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Title: Experiments and Theoretical Data for Studying the Impact of Fission Yield Uncertainties on the Nuclear Fuel Cycle with TALYS/GEF and the Total Monte Carlo Method

We describe the research program of the nuclear reactions research group at Uppsala University concerning experimental and theoretical efforts to quantify and reduce nuclear data uncertainties relevant for the nuclear fuel cycle. We briefly describe the Total Monte Carlo (TMC) methodology and how it can be used to study fuel cycle and accident scenarios, and summarize our relevant experimental activities. Input from the latter is to be used to guide the nuclear models and constrain parameter space for TMC. The TMC method relies on the availability of good nuclear models. For this we use the TALYS code which is currently being extended to include the GEF model for the fission channel. We present results from TALYS-1.6 using different versions of GEF with both default and randomized input parameters and compare calculations with experimental data for {sup 234}U(n,f) in the fast energy range. These preliminary studies reveal some systematic differences between experimental data and calculations but give overall good and promising results.
Authors:
 [1] ; ; ; ; ;  [1] ;  [2] ;  [3] ; ;  [1] ;  [2] ; ; ;  [1]
  1. Department of Physics and Astronomy, Uppsala University, Box 516, 751 20 Uppsala (Sweden)
  2. Nuclear Research and Consultancy Group NRG, P.O.Box 25, 1755 ZG Petten (Netherlands)
  3. (Sweden)
Publication Date:
OSTI Identifier:
22436786
Resource Type:
Journal Article
Resource Relation:
Journal Name: Nuclear Data Sheets; Journal Volume: 123; Conference: International workshop on nuclear data covariances, Santa Fe, NM (United States), 28 Apr - 1 May 2014; Other Information: Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; DATA COVARIANCES; EXPERIMENTAL DATA; FISSION YIELD; FUEL CYCLE; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; NUCLEAR MODELS; RESEARCH PROGRAMS; THEORETICAL DATA; URANIUM 234