published: 01 April 2013
Depletion analysis on long-term operation of the conceptual Molten Salt Actinide Recycler & Transmuter (MOSART) by using a special sequence based on SCALE6/TRITON
R.J. Sheu, C.H. Chang, C.C. Chao, Y.-W.H. Liu
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
Generalized perturbation theory and stochastics algorithms applied to improve CANDU6 reflectors
M. Mahjoub, R. Roy, J. Koclas
Ann. Nucl. Energy, Vol: 53, No: , published: 01 March 2013
Reactor core heterogeneity effects on radionuclide inventory
K. Obaidurrahman, S.K. Gupta
Ann. Nucl. Energy, Vol: 53, No: , published: 01 March 2013
PWR loading pattern optimization using Harmony Search algorithm
N. Poursalehi, A. Zolfaghari, A. Minuchehr
Ann. Nucl. Energy, Vol: 53, No: , published: 01 March 2013
Design of 33 pin annular fuel rod cluster for Advanced Heavy Water Reactor
A.P. Deokule, A.K. Vishnoi, K. Umasankari, D.K. Chandraker, P.K. Vijayan, S. Ganesan
Nucl. Eng. Des., Vol: 256, No: , published: 01 March 2013
Calculation of control rod worth and temperature reactivity coefficient of fuel and coolant with burn-up changes for VVRS-2 MWth nuclear reactor
Mohammad Rahgoshay, Omid Noori-Kalkhoran
Nucl. Eng. Des., Vol: 256, No: , published: 01 March 2013
Preliminary reactor physics assessment of the HTR module with 14% enriched UCO fuel
Gerhard Strydom, Hans D. Gougar
Nucl. Eng. Des., Vol: 256, No: , published: 01 March 2013
A multi-scale homogenization and reconstruction approach for solid material temperature calculations in prismatic high temperature reactor cores
Ivor Clifford, Kostadin N. Ivanov, Maria N. Avramova
Nucl. Eng. Des., Vol: 256, No: , published: 01 March 2013
A code development for LLFP transmutation analysis based on the whole pin-wise calculation in PWRs
Kun Liu, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Changhui Wang
Nucl. Eng. Des., Vol: 256, No: , published: 01 March 2013
Automatic boiling water reactor control rod pattern design using particle swarm optimization algorithm and local search
Cheng-Der Wang, Chaung Lin
Nucl. Eng. Des., Vol: 255, No: , published: 01 February 2013
Assessment of possible cycle lengths for fully encapsulated microstructure fueled light water reactor concepts
R. Sonat Sen, Michael A. Pope, Abderrafi M. Ougouag, Kemal O. Pasamehmetoglu
Nucl. Eng. Des., Vol: 255, No: , published: 01 February 2013
Результаты расчёта нейтронно-физических характеристик 3D модели реактора ГТ-МГР по коду MCU-HTR
Осипов С.Л., Сорокин С.Е., Сухарев Ю.П., Глушков Е.С., Гуревич М.И., Фомиченко П.А.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2013, No: 2 , published: 01 February 2013
О возможности использования оксидного уран-бериллиевого топлива в ВВЭР
Ковалишин А.А., Просёлков В.Н., Сидоренко В.Д., Стогов Ю.В.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2013, No: 2 , published: 01 February 2013
Область маневрирования ВВЭР-1000 при работе в суточном графике нагрузки
Дубов А.А.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2013, No: 2 , published: 01 February 2013
MCNPX and HELIOS-2 comparison for the neutronics calculations of a Supercritical Water Reactor HPLWR
Alejandra-Maribel Barragán-Martínez, Cecilia Martin-del-Campo, Juan-Luis François, Gilberto Espinosa-Paredes
Ann. Nucl. Energy, Vol: 51, No: , published: 01 January 2013
Sensitivity and Uncertainty of OECD Benchmark Ringhals-1 TRACE/PARCS Stability Prediction
Ivan Gajev, Tomasz Kozlowski, Yunlin Xu, Thomas Downar
Nucl. Technol., Vol: 180, No: 3 , published: 01 December 2012
Construction and Analysis of a Dynamic Model for a Canadian Direct-Cycle SCWR for Control System Studies
Peiwei Sun, Jin Jiang
Nucl. Technol., Vol: 180, No: 3 , published: 01 December 2012
Qualification of the Taiwan Power Company's pressurized water reactor physics methods using CASMO-4/SIMULATE-3
Hsien-Chuan Lin, Shung-Jung Yaur, Tzung-Yi Lin, Weng-Sheng Kuo, Jin-Yih Shiue, Yu-Lung Huang
Nucl. Eng. Des., Vol: 253, No: , published: 01 December 2012
Neutronic characteristics of an OTTO refueling PBMR
Hoai Nam Tran, Van Khanh Hoang
Nucl. Eng. Des., Vol: 253, No: , published: 01 December 2012
Neutronic analysis of HPLWR fuel assembly cluster
S. Tashakor, A.A. Salehi, G. Jahanfarnia, A. Abbaspour Tehrani Fard
Ann. Nucl. Energy, Vol: 50, No: , published: 01 December 2012
Developing a computational tool for predicting physical parameters of a typical VVER-1000 core based on artificial neural network
S.M. Mirvakili, F. Faghihi, H. Khalafi
Ann. Nucl. Energy, Vol: 50, No: , published: 01 December 2012
The optimum design of power distribution for pressurized water reactor
Chunhui Dai, Xinyu Wei, Yun Tai, Fuyu Zhao
