Published 2006 | Version v1
Book Metadata-only

Validation of depletion codes for burnup credit evaluation of LWR assemblies

Creators

  • 1. Technical Research Centre of Finland VTT, POB 1000, 02044-VTT (Finland)

Description

This paper reports the comparison of the CASMO-4E predictions with the radiochemical assay data from assemblies irradiated in Takahama-3 PWR and Fukushima-Daini-2 BWR, and the most recently reported spent fuel data from the VVER-440 assembly irradiated in Novovoronezh 4. Some of the calculations were repeated with the ABURN burnup code, which is a combination of the MCNP4C Monte Carlo code and the ORIGEN2 depletion code. The cross section libraries applied were based on the ENDF/B-VI and the JEF-2.2 data. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
0-89448-697-7
Imprint Pagination
11 p.

Conference

Title
American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
Acronym
PHYSOR-2006
Dates
10-14 Sep 2006
Place
Vancouver, BC (Canada)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
43130061
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; CROSS SECTIONS; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; O CODES; PWR TYPE REACTORS; RADIOCHEMICAL ANALYSIS; SPENT FUEL ELEMENTS; SPENT FUELS; VALIDATION; WWER TYPE REACTORS
Descriptors DEC
CALCULATION METHODS; CHEMICAL ANALYSIS; COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVALUATION; FUEL ELEMENTS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; PWR TYPE REACTORS; QUANTITATIVE CHEMICAL ANALYSIS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs.