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U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks
U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks
In July 1999, the U.S. Nuclear Regulatory Commission (NRC) Spent Fuel Project Office
(SFPO) issued Interim Staff Guidance 8 Revision 1 (ISG8R1) to provide recommendations for the use
of burnup credit in storage and transport of pressurized-water reactor (PWR) spent fuel. Subsequent to
the issuance of ISG8R1, the NRC Office of Regulatory Research (RES) has directed an effort to
investigate the technical basis for extending the criteria and recommendations of ISG8R1 to allow
End Effect keff Cias Curve for Actinide-Only Burnup Credit Casks
End Effect keff Cias Curve for Actinide-Only Burnup Credit Casks
A conservative end effect keff bias curve for actinide-only burnup credit casks is presented
in this paper. Rather than performing axially burnup-dependent analysis, cask designers can, if
they choose to, analyze casks with a uniform axial burnup (at assembly average burnup value) and
add the keff bias values to conservatively bound the actinide-only end effect. Earlier studies
suggested 1-3% increase in keff to account for the end effect, but they included fission products
as well as actinides for their analyses.
Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation
Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation
Assessment of Benefits for Extended Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA
Assessment of Benefits for Extended Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA
This paper presents an assessment of the benefits for extended burnup credit in transporting
pressurized-water-reactor (PWR) spent nuclear fuel (SNF) in the United States. A prototypic 32-
assembly cask and the current regulatory guidance were used as bases for this assessment. By
comparing recently released PWR discharge data with actinide-only-based loading curves, this
evaluation shows that additional negative reactivity (through either increased credit for fuel burnup or
A Coordinated U.S. Program to Address Full Burnup Credit in Transport and Storage Casks
A Coordinated U.S. Program to Address Full Burnup Credit in Transport and Storage Casks
The benefits of burnup credit and the technical issues associated with utilizing burnup credit in spent
nuclear fuel (SNF) casks have been studied in the United States for almost two decades. The issuance of the
U.S. Nuclear Regulatory Commission (NRC) staff guidance for actinide-only burnup credit in 2002 was a
significant step toward providing a regulatory framework for using burnup credit in transport casks. However,
adherence to the current regulatory guidance (e.g., limit credit to actinides) enables only about 30% of the existing
slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
UNF-STANDARDS presentation to EPRI extended storage collaboration project
UNF-STANDARDS presentation to EPRI extended storage collaboration project
Understanding the changing nuclear and mechanical characteristics of used nuclear fuel (UNF) over time and how these changing characteristics affect storage, transportation, and disposal options can require many tools and types of data. To streamline analysis capabilities for the waste management system, a comprehensive, integrated data and analysis tool has been assembled—UNF-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS).
Effects of the Presence of Axial Blankets and Integral Burnable Absorbers on the End Effect of PWR Burnup Profiles
Effects of the Presence of Axial Blankets and Integral Burnable Absorbers on the End Effect of PWR Burnup Profiles
Limited Burnup Credit for Increased Fuel Enrichments in a Swiss PWR Storage Pool
Limited Burnup Credit for Increased Fuel Enrichments in a Swiss PWR Storage Pool
Research Supporting Implementation of Burnup Credit in Transport and Storage Casks
Research Supporting Implementation of Burnup Credit in Transport and Storage Casks
Comparison of Computational Estimations of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
Comparison of Computational Estimations of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
Impact of Integral Burnable Absorbers on PWR Burnup Credit Criticality Safety Analyses
Impact of Integral Burnable Absorbers on PWR Burnup Credit Criticality Safety Analyses
Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses
Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses
Spent Fuel Criticality Benchmark Experiments
Spent Fuel Criticality Benchmark Experiments
The Burn-Up Credit Experimental Programme REBUS
The Burn-Up Credit Experimental Programme REBUS
Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety
Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety
Reactivity End-Effects Estimates Using a K Perturbation Model
Reactivity End-Effects Estimates Using a K Perturbation Model
Criticality Safety Evaluation of Fuel Storage Pools in Spain
Criticality Safety Evaluation of Fuel Storage Pools in Spain
A Validated Methodology for Evaluating Burnup Credit in Spent Fuel Casks
A Validated Methodology for Evaluating Burnup Credit in Spent Fuel Casks
Uncertainties in Criticality Analysis Which Affect the Storage and Transportation of LWR Fuel
Uncertainties in Criticality Analysis Which Affect the Storage and Transportation of LWR Fuel
Generic Reactivity Equivalence of PWR Fuel in Spent Fuel Storage Racks
Generic Reactivity Equivalence of PWR Fuel in Spent Fuel Storage Racks
Conservative Axial Burnup Distributions for Actinide-Only Burnup Credit
Conservative Axial Burnup Distributions for Actinide-Only Burnup Credit
Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks
Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks
In 1999, the United States Nuclear Regulatory Commission (U.S. NRC) initiated a research program
to support the development of technical bases and guidance that would facilitate the implementation of burnup
credit into licensing activities for transport and dry cask storage. This paper reviews the following major areas of
investigation: (1) specification of axial burnup profiles, (2) assumption on cooling time, (3) allowance for
assemblies with fixed and removable neutron absorbers, (4) the need for a burnup margin for fuel with initial