Works matching DE "NUCLEAR reactor software"
Results: 18
Kondensacijos pliūpsniais varomos cirkuliacijos analizė panaudojant RELAP5 programų paketą.
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- Energetika, 2010, v. 56, n. 3/4, p. 232
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METHODOLOGY AND SOFTWARE FOR GROSS DEFECT DETECTION OF SPENT NUCLEAR FUEL AT THE ATUCHA-I REACTOR.
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- Nuclear Technology, 2015, v. 192, n. 1, p. 74, doi. 10.13182/NT14-63
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VALIDATION OF THE MONTE CARLO MODEL OF THE GREEK RESEARCH REACTOR CORE.
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- Nuclear Technology, 2010, v. 170, n. 3, p. 460, doi. 10.13182/NT10-A10331
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VALIDATION STATUS OF THE ASTEC INTEGRAL CODE FOR SEVERE ACCIDENT SIMULATION.
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- Nuclear Technology, 2010, v. 170, n. 3, p. 397, doi. 10.13182/NT10-A10326
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RESOLUTION OF PROLIFERATION ISSUES FOR A SODIUM FAST REACTOR BLANKET.
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- Nuclear Technology, 2010, v. 170, n. 3, p. 371, doi. 10.13182/NT10-1
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Modification of the individual collision technique for simulating electron transport using the Monte Carlo method.
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- Physics of Atomic Nuclei, 2013, v. 76, n. 13, p. 1563, doi. 10.1134/S1063778813130024
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Influence of the gamma-ray fraction in the reactor radiation on the total signal of a self-powered neutron detector.
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- Physics of Atomic Nuclei, 2013, v. 76, n. 13, p. 1578, doi. 10.1134/S1063778813130061
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Algorithm intended for space-energy parallelization in solving the criticality problem and implemented in the LUCKY_C multiprocessor program.
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- Physics of Atomic Nuclei, 2013, v. 76, n. 13, p. 1569, doi. 10.1134/S1063778813130085
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Experiments on small-size fast critical fuel assemblies at the AKSAMIT facility and their use for development of computational models.
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- Physics of Atomic Nuclei, 2013, v. 76, n. 13, p. 1607, doi. 10.1134/S1063778813130036
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Methodological Foundations and Development of Computational Optimization Complexes for Designing Fast Reactors.
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- Atomic Energy, 2014, v. 117, n. 1, p. 1, doi. 10.1007/s10512-014-9879-z
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Development of an Evaluated Nuclear Database for Modern Technologies.
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- Atomic Energy, 2014, v. 116, n. 4, p. 258, doi. 10.1007/s10512-014-9851-y
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Verification of an improved module for calculating fission products production in the industry code SOKRAT.
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- Atomic Energy, 2013, v. 113, n. 6, p. 435, doi. 10.1007/s10512-013-9658-2
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Calculation of the thermohydraulic parameters of a core comprised of unjacketed fuel assemblies.
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- Atomic Energy, 2009, v. 107, n. 6, p. 374, doi. 10.1007/s10512-010-9239-6
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ANSWERS computer codes: verification and validation for novel reactor applications.
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- Nuclear Future, 2015, v. 11, n. 3, p. 48
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Nuclear Computer Model for Pollution.
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- Quintessence International, 1982, v. 13, n. 6, p. 641
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Formal Modeling and Verification of Safety-Critical Software.
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- IEEE Software, 2009, v. 26, n. 3, p. 42, doi. 10.1109/MS.2009.67
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A DETAILED PERFORMANCE ANALYSIS OF THE INTERPOLATION SUPPLEMENTED LATTICE BOLTZMANN METHOD ON THE CRAY T3E AND CRAY X1.
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- International Journal of High Performance Computing Applications, 2006, v. 20, n. 4, p. 557, doi. 10.1177/1094342006064572
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SCALABILITY MODELING FOR DETERMINISTIC PARTICLE TRANSPORT SOLVERS.
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- International Journal of High Performance Computing Applications, 2006, v. 20, n. 4, p. 541, doi. 10.1177/1094342006064571
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