Ann. Nucl. Energy, Vol: 50, No: , published: 01 December 2012
Bayesian inference along Markov Chain Monte Carlo approach for PWR core loading pattern optimization
A. Haghighattalab, A. Minuchehr, A. Zolfaghari, F. Khoshahval
Ann. Nucl. Energy, Vol: 50, No: , published: 01 December 2012
A new random distribution method to simulate PBM type reactors with MCNP
S.A. Hosseini
Ann. Nucl. Energy, Vol: 50, No: , published: 01 December 2012
Effect of thermal parameters on performance of modular helium reactors
H.M. Şahin, Ӧ. Akbayir, C. Kocar
Int. J. Energy Res., Vol: 36, No: 15 , published: 01 December 2012
MOX fuel effects on the isotope inventory in LWRs
S. Fehér, T. Reiss, A. Wirth
Nucl. Eng. Des., Vol: 252, No: , published: 01 November 2012
Neutronic analysis of the burning of transuranics in fully ceramic micro-encapsulated tri-isotropic particle-fuel in a PWR
Michael A. Pope, R. Sonat Sen, Abderrafi M. Ougouag, Gilles Youinou, Brian Boer
Nucl. Eng. Des., Vol: 252, No: , published: 01 November 2012
Fluctuations of Mass Yield Distribution for the Epithermal Fission of 235U and Its Impact on HCLWR Calculations
P. Leconte, J.-P. Hudelot, M. Antony
Nucl. Sci. and Eng., Vol: 172, No: 2 , published: 01 October 2012
Corrigendum to “Effect of mesh grid size on the accuracy of deterministic VVER-1000 core calculations” [Annals of Nuclear Energy 38 (5) (2011) 1214–1218]

Ann. Nucl. Energy, Vol: 48, No: , published: 01 October 2012
Development of Erbia-Credit Super-High-Burnup Fuel: Evaluation of Minimum Erbia Content for Criticality Safety Analyses
Masatoshi Yamasaki, Hironobu Unesaki, Akio Yamamoto, Toshikazu Takeda, Masaaki Mori
Nucl. Technol., Vol: 180, No: 1 , published: 01 October 2012
Automatic fuel lattice design in a boiling water reactor using a particle swarm optimization algorithm and local search
Chaung Lin, Tung-Hsien Lin
Ann. Nucl. Energy, Vol: 47, No: , published: 01 September 2012
A 13 × 13 annular fuel assembly 1000 MWe PWR response to a reactivity excursion
M. Saidinezhad, S.D. Hamieh
Ann. Nucl. Energy, Vol: 47, No: , published: 01 September 2012
The performance of closed reactor grade plutonium–thorium fuel cycles in reduced-moderation pressurised water reactors
Benjamin A. Lindley, Geoffrey T. Parks
Ann. Nucl. Energy, Vol: 47, No: , published: 01 September 2012
Propagation of 235,236,238U and 239Pu Nuclear Data Uncertainties for a Typical PWR Fuel Element
D. Rochman, A. J. Koning, D. F. Da Cruz
Nucl. Technol., Vol: 179, No: 3 , published: 01 September 2012
Fission Neutron Spectrum Sensitivity Study for the Case of Advanced Heavy Water Reactor
Anek Kumar, S. Ganesan
Nucl. Sci. and Eng., Vol: 172, No: 1 , published: 01 September 2012
Neutronic characteristics of linear-assembly breed-and-burn reactors
Robert Petroski, Benoit Forget, Charles Forsberg
Nucl. Eng. Des., Vol: 250, No: , published: 01 September 2012
ABWR power tests simulation by using a dual RELAP5 nuclear power plant simulation platform
Chung-Yu Yang, L.C. Dai, Thomas K.S. Liang, B.S. Pei, C.K. Shih, L.C. Wang, S.C. Chiang
Nucl. Eng. Des., Vol: 249, No: , published: 23 August 2012
Effect of pebble packing on neutron spectrum and the isotopic composition of HTGR fuel
Mehmet Türkmen, Üner Çolak
Ann. Nucl. Energy, Vol: 46, No: , published: 04 August 2012
Shifting study of a VHTR using reprocessed fuel with various TRISO packing fractions
F.C. Silva, C. Pereira, M.A.F. Veloso, A.L. Costa
Nucl. Eng. Des., Vol: 248, No: , published: 23 July 2012
A methodology to a DB-MHR fuel recharge evaluation—A basic comparison between WIMSD-5B and MCNPX codes
Clarysson Alberto M. da Silva, Claubia Pereira, M.A.F. Veloso, Antonella Lombardi Costa
Nucl. Eng. Des., Vol: 248, No: , published: 23 July 2012
A PN-based approach along PSO scheme for PWR core reloading patterns optimization
M. Abbassi, A. Zolfaghari, A. Minuchehr, F. Khoshahval
Nucl. Eng. Des., Vol: 248, No: , published: 23 July 2012
Burning minor actinides in a HTR energy spectrum
Christoph Pohl, H. Jochem Rütten
Nucl. Eng. Des., Vol: 248, No: , published: 23 July 2012
Benchmarking the new JENDL-4.0 library on criticality experiments of a research reactor with oxide LEU (20 w/o) fuel, light water moderator and beryllium reflectors
Peng Hong Liem, Tagor Malem Sembiring
Ann. Nucl. Energy, Vol: 44, No: , published: 04 June 2012
Fuel burnup calculation for HEU and LEU cores of Ghana MNSR
E.K. Boafo, E.H.K. Akaho, B.J.B. Nyarko, S.A. Birikorang, G.K. Quashigah
Ann. Nucl. Energy, Vol: 44, No: , published: 04 June 2012
Monte Carlo simulation of additional safety control rod for commercial MNSR to enhance safety
Y.V. Ibrahim, H.C. Odoi, R.L. Njinga, M.O. Adeleye, S.A. Jonah
Ann. Nucl. Energy, Vol: 44, No: , published: 04 June 2012
DRAGON and CORD-2 nuclear calculation of the NPP Krško fuel assembly
Marjan Kromar, Bojan Kurinčič
Nucl. Eng. Des., Vol: 246, No: , published: 23 May 2012
MOx benchmark calculations by deterministic and Monte Carlo codes
M. Pecchia, G. Kotev, C. Parisi, F. D’Auria
Nucl. Eng. Des., Vol: 246, No: , published: 23 May 2012
Effect of systematic error in the fuel mass on keff in pebble bed reactors
Vladimir Radulovič, Igor Lengar, Andrej Trkov
Nucl. Eng. Des., Vol: 246, No: , published: 23 May 2012
Uncertainty and sensitivity analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic–neutronic simulations
F. Ánchel, T. Barrachina, R. Miró, G. Verdú, J. Juanas, R. Macián-Juan
Nucl. Eng. Des., Vol: 246, No: , published: 23 May 2012
Computational validation of a supercritical-water reactor in a thorium-uranium fuel cycle
V. M. Dekusar, A. G. Kalashnikov, E. N. Kapranova, M. S. Kolesnikova, V. E. Korobytsin
Атом. энергия, Vol: 112, No: 5 , published: 05 May 2012
Three-dimensional effects in RBMK fuel temperature calculations
V. N. Babaytsev, G. B. Davydova, L. N. Zakharova, A. V. Krayushkin
Атом. энергия, Vol: 112, No: 5 , published: 05 May 2012
The effects of core zoning on the graphite lifespan and breeding gain of a moderated molten salt reactor
K. Nagy, J.L. Kloosterman, D. Lathouwers, T.H.J.J. van der Hagen
Ann. Nucl. Energy, Vol: 43, No: , published: 04 May 2012
Methodology for estimation of conditional probability of stagnation channel break for PHWRs
Santosh K. Pradhan, Prajjwal Prem, S.K. Gupta
Ann. Nucl. Energy, Vol: 43, No: , published: 04 May 2012
A coupled neutronics/thermal–hydraulics tool for calculating fluctuations in Pressurized Water Reactors
Viktor Larsson, Christophe Demazière
Ann. Nucl. Energy, Vol: 43, No: , published: 04 May 2012
Automatic pressurized water reactor loading pattern design using ant colony algorithms
Chaung Lin, Bo-Feng Lin
Ann. Nucl. Energy, Vol: 43, No: , published: 04 May 2012
Optimizing the fuel management in a VVER-1000 reactor using an artificial neural network
Ali Pazirandeh, Shima Tayefi
Ann. Nucl. Energy, Vol: 42, No: , published: 04 April 2012
An efficient hybrid stochastic/deterministic coarse mesh neutron transport method
Dingkang Zhang, Farzad Rahnema
Ann. Nucl. Energy, Vol: 41, No: , published: 04 March 2012
Kinetic parameters evaluation of PWRs using static cell and core calculation codes
Ali Jahanbin, Hessam Malmir
Ann. Nucl. Energy, Vol: 41, No: , published: 04 March 2012
Performance evaluation of a 3-D kinetic model for CANDU reactors in a closed-loop environment
Lingzhi Xia, Jin Jiang, Hooman Javidnia, John C. Luxat
Nucl. Eng. Des., Vol: 243, No: , published: 22 February 2012
Performance of high-temperature gas-cooled reactor as a tritium production device for fusion reactors
H. Matsuura, S. Kouchi, H. Nakaya, T. Yasumoto, Y. Nakao, S. Shimakawa, M. Goto, S. Nakagawa, M. Nishikawa
Nucl. Eng. Des., Vol: 243, No: , published: 22 February 2012
The design of a compact integral medium size PWR
Koroush Shirvan, Pavel Hejzlar, Mujid S. Kazimi
Nucl. Eng. Des., Vol: 243, No: , published: 22 February 2012
New Strategy on the Evaluation of Dancoff Factor in a Pebble Bed Reactor Using Monte Carlo Method
Song Hyun Kim, Hong-Chul Kim, Jong Kyung Kim, Jea Man Noh
Nucl. Technol., Vol: 177, No: 2 , published: 04 February 2012
Combined Micro and Macro Parameter Perturbation Theory and Application for BWR Lattice Design and Optimization
Albert G. Gu
Nucl. Technol., Vol: 177, No: 2 , published: 04 February 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
Near-complete transuranic waste incineration in a thorium fuelled pressurised water reactor
Benjamin A. Lindley, Geoffrey T. Parks
Ann. Nucl. Energy, Vol: 40, No: , published: 04 February 2012
Comparative analysis of high conversion achievable in thorium-fueled slightly modified CANDU and PWR reactors
A. Nuttin, P. Guillemin, A. Bidaud, N. Capellan, R. Chambon, S. David, O. Méplan, J.N. Wilson
Ann. Nucl. Energy, Vol: 40, No: , published: 04 February 2012
Fuel assembly with inert matrix fuel rods as reload options for Laguna Verde NPP
Hector Hernandez Lopez
Ann. Nucl. Energy, Vol: 40, No: , published: 04 February 2012
Studies of 2D reflector effects in cross section preparation for deep burn VHTRs
Vincent Descotes, Michael A. Pope, Javier Ortensi, Alain Hébert
Nucl. Eng. Des., Vol: 242, No: , published: 22 January 2012
TRU self-recycling in a high temperature modular helium reactor
Chang Keun Jo, Yonghee Kim, Jae Man Noh, Francesco Venneri
Nucl. Eng. Des., Vol: 242, No: , published: 22 January 2012
