Published December 1986
| Version v1
Journal article
The experimental research of neutron flux fitting method in a zero power reactor
- 1. Shanghai Nuclear Engineering Research and Design Inst. (China)
Description
The neutron fluxes have been measured at few points in the core of 728 zero power reactor by using pulse-micro fission chamber. The point flux then was extended to produce the whole core flux distribution by fitting analysis, and further, the hot channel factor (FqN) and enthalpy rising factor (FΔHN) concerned in engineering were obtained. The result is satisfactory. It can be used to measure the power distribution during the initial startup of Qin Shan nuclear power reactor
Additional details
Publishing Information
- Journal Title
- Chin. J. Nucl. Sci. Eng.
- Journal Volume
- 6
- Journal Issue
- 2
- Series
- Chin. J. Nucl. Sci. Eng.
- Journal Page Range
- 184-191
- CODEN
- HYGOD
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 19013924
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DATA COMPILATION; FISSION CHAMBERS; MEASURING METHODS; NEUTRON FLUX; POWER DISTRIBUTION; ZERO POWER REACTORS
- Descriptors DEC
- DISTRIBUTION; EXPERIMENTAL REACTORS; IONIZATION CHAMBERS; MEASURING INSTRUMENTS; NEUTRON DETECTORS; RADIATION DETECTORS; RADIATION FLUX; REACTORS; RESEARCH AND TEST REACTORS; SPATIAL DISTRIBUTION