Monte Carlo analysis of a neutron streaming experiment
Creators
- 1. Oak Ridge National Lab., TN (United States). Radiation Shielding Information Center
- 2. Korea Atomic Energy Research Inst., Health Physics Div., P.O. Box 7, Dae-Duk Danji, Chung-nam (Korea, Republic of)
Description
This paper reports on the analysis of neutron spectra emitted form a 14-MeV source and streaming through a void steel duct embedded in concrete carried out using a multigroup Monte Carlo code on a small computer. The calculated results are compared with experimental results and with other calculational analyses involving continuous energy Monte Carlo methods. The computational methods agree when the PN expansion of the multigroup method is sufficiently extended. Some discrepancies with the experimental results, found in earlier analyses, still remain; and these are investigated with regard to the use of a new modification of the evaluated iron data, the spreading of the calculated results for comparison with experimental spectra, and various other modeling details
Additional details
Publishing Information
- Journal Title
- Nuclear Science and Engineering
- Journal Volume
- 107
- Journal Issue
- 2
- Series
- Nucl. Sci. Eng.
- Journal Page Range
- 180-187
- ISSN
- 0029-5639
- CODEN
- NSENA
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23019568
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- CALCULATION METHODS; CONCRETES; MEV RANGE 10-100; MONTE CARLO METHOD; MULTIGROUP THEORY; NEUTRON SPECTRA; NEUTRON TRANSPORT; REACTOR SAFETY EXPERIMENTS; STEELS
- Descriptors DEC
- ALLOYS; BUILDING MATERIALS; CARBON ADDITIONS; ENERGY RANGE; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MEV RANGE; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; SPECTRA; TRANSPORT THEORY