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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

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

Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit

Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit

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

The purpose of this study is to provide insights into the neutronic similarities that may exist between a
generic cask containing typical spent nuclear fuel assemblies and commercial reactor critical (CRC) state-
points. Forty CRC state-points from five pressurized-water reactors were selected for the study and the
type of CRC state-points that may be applicable for validation of burnup credit criticality safety
calculations for spent fuel transport/storage/disposal systems are identified. The study employed cross-

burnup credit criticality analysis nureg/cr-6951 ornl/tm-2006/87 keff validation spent fuel composition crc sensitivity analysis

Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages

Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages

Author(s)
DeHart, M. D.
Publication Date

Spent fuel transportation and storage cask designs based on a burnup credit approach must
consider issues that are not relevant in casks designed under a fresh-fuel loading assumption. For
example, the spent fuel composition must be adequately characterized and the criticality analysis
model can be complicated by the need to consider axial burnup variations. Parametric analyses are
needed to characterize the importance of fuel assembly and fuel cycle parameters on spent fuel

burnup credit pwr spent fuel ornl/tm-12973 sensitivity analysis used fuel

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff) Predictions

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff) Predictions

Author(s)
Scaglione, J. M. ,
Mueller, D. E. ,
Wagner, J. C. ,
Marshall, W. J.
Publication Date

Taking credit for the reduced reactivity of spent nuclear fuel (SNF) in criticality analyses is referred to as burnup credit (BUC). Criticality safety evaluations require validation of the computational methods with critical experiments that are as similar as possible to the safety analysis models, and for which the keff values are known. This poses a challenge for validation of BUC criticality analyses, as critical experiments with actinide and fission product (FP)

burnup credit spent fuel fission products nureg/cr-7109 ornl/tm-2011/514 criticality analysis keff validation sensitivity analysis used fuel

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report

Author
Austria
Publication Date

This report provides - a detailed description of the Austrian policy and the usual practices concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section B); - a detailed description of the Austrian legal regime concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section E).

siting national report joint convention spent fuel management austria radioactive waste management

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Austrian National Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Austrian National Report

Author
Austria
Publication Date

In Austria there is neither a nuclear power plant (NPP) nor any other fuel cycle facility in op- eration. One NPP was constructed in Zwentendorf in the 1970s, but, as a consequence of the negative vote in a referendum never put into operation. Two out of three research reactors in Austria have been shut down (ASTRA Seibersdorf in 2000, SIEMENS Argonaut Graz in 2004) and are currently under decommissioning. The remaining TRIGA research reactor in Vienna is still in operation. Spent nuclear fuel is stored on site in wet or dry storage facilities.

siting national report joint convention spent fuel management austria radioactive waste management

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Review Meeting of the Contracting Parties, 15 to 24 2006, Vienna, Austria, Summary Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Review Meeting of the Contracting Parties, 15 to 24 2006, Vienna, Austria, Summary Report

Author
Austria
Publication Date

1. Recognizing the importance of the safe management of spent nuclear fuel and radioactive waste, the international community agreed upon the necessity of adopting a convention describing how such safe management could be achieved: this was the origin of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the “Joint Convention”), which was adopted on 5 September 1997 and entered into force on 18 June 2001. 2.

siting national report joint convention spent fuel management austria radioactive waste management

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Review Meeting of the Contracting Parties, 11 to 20 May 2009, Vienna, Austria, Summary Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Third Review Meeting of the Contracting Parties, 11 to 20 May 2009, Vienna, Austria, Summary Report

Author
Austria
Publication Date

1. Recognizing the importance of the safe management of spent nuclear fuel and radioactive waste, the international community agreed upon the necessity of adopting a convention with the objective of achieving and maintaining a high level of safety worldwide in spent fuel and radioactive waste management: this was the origin of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the “Joint Convention”), which was adopted on 5 September 1997 and entered into force on 18 June 2001. 2.

siting national report joint convention spent fuel management austria radioactive waste management

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth Review Meeting of the Contracting Parties, 14 to 23 May 2012, Vienna, Austria, Final Summary Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth Review Meeting of the Contracting Parties, 14 to 23 May 2012, Vienna, Austria, Final Summary Report

Author
Austria
Publication Date

1. Recognizing the importance of the safe management of spent nuclear fuel and radioactive waste, the international community agreed upon the necessity of adopting a convention with the objective of achieving and maintaining a high level of safety worldwide in spent fuel and radioactive waste management: this was the origin of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the “Joint Convention”), which was adopted on 5 September 1997 and entered into force on 18 June 2001. 2.

siting national report joint convention spent fuel management austria radioactive waste management

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Review Meeting of the Contracting Parties 3 to 14 November 2003, Vienna, Austria, Summary Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Review Meeting of the Contracting Parties 3 to 14 November 2003, Vienna, Austria, Summary Report

Author
Austria
Publication Date

1. The operation of nuclear reactors whether for the purposes of electricity production or research, generates spent nuclear fuel and radioactive waste. Other activities also generate radioactive waste. The recognition by the international community of the importance of ensuring the safety of the management of spent fuel and the safety of the management of radioactive waste, led to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Convention).

siting national report joint convention spent fuel management austria radioactive waste management
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