OECD/NEA expert group on uncertainty analysis for criticality safety assessment: Results of benchmark on sensitivity calculation (phase III)

Conference · Sun Jul 01 00:00:00 EDT 2012

OSTI ID:22105774

Ivanova, T.; Laville, C. ^[1]; Dyrda, J. ^[2]; Mennerdahl, D. ^[3]; Golovko, Y.; Raskach, K.; Tsiboulia, A. ^[4]; Lee, G. S.; Woo, S. W. ^[5]; Bidaud, A.; Sabouri, P. ^[6]; Patel, A. ^[7]; Bledsoe, K.; Rearden, B. ^[8]; Gulliford, J.; Michel-Sendis, F. ^[9]

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1. Institut de Radioprotection et de Surete Nucleaire IRSN, BP 17, 92262 Fontenay aux Roses (France)
2. Atomic Weapons Establishment AWE, Aldermaston, Reading, RG7 4PR (United Kingdom)
3. E Mennerdahl Systems EMS, Starvaegen 12, 18357 Taeby (Sweden)
4. Inst. for Physics and Power Engineering IPPE, 1, Bondarenko sq., 249033 Obninsk (Russian Federation)
5. Korea Inst. of Nuclear Safety KINS, 62 Gwahak-ro, Yuseong-gu, Daejeon 305-338 (Korea, Republic of)
6. Laboratoire de Physique Subatomique et de Cosmologie LPSC, CNRS-IN2P3/UJF/INPG, Grenoble (France)
7. U.S. Nuclear Regulatory Commission (NRC), Washington, DC 20555-0001 (United States)
8. Oak Ridge National Laboratory ORNL, M.S. 6170, P.O. Box 2008, Oak Ridge, TN 37831 (United States)
9. OECD/NEA, 12, Bd des Iles, 92130 Issy-les-Moulineaux (France)

The sensitivities of the k{sub eff} eigenvalue to neutron cross sections have become commonly used in similarity studies and as part of the validation algorithm for criticality safety assessments. To test calculations of the sensitivity coefficients, a benchmark study (Phase III) has been established by the OECD-NEA/WPNCS/EG UACSA (Expert Group on Uncertainty Analysis for Criticality Safety Assessment). This paper presents some sensitivity results generated by the benchmark participants using various computational tools based upon different computational methods: SCALE/TSUNAMI-3D and -1D, MONK, APOLLO2-MORET 5, DRAGON-SUSD3D and MMKKENO. The study demonstrates the performance of the tools. It also illustrates how model simplifications impact the sensitivity results and demonstrates the importance of 'implicit' (self-shielding) sensitivities. This work has been a useful step towards verification of the existing and developed sensitivity analysis methods. (authors)

• Research Organization: American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
• OSTI ID: 22105774
• Resource Relation: Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 33 refs.
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
ALGORITHMS
BENCHMARKS
COMPUTER CODES
CRITICALITY
CROSS SECTIONS
DATA COVARIANCES
EIGENFUNCTIONS
EIGENVALUES
FISSION
MONTE CARLO METHOD
NEUTRONS
ONE-DIMENSIONAL CALCULATIONS
RISK ASSESSMENT
SAFETY ENGINEERING
SENSITIVITY
SENSITIVITY ANALYSIS
THREE-DIMENSIONAL CALCULATIONS
VALIDATION