Published 2005 | Version v1
Book Metadata-only

Delayed neutron fraction in low enrichment nuclear fuel. Calculation for RA-3 reactor case

Creators

  • 1. Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

Description

The delayed neutron fraction (βeff ) is recalculated for the case of RA-3 Reactor core (Ezeiza Atomic Centre) which is composed of LEU fuel. The main target is the renormalization of reactor power measured with neutron noise. The previous accepted value of βeff was 8.14E-03. Now this parameter is re-evaluated using neutron diffusion code PUMA and transport code WIMS. Considered was a five group neutron spectrum, several percentages of burn-up and νd from various authors. The nuclear fraction of delayed neutron calculation gave 6.84 E-03 and the effective one 7.69 E-03, resulting sensitive mainly to νd and not to fuel burn-up. (author)

Part of:
Research reactor utilization, safety, decommissioning, fuel and waste management. Posters of an international conference

Additional details

Identifiers

URL
http://www-pub.iaea.org/MTCD/publications/PDF/Pub1212/P1212_Posters_web.pdf;

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (Austria)
ISBN
92-0-113904-7
Imprint Title
Research reactor utilization, safety, decommissioning, fuel and waste management. Posters of an international conference
Imprint Pagination
298 p.
Series
Proceedings series
Journal Page Range
p. 21-24
ISSN
0074-1884

Conference

Title
International conference on research reactor utilization, safety, decommissioning, fuel and waste management
Dates
10-14 Nov 2003
Place
Santiago (Chile)

INIS

Country of Publication
Austria
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
37012500
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; DELAYED NEUTRON FRACTION; DELAYED NEUTRONS; ENRICHMENT; NEUTRON DIFFUSION EQUATION; NEUTRON SPECTRA; NUCLEAR FUELS; RA-3 REACTOR; REACTOR CORES; W CODES
Descriptors DEC
BARYONS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTARY PARTICLES; ENERGY SOURCES; EQUATIONS; FERMIONS; FISSION NEUTRONS; FUELS; HADRONS; MATERIALS; NEUTRONS; NUCLEONS; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SPECTRA; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS

Optional Information

Notes
11 refs, 2 tabs
Secondary number(s)
IAEA-CN--100/28P