Published June 2013 | Version v1
Journal article Metadata-only

Power confirming for critical facility based on activation method and MCNP code

Creators

  • 1. Reactor Engineering Research Sub-institute, Nuclear Power Institute of China, Chengdu (China)

Description

The method for power confirming was introduced. Neutron fluence rate distribution and absolute neutron fluence rate of one point for critical facility under different powers were measured by activation method. Neutron fluence rate distribution was calculated with compiled MCNP code. The power of critical facility was calculated with fission rate method based on neutron fluence rate. The power was extrapolated while the max thermal neutron fluence rate was l × l08 cm-2·s-1. The power confirming for critical facility was completed. (authors)

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
47
Journal Issue
suppl
Journal Page Range
p. 111-113
ISSN
1000-6931

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
48068965
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
COMPUTER CALCULATIONS; DISTRIBUTION; FISSION; M CODES; NEUTRON FLUENCE; THERMAL NEUTRONS; ZERO POWER REACTORS
Descriptors DEC
BARYONS; COMPUTER CODES; ELEMENTARY PARTICLES; EXPERIMENTAL REACTORS; FERMIONS; HADRONS; NEUTRONS; NUCLEAR REACTIONS; NUCLEONS; REACTORS; RESEARCH AND TEST REACTORS

Optional Information

Notes
1 fig., 6 refs.