Published September 2011 | Version v1
Miscellaneous

Isotopic uncertainty assessment due to nuclear data uncertainties in high-burnup samples - 5-09

  • 1. Institute of Nuclear Fusion Universidad Politecnica de Madrid, C/Jose Gutierrez Abascal, n2, 28006, Madrid (Spain)
  • 2. Department of Nuclear Engineering, Universidad Politecnica de Madrid, C/Jose Gutierrez Abascal, n2, 28006, Madrid (Spain)

Description

The aim of this paper is to study the importance of nuclear data uncertainties in the prediction of high-burnup spent fuel content and its effect in the criticality safety assessment. Calculations described in this paper were performed for a typical pin-cell in a water moderated infinite lattice configuration. This fuel rod with an initial 235U enrichment of 4.5 wt% is irradiated to an average burnup of about 78 MWd/kgU. We conclude for this prediction that: (i) decay data uncertainties have a negligible effect on the isotopic prediction both in actinides and fission products, the maximum relative errors are found for 155Eu (7.3%), 106Ru (0.6%) and 243Cm (0.4%) (ii) fission yield data uncertainties induce relative errors in fission products below 5%, the maximum relative errors are found for 95Mo (4.9%) and 149Sm (4.8%); and (iii) larger uncertainties in concentrations were found due to cross section data uncertainties.We have performed a burnup criticality uncertainty analysis for this high-burnup LWR pin-cell with TSUNAMI code showing that relative error in keff at EOC can reach ∼900 pcm, being the most important source of uncertainty: 239Pu(nu-bar), 238U(n,n'), 238U(n,γ) and 239Pu(n,fission). At BOC, with low relative error in keff ∼500 pcm, being 235U(nu-bar), 238U(n,n') and 235U(n,γ) the most important reactions. The contribution of the concentration uncertainty of major-minor actinides and fission products is also assessed

Part of:
Proceedings of the Ninth International Conference on Nuclear Criticality Safety - ICNC 2011

Additional details

Publishing Information

Imprint Title
Proceedings of the Ninth International Conference on Nuclear Criticality Safety - ICNC 2011
Imprint Pagination
1726 p.
Journal Page Range
12 p.
Report number
INIS-XN--22-ICNC-2011

Conference

Title
International conference on nuclear criticality
Acronym
ICNC 2011
Dates
19-22 Sep 2011
Place
Edinburgh (United Kingdom)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
France
INIS RN
53066744
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACCURACY; BURNUP; CHEMICAL COMPOSITION; COMPUTERIZED SIMULATION; NUCLEAR DATA COLLECTIONS; SPENT FUELS; T CODES; VALIDATION
Descriptors DEC
COMPUTER CODES; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; SIMULATION; TESTING

Optional Information

Notes
16 refs.