Published December 2012 | Version v1
Journal article Metadata-only

Application of MCNP SOURCE subroutine to shutdown dose rate calculation

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

The photon transport calculation in shutdown dose rate calculation of fusion facility is carried out by MCNP usually. Huge amount of cells are needed to describe the fusion facility due to its high complexity of mal and geometry. The SDEF card of MCNP limits that the number of source cells should be below 1000. Thus, the photon source involved in shutdown dose rate calculation code cannot be specified by the card because of this restriction. To settle down the problem, the source is sampled directly in SOURCE subroutine in this paper. Tests by ITER benchmark for shutdown dose rate and ITER-T426 experimental benchmark show its validity and reliability. (authors)

Additional details

Publishing Information

Journal Title
Chinese Journal of Nuclear Science and Engineering
Journal Volume
32
Journal Issue
4
Journal Page Range
p. 366-370
ISSN
0258-0918

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
46127558
Subject category
S97: MATHEMATICAL METHODS AND COMPUTING; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
BENCHMARKS; DOSE RATES; GEOMETRY; ITER TOKAMAK; M CODES; PHOTON TRANSPORT; PHOTONS; RELIABILITY; SHUTDOWN
Descriptors DEC
BOSONS; CLOSED PLASMA DEVICES; COMPUTER CODES; ELEMENTARY PARTICLES; MASSLESS PARTICLES; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
5 figs., 14 refs. FDS Team