scholarly journals Contributions to integral nuclear data in ICSBEP and IRPhEP since ND2016

2020 ◽  
Vol 239 ◽  
pp. 18007
Author(s):  
John Darrell Bess ◽  
Tatiana Ivanova ◽  
J. Blair Briggs
Keyword(s):  
Spectral Characteristics ◽  
Nuclear Data ◽  
Nuclear Facilities ◽  
Reactor Physics ◽  
Benchmark Experiment ◽  
Reactivity Coefficients ◽  
Physics Experiment ◽  
Safety Applications ◽  
Evaluation Project ◽  
Criticality Safety

The contributions to the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) was last presented to the international nuclear data community at ND2016. Since ND2016, integral benchmark data that are available for nuclear data testing has continued to increase. The 2018 edition of the International Handbook of Evaluated Criti-cality Safety Benchmark Experiments (ICSBEP Handbook) now contains 574 evaluations with benchmark specifications for 4,916 critical, near-critical, or subcritical configurations, 45 criticality alarm placement/shielding configuration with multiple dose points apiece, and 215 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications. The 2018 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook) contains data from 159 different experimental series that were performed at 54 different nuclear facilities. Currently 156 of the 159 evaluations are published as approved benchmarks with the remaining three evaluations published as drafts. Measurements found in the IRPhEP Handbook include criticality, buckling and extrapolation length, spectral characteristics, reactivity effects, reactivity coefficients, kinetics, reaction-rate distributions, power distributions, isotopic compositions, and/or other miscellaneous types of measurements for various types of reactor systems. Additional benchmark evaluations will be included in the 2019 editions of these handbooks. These handbooks continue to represent the standard for neutronics benchmark experiment evaluation.

scholarly journals Current overview of ICSBEP and IRPhEP benchmark evaluation practices

2020 ◽  
Vol 239 ◽  
pp. 18002
Author(s):  
John Darrell Bess ◽  
Tatiana Ivanova
Keyword(s):  
Data Sets ◽  
Experiment Data ◽  
Reactor Physics ◽  
Energy Agency ◽  
Evaluation Practices ◽  
Benchmark Experiment ◽  
Physics Experiment ◽  
Benchmark Evaluation ◽  
Evaluation Project ◽  
Criticality Safety

Two projects sanctioned by the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) have over two decades of experience developing established and comprehensive data sets in handbooks supporting criticality safety and reactor physics. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) serve as examples of quality and excellence in preserving our experimental data heritage and establishing integral benchmark standards upon which current and future modeling, validation, and safety efforts can be supported. Evaluation practices have evolved with each year of these projects to include additional benchmark experiment data, establish more comprehensive techniques for evaluation of uncertainties and biases, and encourage established high-quality peer-review efforts. This paper will summarize the current format of the handbooks, best-practices for a comprehensive benchmark evaluation, recent activities and protocol within these projects, and a look into future identified needs and activities.

scholarly journals SFCOMPO DATABASE OF SPENT NUCLEAR FUEL ASSAY DATA – THE NEXT FRONTIER

2021 ◽  
Vol 247 ◽  
pp. 10019
Author(s):  
Germina Ilas ◽  
Ian Gauld ◽  
Pedro Ortego ◽  
Shuichi Tsuda
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Critical Evaluation ◽  
Working Party ◽  
Test Bed ◽  
Reactor Physics ◽  
Current Effort ◽  
Energy Agency ◽  
Physics Experiment ◽  
Criticality Safety

SFCOMPO is the world’s largest database for measured spent nuclear fuel assay data. An international effort coordinated by the Nuclear Energy Agency (NEA) resulted in a significant expansion of the database and its release online in 2017 as a downloadable application. The SFCOMPO Technical Review Group (TRG) was recently formed under the direction of NEA’s Nuclear Science Committee/Working Party on Nuclear Criticality Safety and was mandated to maintain and further coordinate the development of SFCOMPO. This TRG is currently focused on (1) critical evaluation of the experimental assay data by independent experts and (2) development of benchmarks and benchmark models that can be applied to validate burnup codes. This will improve the quality and documentation of the experimental datasets and enable their use by the international community to support code validation for design and safety analysis of spent nuclear fuel transportation, storage, and repository applications. It follows the precedent and draws on the experience gained from similar NEA efforts in the International Reactor Physics Experiment Evaluation Project and the International Criticality Safety Benchmark Experiment Project. Ongoing SFCOMPO evaluations have served as a test bed to develop templates for documenting evaluations, develop review guidance, improve approaches for a global uncertainty analysis, and devise a strategy focused on providing practical information of highest value to the user community. The current effort, status, and associated challenges are discussed.

scholarly journals THE PRINCESS PROJECT: FROM DIFFERENTIAL TO INTEGRAL EXPERIMENTS

2021 ◽  
Vol 247 ◽  
pp. 20002
Author(s):  
Isabelle Duhamel ◽  
Mariya Brovchenko ◽  
Jean-Baptiste Clavel ◽  
Matthieu Duluc ◽  
Raphaëlle Ichou ◽  
...  
Keyword(s):  
Experimental Data ◽  
Nuclear Physics ◽  
Nuclear Data ◽  
Nuclear Safety ◽  
Reactor Physics ◽  
Neutron Physics ◽  
Experimental Facilities ◽  
Integral Data ◽  
Criticality Safety

Following the shutdown of the CEA Valduc experimental facilities, where, for more than 50 years, IRSN used to perform experiments related to criticality safety, IRSN initiated a new project named PRINCESS (PRoject for IRSN Neutron physics and Criticality Experimental data Supporting Safety). The objective is to continue collecting experimental data necessary for the IRSN missions in nuclear safety. For this purpose, collaborations with various national and international laboratories have been established. The PRINCESS project covers various nuclear physics fields from nuclear data to criticality-safety and reactor physics providing information to both differential and integral data improvements.

scholarly journals Verification and validation of SuperMC3.2 with heavy water reactor model DCA

2020 ◽  
Vol 35 (1) ◽  
pp. 24-29
Author(s):  
Quan Gan ◽  
Shengpeng Yu ◽  
Lijuan Hao ◽  
Jing Song ◽  
L LongPengcheng
Keyword(s):  
Heavy Water ◽  
Safety Evaluation ◽  
Simulation Software ◽  
Verification And Validation ◽  
Reactor Physics ◽  
Reactor Model ◽  
Water Reactor ◽  
Heavy Water Reactor ◽  
Physics Experiment ◽  
Evaluation Project

The super multi-functional calculation program for nuclear design and safety evaluation is a general, intelligent, accurate and precise simulation software system for the nuclear design and safety evaluations. The heavy water reactor has a much stronger moderation power and much longer diffusion length of the thermalized neutrons. The paper intends to show the verification and validation of SuperMC3.2 with a heavy-water-moderated lattice named the deuterium critical assembly which is very similar to the Canada Deuterium Uranium type reactor and selected from the international reactor physics experiment evaluation project. The calculation results were compared with the reference calculated results and the experimental data from International Reactor Physics Experiment Evaluation Project. The final obtained results proved the accuracy, convenience and universality of SuperMC, and primarily verified the applicability of SuperMC in nuclear analysis of heavy water reactor.

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