Heat generation and corresponding energy saving in nuclear reactor shielding facilities due to γ-rays energy variation
Creators
Description
This paper deals with the energy generation within shielding materials when single energy photons of 1.43 and 2.75 MeV, emitted from V52 and Na24 disc source respectively penetrate single layer shields of Al, Fe, Pb and graphite. The calculation is carried out using the build up factor method. A comparison has been made in order to estimate the percentage of energy saving for each photon energy and shielding material. Also the theoretical and experimental build up factors, used for the energy generation calculation, are presented. The theoretical scalar flux, calculated using the Monte-Carlo code SAM-CE, was applied for the theoretical build up factor calculation. The scalar flux measured directly in experimental facilities was used for the experimental build up factor calculation
Additional details
Identifiers
- PII
- S0306454902000361;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 30
- Journal Issue
- 1
- Journal Page Range
- p. 55-62
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 33048663
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ABSORPTION HEAT; BUILDUP; CALCULATION METHODS; EXPERIMENTAL DATA; FLUX DENSITY; GRAPHITE; MONTE CARLO METHOD; PHOTON EMISSION; S CODES; SHIELDING MATERIALS
- Descriptors DEC
- CALCULATION METHODS; CARBON; COMPUTER CODES; DATA; ELEMENTS; EMISSION; ENERGY; ENTHALPY; HEAT; INFORMATION; MATERIALS; MINERALS; NONMETALS; NUMERICAL DATA; PHYSICAL PROPERTIES; THERMODYNAMIC PROPERTIES
Optional Information
- Copyright
- Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.