Published June 2018 | Version v1
Miscellaneous Metadata-only

Verification of MCU and CASMO5 computer codes based on depletion of different types of fuel assemblies for PWR

Creators

  • 1. JSC Afrikantov OKBM, 15 Burnakovsky Proyezd, Nizhny Novgorod, 603074 (Russian Federation)

Description

Within the frame of present studies, comparative depletion analyses of PWR FA cells were performed using enhanced accuracy MCU-Trb code and CASMO5 code. The MCU-Trb code is an upgraded version of the MCU-Tr code implemented based on the MCU5 package enabling neutron transport process modeling through analog and non-analog Monte-Carlo methods. This paper provides the comparison results of breeding ratio dependence on depletion, concentrations of isotopes and comparison of average power density fields in FA at the BOL. (Author)

Availability note (English)

Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), e-mail: mclaudia.gonzalez@inin.gob.mx

Additional details

Publishing Information

Publisher
Sociedad Nuclear Mexicana
Imprint Place
Ciudad de Mexico (Mexico)
Imprint Pagination
12 p.

Conference

Title
reactor physics paving the way towards more efficient systems
Acronym
PHYSOR 2018
Dates
22-26 Apr 2018
Place
Cancun, Q. R. (Mexico)

INIS

Country of Publication
Mexico
Country of Input or Organization
Mexico
INIS RN
50006163
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACCURACY; BREEDING RATIO; C CODES; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CONCENTRATION RATIO; FUEL ASSEMBLIES; ISOTOPES; M CODES; MONTE CARLO METHOD; NEUTRON TRANSPORT; POWER DENSITY; PWR TYPE REACTORS; VERIFICATION
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; CONVERSION RATIO; DIMENSIONLESS NUMBERS; ENRICHED URANIUM REACTORS; EVALUATION; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; RADIATION TRANSPORT; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Funding organization
Sociedad Nuclear Mexicana (Mexico); American Nuclear Society (United States); GE Hitachi (United States); Instituto Nacional de Investigaciones Nucleares (Mexico); TerraPower (United States); Consejo Nacional de Ciencia y Tecnologia (Mexico)