Published September 2011 | Version v1
Miscellaneous

OECD/UACSA criticality benchmark study to account for fabrication tolerances (Phase II), CRISTAL - SCALE - MCNP evaluations - 5-07

  • 1. AREVA NP Front End Business Group, 12, rue J. Recamier, 69456 Lyon Cedex 06 (France)
  • 2. SOFREN - Engineering Consultant, 28, rue Dr. Brouardel, 76620 Le Havre (France)

Description

The evaluation of the calculated neutron multiplication factor Keff of a fuel system has to account for: -) the bias due to both the biases on the nuclear data applied and the algorithmic and numerical weakness of the criticality code package used, -) the uncertainty in Keff due to the uncertainties in the nuclear data applied, and -) the uncertainty in Keff due to the uncertainties (manufacturing tolerances and/or variations) in the parameters describing the fuel system of interest. An OECD Expert Group was created in 2009 to address more particularly the analysis of the uncertainty in Keff due to the manufacturing tolerances of the design parameters of a fuel assembly configuration derived from typical wet PWR fuel storage rack design and PWR fuel basket design for transport/storage casks. The UACSA (Uncertainty Analysis for Criticality Safety Assessments) working group gathers skills from both the industry and research laboratories. As an option and in order to benchmark the criticality code package used against real experiments some ICSBEP (International Criticality Safety Benchmark Evaluation Program) cases are also suggested. Even if the French criticality code package CRISTAL V1 is the basic code and methodology tool for AREVA Front End Business Group comparisons with other well known codes such as SCALE6 and MCNP4C2 were performed on those ICSBEP benchmarks and on the bounding cases of the OECD/UACSA benchmarks. Those later comparisons with a good agreement observed from the CRISTAL-SCALE-MCNP code packages give confidence for the criticality safety evaluations AREVA Front End Business Group have to perform either for its fuel manufacturing plants and fresh fuel shipping casks or for its abroad increasing criticality safety evaluations. The paper will focus on the full CRISTAL V1 parametric studies as requested by the UACSA working group as well as on some proposed ICSBEP critical experiments comparisons. As a conclusion of this paper it is observed that the three criticality code packages are well suited to assess criticality safety concerns. (authors)

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
9 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
53066742
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACCURACY; BENCHMARKS; C CODES; COMPUTERIZED SIMULATION; CRITICALITY; MULTIPLICATION FACTORS; PARAMETRIC ANALYSIS; TOLERANCE
Descriptors DEC
COMPUTER CODES; DIMENSIONLESS NUMBERS; SIMULATION

Optional Information

Notes
4 refs.