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Assessment of Fission Product Cross-Section Data for Burnup Credit Applications
Assessment of Fission Product Cross-Section Data for Burnup Credit Applications
Past efforts by the Department of Energy (DOE), the Electric Power Research Institute (EPRI), the Nuclear Regulatory Commission (NRC), and others have provided sufficient technical information to enable the NRC to issue regulatory guidance for implementation of pressurized-water reactor (PWR) burnup credit; however, consideration of only the reactivity change due to the major actinides is recommended in the guidance.
Validation of important fission product evaluations through CERES integral benchmarks
Validation of important fission product evaluations through CERES integral benchmarks
Optimization of energy resources suggests increased fuel residence in reactor cores and hence improved
fission product evaluations are required. For thermal reactors the fission product cross sections in the JEF2.2 and
JEFF3.1 libraries plus new evaluations from WPEC23 are assessed through modelling the CERES experiment in
the DIMPLE reactor. The analysis uses the lattice code WIMS10. Cross sections for 12 nuclides are assessed. The
thermal cross section and low energy resonance data for 147,152Sm and 155Gd are accurate to within 4%. Similar data
Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations
Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations
U.S. Nuclear Regulatory Commission Interim Staff Guidance 8 (ISG-8) for burnup credit covers actinides only, a position based primarily on the lack of definitive critical experiments and adequate radiochemical assay data that can be used to quantify the uncertainty associated with fission product credit.
Evaluation of Internal Criticality of the Plutonium Disposition MOX SNF Waste Form
Evaluation of Internal Criticality of the Plutonium Disposition MOX SNF Waste Form
The purpose of this calculation is to perform a parametric study to determine the effects of fission product leaching, assembly collapse, and iron oxide loss on the reactivity of a waste package containing mixed oxide spent nuclear fuel. Previous calculations (CRWMS M&O 1998a) have shown that the criticality control features of the waste package are adequate to prevent criticality of a flooded WP for all the enrichment/burnup pairs expected for the MOX SNF.
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
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
Computational Benchmark for Estimation of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
Computational Benchmark for Estimation of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
This report proposes and documents a computational benchmark problem for the estimation of the additional reactivity margin available in spent nuclear fuel (SNF) from fission products and minor actinides in a burnupcredit storage/transport environment, relative to SNF compositions containing only the major actinides. The benchmark problemlconfiguration is a generic burnup credit cask designed to hold 32 pressurized water reactor (PWR) assemblies.
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
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)
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Australian National Report, July 2003
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Australian National Report, July 2003
The responsibility for the governance of Australia is shared by Australia's federal government (also known as the Commonwealth government) and the governments of the six states and two self governing territories. Responsibility for radiation health and safety in each State and Territory rests with the respective State/Territory government, unless the activity is carried out by a Commonwealth agency or a contractor to a Commonwealth agency; in those cases the activity is regulated by the Federal government (Commonwealth government of Australia).
Fission Product Benchmarking for Burnup Credit Applications
Fission Product Benchmarking for Burnup Credit Applications
Progress toward developing a technical basis for a cost-effective burnup credit methodology for
spent nuclear fuel with initial U-235 enrichment up to 5% is presented. Present regulatory
practices provide as much burnup credit flexibility as can be currently expected. Further progress
is achievable by incorporating the negative reactivity effects of a subset of neutron-absorbing
fission product isotopes. Progress also depends on optimizing the procedure for establishing the
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd Finnish National Report as referred to in Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd Finnish National Report as referred to in Article 32 of the Convention
The Joint Convention on the Safety of Spent Fuel<br/>Management and on the Safety of Radioactive<br/>Waste Management was adopted on 29 September<br/>1997 in the Vienna Diplomatic Conference. Finland<br/>signed the Convention on 2 October 1997 and deposited<br/>the tools of acceptance on 10 February<br/>2000. The Convention entered into force on 18 June<br/>2001.<br/>The fulfilment of the obligations of the<br/>Convention and the developments after the second<br/>Review Meeting are assessed in this report.
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
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
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.
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
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
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.
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
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
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.
United Arab Emirates, First National Report on Compliance with the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
United Arab Emirates, First National Report on Compliance with the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
A.1 This is the United Arab Emirates (UAE) first national report on compliance with the obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention). The UAE deposited its instrument of accession to the Joint Convention on 31 July 2009 and under Article (40) the Joint Convention entered into force for the UAE 90 days later on 29 October 2009. A.2 The report describes the basic policy and legal framework being established by the UAE for spent fuel management and 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
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
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).
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report from Estonia, Third Review Meeting
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report from Estonia, Third Review Meeting
This Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 29 September 1997 in Vienna diplomatic Conference. Estonia signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management 05 January 2001. Estonian Parliament ratified the convention 19 October 2005. Estonia deposited the instrument of accession to the joint Convention on 03 February 2006. The convention entered into force 04 May 2006.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of the Kingdom of the Netherlands, First Review Conference
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report of the Kingdom of the Netherlands, First Review Conference
On 10 March 1999, The Netherlands signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, which was subsequently formally ratified on 26 April 2000 and entered into force on 18 June 2001. The Joint Convention obliges each contracting party to apply widely recognized principles and tools in order to achieve and maintain high standards of safety during management of spent fuel and radioactive waste.
Questions and Answers - USA - Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Questions and Answers - USA - Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Questions and Answers - USA - Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel
Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel
Fission Product Experiment Program: Validation and Calculational Analysis
Fission Product Experiment Program: Validation and Calculational Analysis
From 1998 to 2004, a series of critical experiments referred to as the fission product (FP) experimental program was performed at the Commissariat à l'Energie Atomique Valduc research facility. The experiments were designed by Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and funded by AREVA NC and IRSN within the French program supporting development of a technical basis for burnup credit validation.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
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).
Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit
Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit
This report proposes and documents a computational benchmark for the estimation of the
additional reactivity margin available in spent nuclear fuel (SNF) from fission products and minor
actinides in a burnup-credit storage/transport environment, relative to SNF compositions
containing only the major actinides. The benchmark problem/configuration is a generic burnupcredit
cask designed to hold 68 boiling water reactor (BWR) spent nuclear fuel assemblies. The
purpose of this computational benchmark is to provide a reference configuration for the
Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty
Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty
Analytical methods, described in this report, are used to
systematically determine experimental fuel sub-batch
reactivities as a function of burnup. Fuel sub-batch reactivities
are inferred using more than 600 in-core pressurized water
reactor (PWR) flux maps taken during 44 cycles of operation
at the Catawba and McGuire nuclear power plants. The
analytical methods systematically search for fuel sub-batch
reactivities that minimize differences between measured and
computed reaction rates, using Studsvik Scandpower’s
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report