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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

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT

SED Publication Type

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT

Author
National Atomic Energy Commission
Publication Date

This report describes the actions taken in Argentina on the safety of spent fuel management
(SF) and on the safety of radioactive waste management, in order to provide evidence of the
fulfillment of its obligations under the Joint Convention. To facilitate the reading and a better
understanding of this report a summary of those parts of the 1st Report that were considered
necessary have been included.

spent fuel safety waste management joint convention argentina waste facilities used fuel

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT

SED Publication Type

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT

Author
National Atomic Energy Commission
Publication Date

The present National Report describes the actions taken in Argentina on the safety of spent fuel
(SF) management and on the safety of radioactive waste (RW) management, in order to provide
evidence of the fulfilment of the obligations derived from the Joint Convention. To facilitate the
reading and a better understanding, it has been decided to include a summary of those parts of
the two prior National Reports that are considered necessary in order to comply with this
objective.

spent fuel radioactive waste waste management joint convention waste facilities used fuel

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT FOURTH NATIONAL REPORT Argentina

SED Publication Type

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT FOURTH NATIONAL REPORT Argentina

Author
National Atomic Energy Commission
Publication Date

The structure of the Fourth National Report complies with the Guidelines Regarding the
Form and Structure of National Reports (INFCIRC/604/Rev.1).

Section A describes the scope of the nuclear activity developed in Argentina since 1950
as well as the legal and regulatory framework. It also makes reference to the Strategic
Plan for Radioactive Waste Management (Strategic Plan), which refers to the safety of
Spent Fuel Management and Radioactive Waste Management.

disposal safety radioactive waste waste management siting storage regulations argentina waste facilities

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

The NUMO Structured Approach to HLW Disposal in Japan

SED Publication Type

The NUMO Structured Approach to HLW Disposal in Japan

Author
Nuclear Waste Management Organization of Japan
Publication Date

The constraints set by the Japanese HLW disposal programme – particularly associated with
the decision to initiate siting by an open call for volunteers to host a geological repository –
pose particular challenges for repository project management. In order to maintain the
flexibility required to respond to the conditions found at volunteer sites, NUMO has not
published reference designs or site characterisation plans, as is normal for programmes
progressing by site nomination. Instead, we have developed a methodology – the NUMO

disposal high level waste repository japan siting waste facilities

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT NATIONAL REPORT ARGENTINA 2003

SED Publication Type

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT NATIONAL REPORT ARGENTINA 2003

Author
National Atomic Energy Commission
Publication Date

The structure of this National Report complies, to the greatest adjustment possible, with the
Guidelines Regarding the Form and Structure of National Reports approved in the
Preparatory Meeting held in Vienna in December 2001.

Section A includes a general introduction to the report, and a reference to the National
Program which contemplates spent fuel and radioactive waste management and the treatment
of wastes that originate from Mining and Uranium Processing.

spent fuel radioactive waste waste management regulations waste facilities 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
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