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EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages
EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages
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
Isotopic Generation and Verification of the PWR Application Model
Isotopic Generation and Verification of the PWR Application Model
The objective of this calculation is to establish an isotopic database to represent commercial spent nuclear fuel (CSNF) from pressurized water reactors (PWRs) in criticality analyses performed for the proposed Monitored Geologic Repository at Yucca Mountain, Nevada. Confirmation of the conservatism with respect to criticality in the isotopic concentration values represented by this isotopic database is performed as described in Section 3.5.3.1.2 of the Disposal Criticality Analysis Methodology Topical Report (YMP 2000).
Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package
Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package
The purpose of this calculation is to evaluate the transient behavior and consequences of a worst- case criticality event involving intact pressurized water reactor (PWR) mixed-oxide (MOX) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR waste package (WP). This calculation will provide information necessary for demonstrating that the consequences of a worst-case criticality event involving intact PWR MOX SNF are insignificant in their effect on the overall radioisotopic inventory and on the integrity of the repository.
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to criticality. The effect that the low burnup regions near the ends of spent fuel have on system reactivity is termed the “end-effect”. This calculation will quantify the end-effects associated with Pressurized Water Reactor (PWR) fuel assemblies emplaced in a hypothetical 21 PWR waste package.
Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package
Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package
The purpose of this analysis is to evaluate the transient behavior and consequences of a worst case criticality event involving intact pressurized water reactor (PWR) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR assembly waste package (WP). The objective of this analysis is to demonstrate that the consequences of a worst case criticality event involving intact PWR SNF are insignificant in their effect on the overall radioisotopic inventory in a WP. An internal WP criticality is modeled in a manner analogous to transient phenomena in a nuclear reactor core.
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to
3rd WP Probabilistic Criticality Analysis: Methodology for Basket Degradation with Application to Commercial SNF
3rd WP Probabilistic Criticality Analysis: Methodology for Basket Degradation with Application to Commercial SNF
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to describe the latest version of the probabilistic criticality analysis methodology and its application to the entire commercial waste stream of commercial pressurized water reactor (PWR) spent nuclear fuel (SNF) expected to be emplaced in the repository. The purpose of this particular application is to evaluate the 21 assembly PWR absorber plate waste package (WP) with respect to degradedmode criticality performance.
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.