Published 2012 | Version v1
Book Metadata-only

Preliminary TRIGA fuel burn-up evaluation by means of Monte Carlo code and computation based on total energy released during reactor operation

Creators

  • 1. Italian National Inst. of Nuclear Physics INFN, Section of Pavia, Via A. Bassi, 6, 27100 Pavia (Italy)
  • 2. Dept. of Nuclear and Theoretical Physics, Univ. of Pavia, 27100 Pavia (Italy)
  • 3. Applied Nuclear Energy Laboratory LENA, Univ. of Pavia, Via Aselli, 41, 27100 Pavia (Italy)
  • 4. Italian National Inst. of Nuclear Physics INFN, Section of Milano Bicocca, P.zza della Scienza, 3, 20126 Milano (Italy)
  • 5. Physics Dept. G. Occhialini, Univ. of Milano Bicocca, 20126 Milano (Italy)
  • 6. Dept. of Energy Enrico Fermi Centre for Nuclear Studies CeSNEF, Polytechnic Univ. of Milan, Via U. Bassi, 34/3, 20100 Milano (Italy)

Description

Aim of this work was to perform a rough preliminary evaluation of the burn-up of the fuel of TRIGA Mark II research reactor of the Applied Nuclear Energy Laboratory (LENA) of the Univ. of Pavia. In order to achieve this goal a computation of the neutron flux density in each fuel element was performed by means of Monte Carlo code MCNP (Version 4C). The results of the simulations were used to calculate the effective cross sections (fission and capture) inside fuel and, at the end, to evaluate the burn-up and the uranium consumption in each fuel element. The evaluation, showed a fair agreement with the computation for fuel burn-up based on the total energy released during reactor operation. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
ISBN
978-0-89448-085-9
Imprint Pagination
9 p.

Conference

Title
Conference on Advances in Reactor Physics - Linking Research, Industry, and Education
Acronym
PHYSOR 2012
Dates
15-20 Apr 2012
Place
Knoxville, TN (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
44063460
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; CROSS SECTIONS; EVALUATION; FLUX DENSITY; FUEL ELEMENTS; FUEL MANAGEMENT; MONTE CARLO METHOD; NEUTRON FLUX; NUCLEAR FUELS; REACTOR FUELING; REACTOR OPERATION; RESEARCH REACTORS; SIMULATION; TRIGA TYPE REACTORS; UNINTERRUPTIBLE POWER SUPPLIES; URANIUM
Descriptors DEC
ACTINIDES; CALCULATION METHODS; ELECTRONIC EQUIPMENT; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EQUIPMENT; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MANAGEMENT; MATERIALS; METALS; NUCLEAR MATERIALS MANAGEMENT; OPERATION; POWER SUPPLIES; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs.