Published 2005 | Version v1
Report Open

The VALMONT experimental programme for the neutronics qualification of the UMo/Al fuel for the Jules-Horowitz-Reactor

Creators

  • 1. Nuclear Energy Division/Dpt. of Reactor Studies, CEA Cadarache, F-13108 Saint Paul lez Durance (France)

Description

The proper and safe estimation of the uncertainties associated with the results of neutronics calculations is crucial for the design studies of the future Jules Horowitz Reactor (JHR). However, the neutronics characteristics of this innovative core and, in particular, the use of the new UMo/Al fuel preclude the use of the existing qualification databases. The need for specific experimental data for this fuel was met by the VALMONT programme, which consisted in the precise measurement of the reactivity effect of fuel samples in the MINERVE reactor. These measurements, corroborated by γ-spectroscopic analysis on irradiated UMo/Al fuel, allow to qualify the HORUS3D/N neutronics calculation route for this fuel. Moreover, the application of the representativity method allowed to reduce the uncertainty on the reactivity, due to the uncertainties of the basic nuclear data of the Uranium isotopes, by a factor of 3. (author)

Files

36069527.pdf

Files (426.5 kB)

Name Size Download all
md5:d2a31e0fd4b32e34da54c481639b8f59
426.5 kB Preview Download
Part of:
Abstracts and papers presented at the 2004 international RERTR meeting

Additional details

Identifiers

URL
http://www.rertr.anl.gov/RERTR26/index.html;

Publishing Information

Imprint Title
Abstracts and papers presented at the 2004 international RERTR meeting
Imprint Pagination
585 p.
Journal Page Range
10 p.
Report number
INIS-XA-C--119

Conference

Title
26. international meeting on Reduced Enrichment for Research and Test Reactors (RERTR)
Dates
7-12 Nov 2004
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
36069527
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
ALUMINIUM; BURNUP; CALCULATION METHODS; CROSS SECTIONS; EXPERIMENTAL DATA; GAMMA SPECTROSCOPY; H CODES; JULES HOROWITZ REACTOR; MINERVE REACTOR; PERFORMANCE TESTING; RADIATION EFFECTS; URANIUM ISOTOPES; URANIUM-MOLYBDENUM FUELS
Descriptors DEC
ALLOY NUCLEAR FUELS; COMPUTER CODES; DATA; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; INFORMATION; IRRADIATION REACTORS; ISOTOPES; MATERIALS; MATERIALS TESTING REACTORS; METALS; NUCLEAR FUELS; NUMERICAL DATA; POOL TYPE REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID FUELS; SPECTROSCOPY; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZERO POWER REACTORS

Optional Information

Notes
5 refs