Published December 2013 | Version v1
Journal article Metadata-only

Benchmark of neutron transport simulation capability of super Monte Carlo calculation program SuperMC2.0

Creators

  • 1. Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei (China)
  • 2. University of Science and Technology of China, Hefei (China)

Description

Super Monte Carlo calculation program for nuclear and radiation process (SuperMC2.0) developed by FDS team is a radiation transport code based on Monte Carlo method. A series of testing samples, such as critical safety, neutron integral leakage benchmarks and IAEA-ADS, were used to verify the neutron transport simulation of SuperMC2.0. The results of SuperMC2.0 are in accordance with the results of MCNP and experiments. The correctness of neutron transport in SuperMC2.0 is preliminarily verified. (authors)

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
47
Journal Issue
suppl
Journal Page Range
p. 520-525
ISSN
1000-6931

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
48069055
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
BENCHMARKS; CRITICALITY; INTEGRALS; M CODES; MONTE CARLO METHOD; NEUTRON LEAKAGE; NEUTRON TRANSPORT; NEUTRONS; RADIATION TRANSPORT; SAFETY; SIMULATION; TESTING
Descriptors DEC
BARYONS; CALCULATION METHODS; COMPUTER CODES; ELEMENTARY PARTICLES; FERMIONS; HADRONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; RADIATION TRANSPORT

Optional Information

Notes
2 figs., 6 tabs., 18 refs.