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Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation
Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation
Pressurized water reactor (PWR) burnup credit validation is
demonstrated using the benchmarks for quantifying fuel reactivity
decrements, published as Benchmarks for Quantifying Fuel Reactivity
Depletion Uncertainty, Electric Power Research Institute (EPRI)
report 1022909. This demonstration uses the depletion module
TRITON (Transport Rigor Implemented with Time-Dependent
Operation for Neutronic Depletion) available in the SCALE 6.1
(Standardized Computer Analyses for Licensing Evaluations) code
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
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.
Environmental Permitting Guidance Radioactive Substances Regulation For the Environmental Permitting (England and Wales) Regulations 2010

Environmental Permitting Guidance Radioactive Substances Regulation For the Environmental Permitting (England and Wales) Regulations 2010
This guidance is aimed at helping readers understand the permitting and other requirements specific to Radioactive Substances Regulation (RSR). The RSR regime covers
- more than one European Directive, parts of which are also implemented by other regulatory regimes which, to an extent, complement RSR;
- various Government policies and strategies; and
HTC Experimental Program: Validation and Calculational Analysis
HTC Experimental Program: Validation and Calculational Analysis
In the 1980s a series of the Haut Taux de Combustion (HTC) critical experiments with fuel pins in a water-moderated lattice was conducted at the Apparatus B experimental facility in Valduc (Commissariat à l'Energie Atomique, France) with the support of the Institut de Radioprotection et de Sûreté Nucléaire and AREVA NC. Four series of experiments were designed to assess profit associated with actinide-only burnup credit in the criticality safety evaluation for fuel handling, pool storage, and spent-fuel cask conditions.
Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel
Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel
The purpose of this calculation report, Range of Applicability and Bias Determination for Postclosure
Criticality of Commercial Spent Nuclear Fuel, is to validate the computational method used to perform
postclosure criticality calculations. The validation process applies the criticality analysis methodology
approach documented in Section 3.5 of the Disposal Criticality Analysis Methodology Topical Report.1
The application systems for this validation consist of waste packages containing transport, aging, and
Evaluation of the French Haut Taux de Combustion (HTC) Critical Experiment Data
Evaluation of the French Haut Taux de Combustion (HTC) Critical Experiment Data
In the 1980s, a series of critical experiments referred to as the Haut Taux de Combustion (HTC)
experiments was conducted by the Institut de Radioprotection et de Sûreté Nucléaire (IRSN) at the
experimental criticality facility in Valduc, France. The plutonium-to- uranium ratio and the isotopic
compositions of both the uranium and plutonium used in the simulated fuel rods were designed to be
similar to what would be found in a typical pressurized-water reactor fuel assembly that initially had an
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
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-
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)
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
WP 2 Appendix 6 Public and Stakeholders Engagement in the Decision-processes of the Committee on Radioactive Waste Management (CoRWM)
WP 2 Appendix 6 Public and Stakeholders Engagement in the Decision-processes of the Committee on Radioactive Waste Management (CoRWM)
The activities of the UK Committee on Radioactive Waste Management (CoRWM) were identified by WP2 stakeholders as of particular interest in the context of exploring the scope for local actors’ influence on a major national decision making process. Thus, they agreed to focus on this Committee as one of the case studies.
Defining an Affected Community
Defining an Affected Community
The long term management of radioactive waste creates site specific issues associated with storage and disposal facilities and the transportation of radioactive material. The resolution of these, sometimes controversial, issues requires an appreciation and accommodation of community issues and an essential element of these activities is an approach to defining the extent and composition of communities affected by radioactive waste management. <br><br>A community perspective can provide an insight into the relationship between a facility and people living in its vicinity.
Aspects of Governance in the Practical Implementation of the Concept of Reversibility for Deep Geological Disposal
Aspects of Governance in the Practical Implementation of the Concept of Reversibility for Deep Geological Disposal
The European project COWAM in Practice (CIP) was aimed to lead for three years (2007-2009) a process of monitoring, analyzing and evaluating the governance linked with radioactive waste management. This project, in cooperation with a research group and stakeholders, was conducted in parallel in 5 European countries (Spain, France, United Kingdom, Romania, Slovenia).