Homogenization of Cross Sections and Computation of Discontinuity Factors for a Real 3-D BWR Bottom Reflector for Comparison with Lattice and Nodal Codes
John Loberg, Michael ÖSterlund, Klaes-Håkan Bejmer, Jan Blomgren, Jesper Kierkegaard
Nucl. Technol., Vol: 177, No: 1 , published: 04 January 2012
Boiling Water Reactor Stability Analysis by TRACE/PARCS: Modeling Effects and Case Study of Time Versus Frequency Domain Approach
Rui Hu, Mujid S. Kazimi
Nucl. Technol., Vol: 177, No: 1 , published: 04 January 2012
Analysis of MERCI Decay Heat Measurement for PWR UO2 Fuel Rod
J. C. Jaboulay, S. Bourganel
Nucl. Technol., Vol: 177, No: 1 , published: 04 January 2012
Proliferation-Resistant Fuel for CANDU Reactors
Yigal Ronen, M. Aboudy, D. Regev
Nucl. Sci. and Eng., Vol: 170, No: 1 , published: 04 January 2012
Повышение глубины выгорания и защищенности топлива легководных реакторов при совместном введении в его состав 231Pa и 237Np
Г.Г. Куликов, Е.Г. Куликов, Э.Ф. Крючков, А.Н. Шмелев
Изв. вузов. Ядер. энерг., Vol: 2011, No: 4 , published: 30 November 2011
Введение регенерированного урана в состав топлива легководных реакторов как способ защиты от распространения
А.Ю. Смирнов, В.А. Апсэ, В.Д. Борисевич, В.Б. Глебов, Г.А. Сулаберидзе, А.Н. Шмелев, А.А. Дудников, Е.А. Иванов, В.А. Невиница, Н.Н. Пономарев-Степной
Изв. вузов. Ядер. энерг., Vol: 2011, No: 4 , published: 30 November 2011
Применение наножидкостей в качестве теплоносителя первого контура реактора ВВЭР-1000
К. Хадад, А. Хаджизаде, К. Джафарпур, В.Д. Ганапол
Атом. техн. за рубежом, Vol: 2011, No: 11 , published: 11 November 2011
Neutronic performance of CANDU reactor fuelling with ThC2/ 233UC2
Kadir Yıldız, Necmettin Şahi̇n, Mahmut Alkan
Int. J. Energy Res., Vol: 35, No: 2 , published: 28 February 2011
Расчет нейтронно-физических характеристик активной зоны ВВЭР-1000 методом Монте-Карло по программе MCU-PD, сравнение с результатами расчетов по программе БИПР-7А и экспериментальными данными
Дементьев В.Г./Олейник Д.С.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2010, No: 1 , published: 24 September 2010
Исследование некоторых моделей и приближений, применяемых при расчете ТВС высокотемпературного газоохлаждаемого реактора ГТ-МГР
Бояринов В.Ф./Фомиченко П.А.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2010, No: 1 , published: 24 September 2010
Топливо повышенного обогащения в ВВЭР
Цибульский В.Ф./Давиденко В.Д./Лобынцев В.А./и др.
Атом. энергия, Vol: 108, No: 3 , published: 02 September 2010
Топливные циклы ВВЭК-440 с инертными матрицами для сжигания плутония
Шебиан В./Нехаш В./Дарилек П.
Атом. энергия, Vol: 108, No: 1 , published: 09 June 2010
Модель активной зоны РБМК для расчетного сопровождения производства {60}Co на Ленинградской АЭС
Артемов В.Г./Ельшин А.В./Иванов А.С./и др.
Атом. энергия, Vol: 108, No: 1 , published: 09 June 2010
Оптимизация распределения энерговыделения в активной зоне РБМК в процессе эксплуатации
Постников В.В./Краюшкин А.В.
Атом. энергия, Vol: 106, No: 2 , published: 01 December 2009
Возможность использования регенерированного урана в топливном цикле реакторе LWR для производства "защищенного" плутония
Фукуда Косаки/Сагара Хироси/Сайто Масаки/Мицухаси Цунэтомо
Атом. техн. за рубежом, Vol: 2009, No: 11 , published: 16 August 2009
Оптимизация однократного выжигания трансуранов в модульном реакторе с гелиевым теплоносителем
Ким Я./Веннери Ф.
Атом. техн. за рубежом, Vol: 2009, No: 9 , published: 07 May 2009
Утилизация Np, Am, Cm в энергетическом ядерном реакторе
Бергельсон Б.Р./Белоног В.В./Герасимов А.С./Тихомиров Г.В.
Атом. энергия, Vol: 107, No: 2 , published: 07 April 2009
Реактивностные эффекты в реакторе ВВЭР-1000 3-го блока Калининской АЭС на этапе физического пуска. Расчеты в интеллектуальной программной среде ShIPR с библиотекой двугрупповых сечений, полученных по программе UNK
Зизин М.Н./Зимин В.Г./Зизина С.Н./и др.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2009, No: 3 , published: 25 January 2009
Верификация комплекса программ SUHAM-2D на расчетах выгорания топлива в ТВС ВВЭР-1000 с урановым и MOX топливом
Бояринов В.Ф./Давиденко В.Д./Полисмаков А.А./Цибульский В.Ф.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2009, No: 3 , published: 25 January 2009
Некоторые нейтронно-физические и теплогидравлические характеристики усовершенствованной конструкции реактора "МАСТЕР"
Казанский Ю.А./Левченко В.А./Юрьев Ю.С./и др.
Изв. вузов. Ядер. энерг., Vol: 2008, No: 1 , published: 03 December 2008
Легководный реактор со сверхкиритическими параметрами теплоносителя и (Th-U)O[2] топливом: уменьшение температурного эффекта реактивности по теплоносителю
Куликов Е.Г./Шмелев А.Н./Куликов Г.Г.
