Published April 2017 | Version v1
Journal article Metadata-only

Radiation field for the decommissioning source term of Qinshan reactor

Creators

  • 1. Sanmen Technician College, Taizhou (China)
  • 2. School of Nuclear Science and Technology, University of South China, Hengyang (China)
  • 3. Shanghai Nuclear Engineering Research and Design Institute, Shanghai (China)

Description

According to the actual situation of Qinshan reactor, pin-by-pin neutron transport calculation model for the whole core was set up by Monte Carlo codes, and the reliability of the model was validated. Based on geometric parameters, material parameters, neutron fluence rate distribution of structure parts, and under assumed reactor power operation history, burnup calculation codes are used to calculate the neutron activation products as estimation results of source term after shutdown, and to analyze the 3D radiation field visualized model of source term. The simulation results are consistent with the theoretical analysis. This study is an important fundamental work for the establishment of the decommissioning technology security verification and virtual simulation platform for Qinshan nuclear power plant. (authors)

Additional details

Publishing Information

Journal Title
Chinese Journal of Nuclear Science and Engineering
Journal Volume
37
Journal Issue
2
Journal Page Range
p. 302-307
ISSN
0258-0918

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
52062317
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BURNUP; DECOMMISSIONING; DISTRIBUTION; GEOMETRY; MONTE CARLO METHOD; NEUTRON FLUENCE; NEUTRON TRANSPORT; NEUTRONS; NUCLEAR POWER PLANTS; OPERATION; QINSHAN-1 REACTOR; RELIABILITY; SECURITY; SHUTDOWN; SIMULATION; SOURCE TERMS; VERIFICATION
Descriptors DEC
BARYONS; CALCULATION METHODS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FACILITIES; NUCLEONS; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; RADIATION TRANSPORT; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
7 figs., 3 tabs., 11 refs.