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Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Author(s)
Mueller, D. E. ,
Wagner, J. C.
Publication Date
The responsible use of calculational methods in nuclear criticality safety includes a determination of bias and bias uncertainty that may exist between the calculated results and reality. Such biases exist due to approximations used to model the real world, uncertainties in nuclear data, and approximations associated with the calculational method (e.g., Monte Carlo method). The bias and bias uncertainty are typically determined by using the modeling approximations, nuclear data, and calculational method to model well-known, usually critical, systems.
burnup credit criticality analysis iaea-tecdoc-1547 iaea sensitivity analysis

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Isotopic Composition Predictions

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Isotopic Composition Predictions

Author(s)
Radulescu, G. ,
Gauld, I. C. ,
Ilas, G. ,
Wagner, J. C.
Publication Date

Taking credit for the reduced reactivity of spent nuclear fuel in criticality analyses is referred to
as burnup credit. Criticality safety evaluations employing burnup credit require validation of the
depletion and criticality calculation methods and computer codes with available measurement
data. To address the issues of burnup credit criticality validation, the U.S. Nuclear Regulatory
Commission initiated a project with Oak Ridge National Laboratory to (1) develop and establish

fission products nureg/cr-7108 ornl/tm-2011/509 criticality aalysis burnup credit spent fuel composition validation sensitivity analysis

Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)

Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)

Author(s)
NRC
Publication Date

This guidance manual provides the NRC staff methodology for calculating parameters for limiting conditions of operation required in the radiological effluent Technical Specifications for light-water-cooled nuclear power plants. it provides guidance in using the model specifications reported in NUREG-0472 (Revision 1)*, and NUREG-0473 (Revision 1)*, applicable to operating PWR and BWR licensees, and users of the Standard Technical Specifications packages available for various vendor designs.

pwr bwr operation regulations radioactive waste management standard technical specifications

Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit

Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit

Author(s)
Radulescu, G. ,
Mueller, D. E. ,
Wagner, J. C.
Publication Date

This paper provides insights into the neutronic similarities between a representative high-capacity rail-transport cask containing typical pressurized water reactor (PWR) spent nuclear fuel assemblies and critical reactor state-points, referred to as commercial reactor critical (CRC) state-points. Forty CRC state-points from five PWRs were analyzed, and the characteristics of CRC state-points that may be applicable for validation of burnup-credit criticality safety calculations for spent fuel transport/storage/disposal systems were identified.

burnup credit spent fuel criticality analysis keff validation spent fuel composition sensitivity analysis used fuel

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

Author(s)
Solis, J.
Publication Date

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

slides nei used fuel management meeting cfd thermal modeling vacuum drying
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