Изв. вузов. Ядер. энерг., Vol: 2008, No: 1 , published: 03 December 2008
Нейтронная активность облученного МОХ-топлива при различных глубинах выгорания
Шаманин И.В./Гаврилов П.М./Беденко С.В./Мартынов В.В.
Изв. вузов. Ядер. энерг., Vol: 2008, No: 1 , published: 03 December 2008
Нейтронная активность отработавшего ядерного топлива при повышенных глубинах выгорания
Шаманин И.В./Гаврилов П.М./Беденко С.В./Мартынов В.В.
Изв. вузов. Ядер. энерг., Vol: 2008, No: 1 , published: 03 December 2008
Плотностной эффект реактивности энергетического тяжеловодного реактора, работающего в режиме самообеспечения {233}U
Бергельсон Б.Р./Герасимов А.С./Тихомиров Г.В.
Атом. энергия, Vol: 105, No: 5 , published: 26 November 2008
Моделирование ядерно-физических процессов в поверхностном слое топливного сердечника с выгорающим поглотителем
Баранов В.Г./Терновых М.Ю./Тихомиров Г.В./Хлунов А.В.
Атом. энергия, Vol: 105, No: 6 , published: 26 November 2008
Моделирование ядерно-физических процессов в поверхностном слое топливного сердечника
Андрианов А.Н./Баранов В.Г./Тихомиров Г.В./Хлунов А.В.
Атом. энергия, Vol: 104, No: 6 , published: 26 November 2008
RBMK-1500 reaktoriaus atsargos koeficiento iki ribinio leistino kuro kanalo galingumo skai~3ciavimo algoritmo patobulinimas
Matuzas Vaidas/Kopustinskas Vytis/Augutis Juozas
Energetika, Vol: 54, No: 4 , published: 02 November 2008
Reaktoriaus RBMK-1500 konstrukcini~8u element~8u neutronin~.es aktyvacijos skaitinis vertinimas. 2. Altramini~8u ir apsaugini~8u plieno plok~3s~3ci~8u neturonin~.es aktyovacijos skaitinis vetinimas
Nark~-unas Ernestas/~3Smai~3zys Art~-uras/Po~3skas Povilas
Energetika, Vol: 54, No: 2 , published: 12 October 2008
Влияние неопределенности микроконстант на сжигание трансплутониевых актиноидов в жидкосолевых реакторах
Мясников А.А.
Атом. энергия, Vol: 102, No: 5 , published: 11 April 2008
Оптимальное использование топлива при выводе АЭС с РБМК из эксплуатации
Федосов А.М.
Атом. энергия, Vol: 102, No: 5 , published: 11 April 2008
Нейтронно-физические характеристики активной зоны ВВЭР-1000 со 100%-ной загрузкой топливом из регенированного урана и плутония
Павловичев А.М.\Павлов В.И.\Семченков Ю.М.\и др.
Атом. энергия, Vol: 101, No: 6 , published: 31 March 2008
Сопоставление результатов расчета и послереакторных исследований твэлов ВВЭР-1000 выгоранием 49 МВт~xсут/кг
Пассаж Г.\Стефанова С.\Щеглов А.С.\Проселков В.Н.
Атом. энергия, Vol: 101, No: 6 , published: 31 March 2008
Расчетно-экспериментальные исследования нейтронно-физических характеристик активной зоны ГТ-МГР
Кодочигов Н.Г.\Сухарев Ю.П.\Марова Е.В.\и др.
Атом. энергия, Vol: 102, No: 1 , published: 23 December 2007
Возможности эксплуатации ГТ-МГР с разным топливом
Кодочигов Н.Г.\Сухарев Ю.П.\Марова Е.В.\Усынина С.Г.
Атом. энергия, Vol: 102, No: 1 , published: 23 December 2007
Замечания к статье Страхова Э.Б., Воробьева В.Н. и Смирнова О.А "Расчетная оценка накопления трития в тяжеловодных реакторах"
Ерыкалов А.Н.
Атом. энергия, Vol: 102, No: 3 , published: 22 December 2007
Effect of nonuniform 3-D void distribution within BWR fuel assemblies on neutronic characteristics
Takeda T.\Hyoudou H.\Kitada T.\et al.
Transp. Theory and Statist. Phys., Vol: 33, No: 3-4 , published: 21 September 2007
Нейтронно-физические и теплотехнические аспекты уран-графитовых реакторов, загруженных твэлами на основе обогащенного урана
Артельный Ю.А.\Гаврилов П.М.\Цыганов А.А.
Атом. энергия, Vol: 101, No: 2 , published: 05 September 2007
Статистическая погрешность расчета нуклидного состава топлива при малой глубине выгорания
Дегтярев А.М.\Мясников А.А.
Атом. энергия, Vol: 98, No: 2 , published: 03 September 2007
Анализ неопределенности расчетов аварий с потерей теплоносителя для 1-го энергоблока Курской АЭС
Афремов Д.А.\Журавлева Ю.В.\Миронов Ю.В.\и др.
Атом. энергия, Vol: 98, No: 6 , published: 12 August 2007
Расчет глубокого выгорания ядерного топлива в решетках с регулируемым спектром нейтронов
Савандер В.И.\Увакин М.А.
Атом. энергия, Vol: 98, No: 6 , published: 12 August 2007
Расчетная оценка накопления трития в тяжеловодных реакторах
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Атом. энергия, Vol: 100, No: 5 , published: 31 July 2007
Les effets physiques sur le coeur mis en jeu lors des variations de puissance
Paulin Ph.\Golfier H.