POSITION PAPER ON PUBLIC AND STAKEHOLDER ENGAGEMENT
POSITION PAPER ON PUBLIC AND STAKEHOLDER ENGAGEMENT
This document does not present the views of the Committee on Radioactive Waste Management nor can it be taken to present the views of its author. It is a draft paper to inform Committee deliberations and both the author and the whole Committee may adopt different views and draw entirely different conclusions after further consideration and debate
POSITION PAPER ON PUBLIC AND STAKEHOLDER ENGAGEMENT for Discussion and Decision
POSITION PAPER ON PUBLIC AND STAKEHOLDER ENGAGEMENT for Discussion and Decision
This document does not present the views of the Committee on Radioactive Waste Management nor can it be taken to present the views of its author. It is a draft paper to inform Committee deliberations and both the author and the whole Committee may adopt different views and draw entirely different conclusions after further consideration and debate
Funding Issues
Funding Issues
The purpose of this paper is to allow CoRWM to consider the range of issues concerning funding of a geological disposal facility (GDF) and of safe and secure interim storage, to note current developments and to identify issues that require further consideration or where CORWM should develop advice to Government.
Geological Disposal of Higher Activity Radioactive Wastes
Geological Disposal of Higher Activity Radioactive Wastes
This is one of three CoRWM reports to Government in 2009. The reports are about: <br><br>_ interim storage of higher activity wastes (including waste conditioning, packaging and transport, and the management of materials that may be declared to be wastes) <br>_ the implementation of geological disposal of higher activity wastes (this report) <br>_ research and development for interim storage and geological disposal. <br><br>The reports cover the three strands of the Government_s Managing Radioactive Waste Safely programme.
CORWM’S ADVICE TO GOVERNMENT ON OPTIONS FOR THE ACCELERATION OF THE IMPLEMENTATION OF GEOLOGICAL DISPOSAL
CORWM’S ADVICE TO GOVERNMENT ON OPTIONS FOR THE ACCELERATION OF THE IMPLEMENTATION OF GEOLOGICAL DISPOSAL
This paper is a response to a request from the Department of Energy and Climate Change (DECC) for CoRWM’s advice on the 2011 review of options for accelerating the geological disposal programme carried out by the Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA).
D1-12 Prospective Case Study - United Kingdom
D1-12 Prospective Case Study - United Kingdom
Managing our Radioactive Waste Safely: CoRWM's recommendations to Government
Managing our Radioactive Waste Safely: CoRWM's recommendations to Government
The Committee on Radioactive Waste Management was asked by Government in 2003 to make recommendations for the long-term management of the UK’s higher activity wastes that would both protect the public and the environment, and inspire public confidence. To do this, we have combined a technical assessment of options with ethical considerations, examination of overseas experience and a wide-ranging programme of engagement both with the public and with interested parties (stakeholders). I am happy to present our recommendations in the pages that follow.
INTERIM STORAGE OF HIGHER ACTIVITY WASTES AND THE MANAGEMENT OF SPENT FUELS, PLUTONIUM AND URANIUM
INTERIM STORAGE OF HIGHER ACTIVITY WASTES AND THE MANAGEMENT OF SPENT FUELS, PLUTONIUM AND URANIUM
CoRWM’s remit is to provide independent scrutiny and advice to Government on the long-term management, including storage and disposal, of radioactive wastes and materials that may be declared to be wastes. This is the first of three reports to be produced in 2009 that describes the results of the Committee’s scrutiny work in 2008 and the first part of 2009 and provides advice to Government.
Committee on Radioactive Waste Management Seventh Annual Report
Committee on Radioactive Waste Management Seventh Annual Report
This is the seventh CoRWM Annual Report. It summarises the outcomes of CoRWM’s scrutiny and advice work during the year. It also contains the Committee’s views on the current status of arrangements and plans for the long-term management of higher activity radioactive wastes in the UK. All the Committee Members have contributed to this Report and I am grateful to Marion Hill and the Secretariat for all their hard work in compiling it.
Committee on Radioactive Waste Management Eighth Annual Report
Committee on Radioactive Waste Management Eighth Annual Report
This is the eighth CoRWM Annual Report. It summarises CoRWM’s scrutiny and advice for the financial year ending on 31 March 2012. It also contains the Committee’s views on the status of arrangements and plans for the long-term management of higher activity radioactive wastes in the UK at June 2012.
ASSESSMENT OF THE GENERIC DISPOSAL SYSTEM SAFETY CASE for Information
ASSESSMENT OF THE GENERIC DISPOSAL SYSTEM SAFETY CASE for Information
The Committee on Radioactive Waste Management (CoRWM) has carried out an assessment of the generic Disposal System Safety Case (gDSSC) published by the Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) in February 2011. The assessment covered the whole suite of gDSSC documents, and related RWMD reports on research and development (R&D) and site characterisation.