Published October 2003 | Version v1
Journal article Metadata-only

Effective delayed neutron fraction and prompt neutron lifetime of Tehran research reactor

Creators

Description

Computer codes Wims-D4 and Citation used for calculations of effective delayed neutron fractions βeff and prompt neutron lifetime (Λ) for both HEU and LEU fuel elements of the Tehran research reactor (TRR). Calculations have been performed for two states of the cold clean and hot core configuration. Calculated beta effective of LEU fuel were compared with the measured value and HEU values were compared with the Safety Analysis Report (SAR) of original HEU Fuel. Also the ratios of (βeff)i/(βeff)core, the input data for the reactivity accident analysis are included in the calculations

Additional details

Identifiers

PII
S0306454903000811;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
30
Journal Issue
15
Journal Page Range
p. 1591-1596
ISSN
0306-4549
CODEN
ANENDJ

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35000588
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
C CODES; HIGHLY ENRICHED URANIUM; MULTIPLICATION FACTORS; RISK ASSESSMENT; SLIGHTLY ENRICHED URANIUM; UTRR REACTOR; W CODES
Descriptors DEC
ACTINIDES; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; POOL TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Copyright
Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.