Category of Content
Siting Experience Documents Only
Publication Date
Keywords
The Nuclear Energy Research Initiative Burnup Credit Critical Experiment
The Nuclear Energy Research Initiative Burnup Credit Critical Experiment
Reconciliation of Isotopic Uncertainty Between Assays and Integral Benchmarks
Reconciliation of Isotopic Uncertainty Between Assays and Integral Benchmarks
IAEA TCM 2000: An International Meeting on Burnup Credit Applications
IAEA TCM 2000: An International Meeting on Burnup Credit Applications
Actinide-Only Burnup Credit License Application: the CASTOR X/32 S Cask Modeling Details
Actinide-Only Burnup Credit License Application: the CASTOR X/32 S Cask Modeling Details
Applicability of CRC Benchmark Experiments for Burnup Credit Validation
Applicability of CRC Benchmark Experiments for Burnup Credit Validation
Full Burnup Credit in Transport and Storage Casks--Benefits and Implementation
Full Burnup Credit in Transport and Storage Casks--Benefits and Implementation
Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D
Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D
Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs
Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs
Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation
Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation
PWR Burnup Credit Using Both Belts and Suspenders
PWR Burnup Credit Using Both Belts and Suspenders
Status of the Joint French ISPN/COGEMA Qualification Programme of Fission Products
Status of the Joint French ISPN/COGEMA Qualification Programme of Fission Products
Design of Wet Storage Racks for Spent BWR Fuel
Design of Wet Storage Racks for Spent BWR Fuel
SAS2D--A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
SAS2D--A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
From Integral Experiments to Nuclear Data Improvement
From Integral Experiments to Nuclear Data Improvement
Target accuracy on LWR neutronics parameters is 2 to 5 times lower than the a priori uncertainty (1σ)
due to nuclear data. This paper summarizes the experimental facilities and the integral measurements that are required
for code qualification. The rigorous use of integral information through trend analysis method is described. Trends
on JEF2 data from Keff measurements and P.I.Es are presented. These trends were accounted for in the new JEFF3
evaluations. The role of fundamental experiments, such as worth measurement of separated isotopes, is emphasized.
Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition-Proceedings of a Technical Meeting held in London, 29 August-2 September 2006
Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition-Proceedings of a Technical Meeting held in London, 29 August-2 September 2006
This publication records the proceedings of a technical meeting organized by the IAEA and
held in London 29 August–2 September 2005 with sixty participants from 18 countries. As
indicated in the title, the objective of this meeting was to provide a forum for exchange of
technical information on spent fuel burnup credit applications and thereby compile state-ofthe-
art information on technical advances related to spent fuel transportation, storage,
reprocessing and disposition.