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

Journal Article · Thu Jan 15 04:00:00 EST 2015 · Nuclear Data Sheets

DOI:https://doi.org/10.1016/J.NDS.2014.12.038· OSTI ID:22436786

Al-Adili, A.; Alhassan, E.; Gustavsson, C.; Helgesson, P.; Hellesen, C. ^[1]; Koning, A. J. ^[2]; Lantz, M.; Österlund, M. ^[1]; Rochman, D. ^[2]; Simutkin, V.; Sjöstrand, H.; Solders, A. ^[1]

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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)

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.

• OSTI ID: 22436786
• Journal Information: Nuclear Data Sheets, Journal Name: Nuclear Data Sheets Vol. 123; ISSN NDTSBA; ISSN 0090-3752
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
DATA COVARIANCES
EXPERIMENTAL DATA
FISSION YIELD
FUEL CYCLE
MONTE CARLO METHOD
NUCLEAR DATA COLLECTIONS
NUCLEAR FUELS
NUCLEAR MODELS
RESEARCH PROGRAMS
THEORETICAL DATA
URANIUM 234