Rev. gen. nucl., Vol: 2007, No: 3 , published: 01 May 2007
Использование модели малой размерности для восстановления поля энерговыделения в активной зоне по показаниям боковых ионизационных камер
Семенов А.А./Рябов Н.О./Щукин Н.В./Харитонов В.С.
Изв. вузов. Ядер. энерг., Vol: 2007, No: 4 , published: 15 April 2007
Усовершенствование активных зон реакторов РБМК-1500 Игналинской АЭС. Внедрение уран-эрбиевого топлива
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Energetika, Vol: 2007, No: 1 , published: 01 January 2007
Criticality calculation of full-scale RBMK cores using MCU-REA/1 code
Gomin E.A.\Gorodkov S.S.\Gurevich M.I.\et al.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2006, No: 1 , published: 01 January 2006
"Benchmark" neutronic computational investigations of the GT-MHR type reactor
Boyarinov V.F.\Bryzgalov V.I.\Glushkov E.S.\et al.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2006, No: 1 , published: 01 January 2006
Составляющие пространственно-распределенного источника тепловыделения в графитовых конструкциях ЯЭУ
Бойко В.И.\Гаврилов П.М.\Лызко В.А.\и др.
Изв. вузов. Ядер. энерг., Vol: 2005, No: 4 , published: 01 January 2005
Определение экономически оптимального нуклидного состава стали 08Х18Н10Т в активной зоне ректора РБМК-1000
Михеев И.В.\Алхутов М.С.
Теплоэнергетика (Москва), Vol: 2005, No: 1 , published: 01 January 2005
Зависимость эффективности стержней СУЗ РБМК при пуске от их координат и распределения нейтронного потока в активной зоне
Чичулин Н.Л.\Ионов А.И.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 2004, No: 3 , published: 01 January 2004
Топливные циклы с глубоким выгоранием: анализ коэффициента реактивности
Крючков Э.Ф.\Терновых М.Ю.\Тихомиров Г.В.\и др.
Изв. вузов. Ядер. энерг., Vol: 2004, No: 3 , published: 01 January 2004
Calculation of the moderator temperature coefficient of reactivity for water moderated reactors
Mourtzanos K., Housiadas C., Antonopoulos-Domis M.
Ann. Nucl. Energy, Vol: 28, No: 17 , published: 15 November 2001
Validation of a methodology for fuel management analysis of Lfguna Verde nuclear power plant
Francois J.L., Esquivel J.L., Cortes C. et al.
Ann. Nucl. Energy, Vol: 28, No: 5 , published: 15 March 2001
Safety evaluation of the inherent and passive safety features of the smart design
Bae K.H., Kim H.C., Chang M.H., Sim S.K.
Ann. Nucl. Energy, Vol: 28, No: 4 , published: 01 March 2001
Effect of core calcualtion models on optimum cycle length analyses of pressurized water reactors
Yamamoto A., Kimoto T.
Ann. Nucl. Energy, Vol: 27, No: 11 , published: 15 July 2000
A reactivity hold-down ttrategy for soluble boron free operation by introducing Pu-238 added fuel
Kim S.Y., Kim J.K.
Ann. Nucl. Energy, Vol: 27, No: 10 , published: 01 July 2000
ThO2–UO2 annular pins for high burnup fuels
Caner M., Dugan E.T.
Ann. Nucl. Energy, Vol: 27, No: 9 , published: 01 June 2000
Graphite-filled mixed-oxide fuel design for fully loaded PWR cores
Jo C.K., Cho N.Z., Kim Y.H.
Ann. Nucl. Energy, Vol: 27, No: 9 , published: 01 June 2000
The AMEBA PWR, a new concept in the technology of nuclear reactor safety
Novelli A.
Ann. Nucl. Energy, Vol: 27, No: 7 , published: 01 May 2000
Application of modified explicit higher order perturbation (MHP) method to PWER core analysis
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Ann. Nucl. Energy, Vol: 27, No: 4 , published: 01 March 2000
The effect of random goemetry on the criticality of a multiplying system
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Ann. Nucl. Energy, Vol: 27, No: 2 , published: 15 January 2000
Efficient code system of core characteristics for smalo cylindrical thermal reactor
Aboanber A.E., Hirakawa N., Shaker M.O.
Ann. Nucl. Energy, Vol: 26, No: 6 , 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
Optimierung des Brennstoffkreislaufes fur Druckwasserreaktoren
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Сравнение некоторых параметров условий облучения образцов-свидетелей и корпуса ВВЭР-1000
Буканов В.Н., Васильева Е.Г., Гриценко А.В., Демехин В.Л.
Атом. энергия, Vol: 87, No: 4 , 1999
Neutronic and burnup characteristics of an actinide-reduced plutonium fuel with tungsten
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Nucl. Technol., Vol: 122, No: 1 , published: 01 January 1998
Ковариации в нейтронных спектрах и их влияние на результаты корректировки нейтронного потока на корпус реактора
Бемер Б., Мантуров Г.Н.
Вопp. атом. науки и техн. Сер. Ядеp. константы., Vol: 1998, No: 1 , published: 01 January 1998
Физические особенности использования оружейного и реакторного плутония в легководных реакторах со сверхдлинными кампаниями (топливо: Pu+{232}Th+{231}Pa)
Апсэ В.А., Крючков Э.Ф., Куликов Г.Г. и др.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 1998, No: 3 , published: 01 January 1998
Расчетно-теоретическое обоснование возможности глубокого выжигания плутония оружейного и реакторного качества в ВТГР
Савандер В.И., Цветков П.В.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 1998, No: 3 , published: 01 January 1998
Концептуальные исследования по проблеме утилизации оружейных делящихся материалов в реакторах водно-водяного типа на базе традиционной и микротвэльной топливной технологии
Белоусов Н.И., Наумов В.И., Савандер В.И.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 1998, No: 3 , published: 01 January 1998
Утилизация оруженых материалов в реакторах ВВЭР-1000 с топливом на основе тория
Декусар В.М., Долгов Е.В., Илюнин В.Г. и др.
