Engagement opportunities in OECD NEA benchmark development
暂无分享,去创建一个
P. Blaise | U. Rohatgi | A. Petruzzi | G. Ilas | T. Valentine | W. Marshall | M. DeHart | O. Buß | E. Ivanov | Julie-Fiona Martin | I. Hill | J. Bess | T. Ivanova | Thomas Miller | C. Percher | Michael Fleming
[1] C. Herer. ASN/IRSN guide 28: Qualification of scientific computing tools used in the nuclear safety case – 1st barrier , 2023, Nuclear Engineering and Design.
[2] U. Rohatgi,et al. OVERVIEW OF THE OECD-NEA EXPERT GROUP ON MULTI-PHYSICS EXPERIMENTAL DATA, BENCHMARKS AND VALIDATION , 2018, EPJ Web of Conferences.
[3] Upendra S. Rohatgi,et al. The International Experimental Thermal Hydraulic Systems Database (TIETHYS): A New NEA Validation Tool , 2018, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation.
[4] Ian C Gauld,et al. SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data , 2017 .
[5] F. D’Auria,et al. Standardized Consolidated Calculated and Reference Experimental Database (SCCRED): A Supporting Tool for V&V and Uncertainty Evaluation of Best-Estimate System Codes for Licensing Applications , 2016 .
[6] J. B. Briggs,et al. Applications of Integral Benchmark Data , 2014 .
[7] N. Soppera,et al. IDAT: The International Handbook of Evaluated Reactor Physics Benchmark Experiments Database and Analysis Tool , 2014 .
[8] J. B. Briggs,et al. An Overview of the International Reactor Physics Experiment Evaluation Project , 2014 .
[9] I. Kodeli,et al. 20 Years of SINBAD (Shielding Integral Benchmark Archive and Database) , 2014 .
[10] 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 .
[11] J. B. Briggs,et al. The International Criticality Safety Benchmark Evaluation Project , 2002 .
[12] E. Sartori,et al. SINBAD – Radiation shielding benchmark experiments , 2021 .
[13] I. Gauld,et al. SFCOMPO DATABASE OF SPENT NUCLEAR FUEL ASSAY DATA – THE NEXT FRONTIER , 2021, EPJ Web of Conferences.
[14] R. Bordia,et al. Transactions of the American Nuclear Society , 2012 .
[15] Francesco Saverio D'Auria,et al. Validation Matrix for the assessment of Thermal-Hydraulic codes for VVER LOCA and Transient , 2001 .
[16] Francesco Saverio D'Auria,et al. Evaluation of the Separate effects tests (SET) Validation Matrix. OECD-CSNI Report , 1996 .
[17] Francesco Saverio D'Auria,et al. Separate Effects Test Matrix for Thermal-hydraulic Code Validation: Facility and Experiment Characteristics,Vol II , 1993 .