The Application of Radiochemical Measurements of PWR Spent Fuel for the Validation of Burnup Codes

The paper shows the usage of destructive assay data from PWR fuel samples for the validation of the NFCSS burnup system developed by the IAEA. The results of radiochemical measurements of spent fuel isotopic composition were compared with the results of numerical modelling. In total, 254 samples from 15 PWRs, incorporated in the SFCOMPO database, were applied in the validation study. The paper shows the trends observed in the calculated-to-experimental ratios for eight major actinides and six minor actinides present in spent nuclear fuel. The data were quantified and analysed considering the enrichment, burnup and origin. The obtained results were compared with other studies on burnup validation using different numerical tools. In general, the results of numerical modelling for major actinides show rather good consistency with radiochemical measurements, while the results for minor actinides are less accurate.

[1]  J. Cetnar,et al.  Development of a Trajectory Period Folding Method for Burnup Calculations , 2022, Energies.

[2]  Abdolhamid Minuchehr,et al.  Development and validation of ISOBURN, a new depletion code , 2021 .

[3]  D. Rochman,et al.  Nuclear Data Uncertainty Quantification in Criticality Safety Evaluations for Spent Nuclear Fuel Geological Disposal , 2021, Applied Sciences.

[4]  M. Oettingen.  Assessment of the Radiotoxicity of Spent Nuclear Fuel from a Fleet of PWR Reactors , 2021, Energies.

[5]  Jerzy Cetnar,et al.  Linear Chain Method for Numerical Modelling of Burnup Systems , 2021, Energies.

[6]  A. Peakman,et al.  Criticality Analysis for BWR Spent Fuel Based on the Burnup Credit Evaluation from Full Core Simulations , 2021, Applied Sciences.

[7]  A. Peakman,et al.  Burnup Credit Evaluation for BWR Spent Fuel from Full Core Calculations , 2020, Applied Sciences.

[8]  M. Radaideh,et al.  Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled Neutronics/Thermal-Hydraulics Simulations , 2020 .

[9]  A. Peakman,et al.  Evaluation of BWR Burnup Calculations Using Deterministic Lattice Codes SCALE-6.2, WIMS-10A and CASMO5 , 2020, Energies.

[10]  I. Gauld,et al.  Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit , 2019, Nuclear Engineering and Design.

[11]  M. Pecchia,et al.  Preliminary Assessment of Criticality Safety Constraints for Swiss Spent Nuclear Fuel Loading in Disposal Canisters , 2019, Materials.

[12]  P. Stanisz,et al.  Monte Carlo modelling of Th-Pb fuel assembly with californium neutron source , 2018, Nukleonika.

[13]  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 .

[14]  Ian C Gauld,et al.  Integral nuclear data validation using experimental spent nuclear fuel compositions , 2017 .

[15]  Tomasz Mirowski,et al.  The MCB code for numerical modeling of Fourth Generation nuclear reactors , 2015, Comput. Sci..

[16]  J. Cetnar,et al.  Comparative analysis between measured and calculated concentrations of major actinides using destructive assay data from Ohi-2 PWR , 2015 .

[17]  K. Suyama,et al.  Validation of Burnup Calculation Code SWAT4 by Evaluation of Isotopic Composition Data of Mixed Oxide Fuel Irradiated in Pressurized Water Reactor , 2015 .

[18]  C. Weber,et al.  Reactor Fuel Isotopics and Code Validation for Nuclear Applications , 2015 .

[19]  Jerzy Cetnar,et al.  Validation of gadolinium burnout using PWR benchmark specification , 2014 .

[20]  Toru Yamamoto,et al.  Analysis of measured isotopic compositions of high-burnup PWR MOX and UO2 fuels in the MALIBU program , 2012 .

[21]  Ian C Gauld,et al.  Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE , 2012 .

[22]  Joachim Doll,et al.  Organization for Economic Cooperation and Development , 2021, International Organization.