Organized by the Nuclear Safety Council of Spain (CSN) in cooperation with the International Atomic Energy Agency (IAEA). Co-sponsored by ENUSA Industrias Avanzadas S.A. and Empresa Nacional de Residuos Radiactivos S.A. (ENRESA)
SESSION I: INTERNATIONAL AND NATIONAL REPORTS
Co-Chairs: J.-C. Neuber (AREVA), J. M. Conde (CSN)
1.1 |
“IAEA Activities on Spent Fuel Management” |
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1.2 |
“Lessons Learned from International Investigations of Burnup Credit Criticality” |
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1.3 |
“Activities of the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel” |
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1.4 |
“Burnup Credit Development and Implementation in the Slovak Republic” |
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1.5 |
“Applying Burn-up Credit Technology for Spent Fuel Storage in China” |
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1.6 |
“National program for BUC application in India” |
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1.7 |
“Research Activities of JAEA Considering the Future Needs of Japan in Burnup Credit Implementation” |
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1.8 |
“Review of Technical Studies in the United States in Support of Burnup Credit Regulatory Guidance” |
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1.9 |
”Latest Studies Related to the Use of Burnup Credit in France” |
SESSION II: CALCULATION METHODS
II.A Codes and methods
Co-Chairs: S. Evo (IRSN), John C. Wagner (ORNL)
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Chair overview of the status and the main challenges in burnup credit depletion calculation |
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2.1 |
“Enhancements to the Burnup Credit Criticality Safety Analysis Sequence in SCALE” |
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2.2 |
“Assessment of the MCNP+ACAB Code System for Burnup Credit Analysis” |
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2.3 |
“Convergence issues in Best-estimate Monte Carlo Depletion Calculations” |
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2.4 |
“Peak Reactivity Characterization and Isotopic Inventory Calculations for BWR Criticality Applications” |
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Chair overview of the main improvements in nuclear data with respect to burnup credit nuclides and on the availability of assay data |
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2.5 |
“Correction Factors Derived from French Experiments with the Recent JEFF3.1.1 Library for PWR-UOx BUC Applications” |
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2.6 |
“Study of Burnup Reactivity and Isotopic Inventory in REBUS Program” |
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2.7 |
“PWR and BWR Fuel Assay Data Measurements” |
II.C Sensitivity/Uncertainty analyses
Co-Chairs: J.-C. Neuber (AREVA), T. Ivanova (IRSN)
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Chair overview of the objectives, key concepts, and methods |
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2.8 |
“Sensitivity/uncertainty Analysis applied to the Phase VII Benchmark” |
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2.9 |
“Use of French Fission Product Experiments for Burnup Credit Validation” |
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2.10 |
“General hierarchical Bayesian procedure for calculating the bias and the a posteriori uncertainty of neutron multiplication factors” |
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2.11 |
“Usage of TSUNAMI in a Hierarchical Bayesian Procedure for Calculating the Bias and the a posteriori Uncertainty of keff” |
Note: Papers 2.10 and 2.11 were merged into one. The slides and paper files are the same for both.
II.D Verification and validation
Co-Chairs: M. Brady-Raap (PNNL), Ian C. Gauld (ORNL)
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Chair overview of the available data and methods |
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2.12 |
“Determination of a Depletion Uncertainty from Fuel Management Experience” |
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2.13 |
“Sufficiency of Available MOX Experiments for Criticality calculation validation of VVER Burnup Credit Application” |
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2.14 |
“Evaluation of Fission Product Critical Experiments and Associated Biases for Burnup Credit Validation” |
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2.15 |
“Regulatory Perspective on Computer Code Validation for Burnup Credit Criticality Analyses for Spent Nuclear Fuel Transportation |
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2.16 |
“SCALE Validation Experience using an Expanded Isotopic Assay Database for Spent Nuclear Fuel” |
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SESSION III: APPLICATIONS AND IMPLEMENTATION
Co-Chairs: J. Gulliford (NNL), A. Barto (USNRC)
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Chair overview of reactor operations impacting the spent fuel reactivity and the burnup distribution |
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3.1 |
“Regulatory Perspective on Confirmatory Burnup Measurements for Burnup Credit in Spent Nuclear Fuel Transportation |
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3.2 |
“Fuel Burnup Plant Records: Generation and Accuracy” |
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3.3 |
“Recommended Bounding Axial Burnup Profiles In BUC Applications From Actual Burnup Measurement Of French PWR Assemblies” |
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3.4 |
“Inventory Prediction and BUC Calculations Related to MEU/LEU IRT Fuels of LVR-15 Research” |
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3.5 |
“Fuel Depletion Calculation in MTR-LEU NUR Reactor” |
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3.6 |
“Burnup Credit in the Swedish Interim Storage Facility (CLAB)” |
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3.7 |
“Lessons Learnt from OECD/NEA Phase II-C through Phase II-E Benchmarks” |
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3.8 |
“Review of results for the OECD/NEA Phase VII Benchmark: Study of the Spent Fuel Compositions for Long Term disposal” |
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3.9 |
“Burnup Credit Approach for the Proposed United States Repository at Yucca Mountain” |
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3.10 |
“Regulatory Issues for Final Disposal” |
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3.11 |
“Burnup Credit in the Canister for Final Disposal of Spent Nuclear Fuel” |
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Last reviewed: 19 August 2013