Вопр. атом. науки и техн. Сер. Физ. ядер. реакторов, Vol: 1998, No: 3 , published: 01 January 1998
A new uncertainty arising in reactor pressure vessel fluence calculation
Kim J.O., Kim J.K.
Ann. Nucl. Energy, Vol: 25, No: 12 , 1998
A study on the criticality search of transuranium recycling BWR core by adjusting supplied fuel composition in equilibrium state
Seino T., Sekimoto H.
Ann. Nucl. Energy, Vol: 25, No: 4-5 , 1998
Quick and reliable estimation of power distribution in a PHWR by ANN
Dubey B.P., Jagannathan V., Kataria S.K.
Ann. Nucl. Energy, Vol: 25, No: 8 , 1998
MOX fuel core physics experiments and analysis. Aiming for plutonium effective use
Kanda K., Yamamoto T., Matuura H. et al.
Nihon genshiryoku gakkaishi, Vol: 40, No: 11 , 1998
A high-conversion water reactor design
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Nucl. Sci. and Eng., Vol: 130, No: 2 , 1998
Improved axial flux shape generator for a quick departure from nucleate boiling test
Karve A.A., Han Ch., Rizwan-Uddin
Nucl. Technol., Vol: 123, No: 2 , 1998
Conceptual design of a 50-mw severe-accident-free HTR and the related test program of the HTTR
Kunitomi K., Tachibana Y., Saikusa A. et al.
Nucl. Technol., Vol: 123, No: 3 , 1998
The nonproliferative light water thorium reactor: A new approach to light water reactor core technology
Radkowsky Alvin, Galperin Alex
Nucl. Technol., Vol: 124, No: 3 , 1998
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Пономарев-Степной Н.Н., Лунин Г.Л., Морозов А.Г., Кузнецов В.В., Кевролев В.В., Кузнецов В.Ф.
Атом. энергия, Vol: 85, No: 4 , 1998
Monitoring of the temperature reactivity coefficient at the PWR nuclear power plant
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Ann. Nucl. Energy, Vol: 24, No: 1 , published: 01 January 1997
A study on the optimization of integral fuel burnable absorbers using deterministic methods
Haibach B.V., Feltus M.A.
Ann. Nucl. Energy, Vol: 24, No: 11 , 1997
A modal-based reduced-order model of BWR out-of-phase instabilities
Turso J.A., March-Leuba J., Edwards R.M.
Ann. Nucl. Energy, Vol: 24, No: 12 , 1997
Complex Lyapunov exponents from short and noisy sets of data. Application to stability analysis of BWRs
Verdu G., Ginestar D., Bovea M.D., Jimenez P., Pena J., Munoz-Cobo J.L.
Ann. Nucl. Energy, Vol: 24, No: 12 , 1997
Development of CANDU reactor physics calculation system based on WIMS code
Patrulescu I., Constantin M., Rades E., Balaceanu V.
Ann. Nucl. Energy, Vol: 24, No: 14 , 1997
On the validation of release 3 of ENDF/B-VI nuclear data for light water reactor criticality analysis
Rahnema G., McKinley S.
Ann. Nucl. Energy, Vol: 24, No: 14 , 1997
Core and plant design of the power reactor cooled and moderated by supercritical light water with single tube water rods
Dobashi K., Oka Y., Koshizuka S.
Ann. Nucl. Energy, Vol: 24, No: 16 , 1997
The Monte-Carlo method application in computation studies of fuel compositions with the HTGR coated particles of water-cooled reactors
Goltsev A.O., Gurevich M.I., Davidenko V.D., Malkova L.K., Marin S.V., Martynov D.N.
Ann. Nucl. Energy, Vol: 24, No: 16 , 1997
Neutronic model for modal multichannel analysis of out-of-phase instability in boiling water reactor cores
Hashimoto K., Hotta A., Takeda T.
Ann. Nucl. Energy, Vol: 24, No: 2 , 1997
New approach to the decay ratio estimation in B.W.R.N.P.P.: Frequency-moments technique
Sanchis R., Tkachenko I., Verdu G., Munoz-Cobo J.L., Bovea M.D., Ginestar D.
Ann. Nucl. Energy, Vol: 24, No: 2 , 1997
Validation of ENDF/B-VI.2, JEF-2,2 and JENDL-3.2 through MCNP analysis of BWR-simulated critical experiments
Kim J.-D., Hil C.-S.
Ann. Nucl. Energy, Vol: 24, No: 3 , 1997
Evaluation of the moderator temperature coefficient of rectivity in a PWR by means of noise analysis
Laggiard E., Runkel J.
Ann. Nucl. Energy, Vol: 24, No: 5 , 1997
Study on neutron spectrum for effective transmutation of minor actinides in thermal reactors
Takeda T., Yokoyama K.
Ann. Nucl. Energy, Vol: 24, No: 9 , 1997
Investigation of thermal margin in an advanced PWR core loaded with hexagonal fuel assembly
Hwang D.-H., Yoo Y.-J., Kim Y.-J., Joo H.-K.
Ann. Nucl. Energy, Vol: 24, No: 9 , 1997
Design procedures for small pebble-bed high temperature reactors
Liem P.H.
Ann. Nucl. Energy, Vol: 23, No: 3 , published: 01 March 1996
Velocity profile effects on neutron cross-spectra in BWRs
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Ann. Nucl. Energy, Vol: 23, No: 3 , published: 01 March 1996
A phenomenological model for the interpretation of velocities measured in BWR[S] by cross-correlation techniques
Analytis G.Th.
