Establishment of Correlations for Some Critical and Reactor Physics Experiments

Abstract Criticality safety and reactor physics benchmark experiments may share certain components of the configurations and the same experimental techniques. This results in correlations between pairs of benchmark experiments. The correlations may impact validation results of criticality safety or reactor physics calculations as well as nuclear data validation. This paper presents how experimental correlations have been established for some fast and thermal neutron spectra configurations, documented in International Handbook of Evaluated Criticality Safety Benchmark Experiments and in International Handbook of Evaluated Reactor Physics Benchmark Experiments. It also discusses the impact of those correlations on validation of the most recent nuclear data libraries.

[1]  Bucholz,et al.  SCALE: a modular code system for performing standardized computer analyses for licensing evaluation , 1981 .

[2]  Tatiana Ivanova,et al.  Towards validation of criticality calculations for systems with MOX powders , 2009 .

[3]  Andrei D. Polyanin,et al.  A Concise Handbook of Mathematics, Physics, and Engineering Sciences , 2010 .

[4]  K. F. Raskach,et al.  Influence of the Correlations of Experimental Uncertainties on Criticality Prediction , 2003 .

[5]  V. Rich.  Personal communication , 1989, Nature.

[6]  Hugo J. Hahn.  ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT, NUCLEAR ENERGY AGENCY , 1983 .

[7]  L. G. LeSage.  An overview of the Argonne National Laboratory fast critical experiments 1963-1990. , 2001 .

[8]  M. Salvatores,et al.  The role of differential and integral experiments to meet requirements for improved nuclear data , 2007 .

[9]  Thomas E. Booth,et al.  Release of MCNP5_RSICC_1.30. , 2004 .

[10]  J. L. Rowlands.  Accuracy of criticality calculations made using current nuclear data libraries for MOX fuelled fast critical assemblies , 2010 .

[11]  Gérald Rimpault,et al.  THE ERANOS CODE AND DATA SYSTEM FOR FAST REACTOR NEUTRONIC ANALYSES , 2002 .

[12]  Organisation for Economic Cooperation and Development,et al.  Organisation for economic cooperation and development , 1998 .

[13]  Van Der Marck,et al.  Benchmarking ENDF/B-VII.1, JENDL-4.0 and JEFF-3.1 , 2012 .

[14]  Victor Picheny,et al.  Using the Efficient Global Optimization Algorithm to Assist Nuclear Criticality Safety Assessment , 2013 .

[15]  Evgeny Ivanov,et al.  Uncertainty Assessment for Fast Reactors Based on Nuclear Data Adjustment , 2014 .

[16]  J. B. Briggs,et al.  Identification of Integral Benchmarks for Nuclear Data Testing Using DICE (Database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments) , 2011 .