Published September 2006 | Version v1
Journal article Metadata-only

Calculation of neutron response for high sensitivity environmental neutron dose equivalent meter

Creators

  • 1. China Institute of Atomic Energy, Beijing (China)

Description

The energy responses of high sensitivity environmental neutron dose equivalent meter was calculated by MCNP4C code. The calculated results are satisfied in interesting neutron energy fields, and the shape of the response curve agrees with H* (10) curve in ICRP 74 report. It is seen that MCNP4C code can be applied to calculate neutron response for high sensitivity environmental neutron dose equivalent meter, and it can raise work efficiency and help to analyze the experimental results. (authors)

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
40
Journal Issue
suppl
Journal Page Range
p. 134-138
ISSN
1000-6931

Conference

Title
4. Symposium on Nuclear Technology Application of Beijing Nuclear Society
Dates
2006
Place
Beijing (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
47093995
Subject category
S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CALCULATIONS; DIAGRAMS; DOSE EQUIVALENTS; DOSEMETERS; EFFICIENCY; ENVIRONMENTAL EXPOSURE; ICRP; M CODES; NEUTRON DOSIMETRY; NEUTRONS; SENSITIVITY
Descriptors DEC
BARYONS; COMPUTER CODES; DOSIMETRY; ELEMENTARY PARTICLES; FERMIONS; HADRONS; INFORMATION; INTERNATIONAL ORGANIZATIONS; MEASURING INSTRUMENTS; NUCLEONS

Optional Information

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