Ann. Nucl. Energy, Vol: 23, No: 1 , published: 01 January 1996
Prediction of transient behaviour of heavy water and helium gas in reactivity mechanism thimbles during and in-core break in CANDU reactor
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Ann. Nucl. Energy, Vol: 23, No: 2 , published: 01 January 1996
Pellet power ratio in a pellet-suspension fission core
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Nucl. Technol., Vol: 116, No: 1 , 1996
Feasibility of zero temperature coefficient core with highly diluted fuel and graphite moderator
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Ann. Nucl. Energy, Vol: 22, No: 6 , published: 01 June 1995
A method for neutron transmutation doping of silicon in research reactors
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Ann. Nucl. Energy, Vol: 22, No: 5 , published: 01 May 1995
Методика pасчета и анализ пpименения гpанулиpованных поглотителей в ВВЭР
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Атом. энергия, Vol: 100, No: 1
Канальный пpямоточный pеактоp со свеpхкpитическим давлением теплоносителя
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Атом. энергия, Vol: 98, No: 4
Изучение нейтpонно-физических хаpактеpистик легководного pеактоpа с (Th-U-Pu)-топливом
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Изв. вузов. Ядер. энерг., Vol: 00, No: 2
Сpавнительный анализ pазличных способов достижения больших глубин выгоpания в pеактоpных системах без использования дополнительных поглотителей
Савандеp В.И., Увакин М.А.
Изв. вузов. Ядер. энерг., Vol: 00, No: 2
Работы по пpоектам REDOS и COBRA, связанным с pеактоpной дозиметpией пpи монитоpинге коpпусов давления pеактоpов ВВЭР
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Атом. техн. за рубежом, Vol: , No: 5
Концепция pеактоpа на тепловых нейтpонах с псевдоожиженным потоком топлива
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Влияние глубины выгоpания и выдеpжки облученного ядеpного топлива на отношение массы Am, Cm, Np и делящегося плутония
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Атом. энергия, Vol: 96, No: 2
The fission power of a conceptual fluidised bed thermal nuclear reactor
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Выбор и обоснование оптимальных режимов работы реактора ВВЭР-1000 на мощностном эффекте реактивности
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Neutronics investigations for the lower part of a westinghouse SVEA-96+ assembly
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A mixed-oxide assembly design for rapid disposition of waapons plutonium in pressurized water reactors
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Глубина иодной ямы в РБМК на уран-эрбиевом топливе
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Атом. энергия, Vol: 93, No: 2
Verification of the TRANSURANUS-WWER code version V1M2J00 by Sofit and Kola-3 data bases. II
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Анализ характеристик топливных циклов повышенной длительности реакторов ВВЭР
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Анализ и прогнозирование экономических характеристик топливных циклов реакторов ВВЭР
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Composition heterogeneity analysis for direct use of spent pressuized water reactor fuel in CANDU reactors (DUPIC)-I: deterministic analysis
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Composition heterogeneity analysis for direct use of spent pressurized watwr reactor fuel in CANDU reactors (DUPIC)-II: statistical analysis
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Boiling water reactor loading pattern optimization using simple linear perturbation and modified tabu search methods
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Nucl. Sci. and Eng., Vol: 138, No: 1
Conceptual design of a fluidized bed nuclear reactor
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LWR-PROTEUS verification of reaction rate distributions in modern 10×10 boiling water reactor fuel
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Ядерное топливо с инертной матрицей(IMF)
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Поддержание равновесного офскта - эффективный способ подавления ксеноновых колебаний в ВВЭР-1000
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Атом. энергия, Vol: 90, No: 3
Numerical solution of the chain model of fission product nuclides. Effect on the reactivity of the reactor
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Изв. вузов. Радиоэлектрон., Vol: 28, No: 9
Расчетный бенчмарк по активации конструктивных материалов исследовательского реактора АМ
Мухамадеев Р.И., Суворов А.П.
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Reacteurs nucleaires: le point de vue du physicien
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Ann. phys. (Fr.), Vol: 25, No: 2
Void reactivity effect in a typical candu cell using CPs and a multistratified coolant model
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Effect of void distribution parameter and axial power profile on boiling water reactor ifurcation characteristics
van Bragt D.D.B., Rizwan-uddin, , van der Hagen T.H.J.J.
Nucl. Sci. and Eng., Vol: 134, No: 2
Compatibility analysis of existing reactivity devices in CANDU 6 reactors for DUPIC fuel cycle
Jeong Chang-Joon, Choi Hangbok
Nucl. Sci. and Eng., Vol: 134, No: 3
Analysis of differences in void coefficient predictions for mixed-oxide-fueled tight-pitch light water reactor cells
Unesaki Hironobu, Shiroya Seiji, Kanda Keiji et al.
Nucl. Sci. and Eng., Vol: 135, No: 1
Influence of the thermal cutoff energy on the calculation of neutronic parameters for light water reactor lattices
Paratte Jean-Marie, Pelloni Sandro
Nucl. Sci. and Eng., Vol: 135, No: 1
Reactivity control method for direct use of spent pressurized water reactor fuel in CANDU reactors (DUPIC)
Choi HangbokKo Won Il, Yang Myung Seung
Nucl. Sci. and Eng., Vol: 135, No: 2
Use of axially graded burnable boron for hot-spot temperature reduction in a pressurized water reactor core
Segev M., Galperin A., Schwageraus E.
Nucl. Sci. and Eng., Vol: 135, No: 3
Применение интегрированных с топливными таблетками выгорающих поглотителей в LWR
Горский В.В.
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