Published January 2003 | Version v1
Journal article

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.