Published June 1993
| Version v1
Journal article
HFETR core neutron spectra calculation
Description
The ANISN code, the DOT 3.5 code and the Combinatorial Geometry Full Energy Range Monte Carlo code are used to calculate the core neutron spectra of HFETR. HFETR core is simplified as composed of fuels, beryllium reflector, surrounded by aluminium and water. Irradiation channels and capsules are put into the central position of the core (K11). By analysing the calculation results of different core arrangements, some valuable conclusions are derived for the optimal radius of a cylinder flux trap, the analytical expression of epithermal neutron spectra and other calculated results are compared with experimental results of spectra and spectrum parameters
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 13
- Journal Issue
- 2
- Journal Page Range
- p. 135-142.
- ISSN
- 0258-0918
- CODEN
- HYGODG
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 25040335
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; CALCULATION METHODS; D CODES; DISADVANTAGE FACTOR; FAST NEUTRONS; HFETR REACTOR; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON SPECTRA; REACTOR CORES; THERMAL NEUTRONS; THERMAL UTILIZATION
- Descriptors DEC
- BARYONS; COMPUTER CODES; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; NEUTRONS; NUCLEONS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; SPECTRA; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS