Category of Content

Siting Experience Documents Only

Publication Date

Country

Keywords

Displaying 1 - 25 of 47

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

Presentation made at IAEA on A Unified Spent Nuclear Fuel (SNF) Database and Analysis System

Presentation made at IAEA on A Unified Spent Nuclear Fuel (SNF) Database and Analysis System

Author(s)
Scaglione
Publication Date

Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.

iaea snf unified database

Management of Uncertainty in Safety Cases and the Role of Risk - Workshop Proceedings

SED Publication Type

Management of Uncertainty in Safety Cases and the Role of Risk - Workshop Proceedings

Author
Nuclear Energy Agency
Publication Date

The development of radioactive waste repositories involves consideration of how the waste and the
engineered barrier systems will evolve, as well as the interactions between these and, often relatively
complex, natural systems. The timescales that must be considered are much longer than the timescales
that can be studied in the laboratory or during site characterisation. These and other factors can lead to
various types of uncertainty (on scenarios, models and parameters) in the assessment of long-term,

disposal repository sweden safety waste management risk assessment

Assessment of Benefits for Extended Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA

Assessment of Benefits for Extended Burnup Credit in Transporting PWR Spent Nuclear Fuel in the USA

Author(s)
Wagner, J. C. ,
Parks, C. V. ,
Mueller, D. E.
Publication Date

This paper presents an assessment of the benefits for extended burnup credit in transporting
pressurized-water-reactor (PWR) spent nuclear fuel (SNF) in the United States. A prototypic 32-
assembly cask and the current regulatory guidance were used as bases for this assessment. By
comparing recently released PWR discharge data with actinide-only-based loading curves, this
evaluation shows that additional negative reactivity (through either increased credit for fuel burnup or

burnup credit criticality analysis iaea general

Internationalization of the Nuclear Fuel Cycle: Goals, Strategies, and Challenges

Internationalization of the Nuclear Fuel Cycle: Goals, Strategies, and Challenges

Author(s)
National Academy of Sciences
Publication Date

Following the proposals for nuclear fuel assurance of International Atomic Energy
Agency (IAEA) Director General Mohamed ElBaradei, former Russian President Vladimir V.
Putin, and U.S. President George W. Bush, joint committees of the Russian Academy of
Sciences (RAS) and the U.S. National Academies (NAS) were formed to address these and other
fuel assurance concepts and their links to nonproliferation goals. The joint committees also
addressed many technology issues relating to the fuel assurance concepts. This report provides

iaea nuclear fuel cycle gnep blue ribbon commission nonproliferation global nuclear energy partnership

U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks

U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks

Author(s)
Withee, C. J. ,
Wagner, J. C. ,
Parks, C. V.
Publication Date

In July 1999, the U.S. Nuclear Regulatory Commission (NRC) Spent Fuel Project Office
(SFPO) issued Interim Staff Guidance 8 Revision 1 (ISG8R1) to provide recommendations for the use
of burnup credit in storage and transport of pressurized-water reactor (PWR) spent fuel. Subsequent to
the issuance of ISG8R1, the NRC Office of Regulatory Research (RES) has directed an effort to
investigate the technical basis for extending the criteria and recommendations of ISG8R1 to allow

burnup credit criticality analysis iaea-tecdoc-1547 iaea regulations

A Coordinated U.S. Program to Address Full Burnup Credit in Transport and Storage Casks

A Coordinated U.S. Program to Address Full Burnup Credit in Transport and Storage Casks

Author(s)
Parks, C. V. ,
Wagner, J. C.
Publication Date

The benefits of burnup credit and the technical issues associated with utilizing burnup credit in spent
nuclear fuel (SNF) casks have been studied in the United States for almost two decades. The issuance of the
U.S. Nuclear Regulatory Commission (NRC) staff guidance for actinide-only burnup credit in 2002 was a
significant step toward providing a regulatory framework for using burnup credit in transport casks. However,
adherence to the current regulatory guidance (e.g., limit credit to actinides) enables only about 30% of the existing

burnup credit criticality analysis iaea-tecdoc-1547 iaea general

Presentation made at IAEA on the NFST Execution Strategy Analysis Capability

Presentation made at IAEA on the NFST Execution Strategy Analysis Capability

Author(s)
Ralph Stoll ,
Mark Nutt ,
Natalia Saraeva ,
Alan Keizur ,
Alyssa Neir
Publication Date

Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.

iaea execution strategy analysis

Presentation made at IAEA on Interim Storage Facility Design Concepts

Presentation made at IAEA on Interim Storage Facility Design Concepts

Author(s)
Joe Carter
Publication Date

Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.

iaea design concepts interim storage facility

Presentation made at IAEA on Dry Storage System Aging Management

Presentation made at IAEA on Dry Storage System Aging Management

Author(s)
Yung Liu
Publication Date

Presentation made at International Conference on The Management of Spent Nuclear Fuel from Nuclear Power Reactors, An Integrated approach to the Back-End of the Fuel Cycle (IAEA-CN-226). The purpose of the conference was to highlight the importance of an integrated long-term approach to the management of spent fuel from nuclear power reactors.

dry cask storage iaea aging management

Long-term Safety for KBS-3 Repositories at Forsmark and Laxemar—a First Evaluation: Main Report of the SR-Can project

Long-term Safety for KBS-3 Repositories at Forsmark and Laxemar—a First Evaluation: Main Report of the SR-Can project

Author(s)
Swedish Nuclear Fuel and Waste Management Co
Publication Date

This document is the main report from the safety assessment project SR-Can. The SR-Can project is a preparatory stage for the SR-Site assessment, the report that will be used in support of SKB’s application for a final repository. The purposes of the safety assessment SR-Can are the following:
1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant.

disposal spent fuel repository sweden used fuel

Treatment and final disposal of nuclear waste: Programme for encapsulation, deep geological disposal, and research, development and demonstration: Ch 6 - App 1

SED Publication Type

Treatment and final disposal of nuclear waste: Programme for encapsulation, deep geological disposal, and research, development and demonstration: Ch 6 - App 1

Author
SKB
Publication Date

In RD&D-Programme 92, SKB presented a partially new strategy for its activities. The new strategy entailed a focusing and concentration on the implementation of deep disposal of a limited quantity (about 800 tonnes) of encapsulated spent nuclear fuel during the coming 20-year period. Following this initial deposition, the results of the work will be evaluated, and only then will a decision be taken as to how and when regular deposition of the main body of the fuel and other long-lived nuclear waste will take place.

disposal sweden siting skb

Possible Strategies for Geoscientific Classification for High-Level Waste Repository Site Selection

SED Publication Type

Possible Strategies for Geoscientific Classification for High-Level Waste Repository Site Selection

Author
Lars Rosén ,
Gunnar Gustafson ,
SKB
Publication Date

This work was performed to suggest possible strategies for geoscientific classifications in the siting process of a high-level repository. To develop a feasible method for geoscientific classifications, a number of factors of a philosophical character, related to the purpose of the classifications, need to be accounted for. Many different approaches can be visualized, and this report was not intended to present a complete classification methodology.

repository sweden geology siting skb tr-93-12

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

SED Publication Type

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

Author
Swedish Ministry of the Environment
Publication Date

Spent fuel in Sweden emanates mainly from four commercial nuclear power plants. In addition there is one material testing reactor and one research reactor. The radioactive waste originates from the nuclear power industry as well as medical use, industry, research and consumer products.

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

Stakeholder Dialogue: Experience and Analysis

SED Publication Type

Stakeholder Dialogue: Experience and Analysis

Author
RISCOM
Publication Date

The report begins with a consideration of the factors which have led to a growth in the use of dialogue processes, a clarification of key concepts and a classification of dialogue processes. A description of recent and current activities in Europe and North America is followed by discussion of the relationship of processes and contexts. This then leads to an identification of the key aims and evaluation criteria which will be used in the design of dialogue processes to be conducted in subsequent phases of the project.

sweden waste management siting united kingdom public policy wp4

Geosphere Performance Indices: Comparative measures for site selection and safety assesment of deep waste repositories

SED Publication Type

Geosphere Performance Indices: Comparative measures for site selection and safety assesment of deep waste repositories

Author
Vladimir Cvetkovic ,
Jan-Olof Selroos ,
SKB
Publication Date

The concept of Geosphere Perfonnance Indices (GPis) is proposed. The &quot;performance&quot;<br/>refers to the geosphere&#39;s capacity to retain/contain radionuclides in the event of their accidental<br/>release at some point in time. The GPis are based on the Lagrangian stochastic-analytical<br/>framework for transport in the subsurface and are believed to render useful tools in performance<br/>assessment studies in general and in the site selection process in particular.

sweden siting performance assessment r-99-01 geosphere retention stochastic transport modelling

RD&D Programme 2007: Programme for research, development, and demonstration of methods for the management and disposal of nuclear waste

SED Publication Type

RD&D Programme 2007: Programme for research, development, and demonstration of methods for the management and disposal of nuclear waste

Author
SKB
Publication Date

RD&D Programme 2007 presents SKB’s plans for research, development and demonstration during<br/>the period 2008–2013. The plans for the first three-year period are for natural reasons more detailed<br/>than those for the next one.

spent fuel public perception repository sweden waste management siting skb tr-07-12 used fuel

Handling and final disposal of nuclear waste: Hard Rock Laboratory

SED Publication Type

Handling and final disposal of nuclear waste: Hard Rock Laboratory

Author
SKB
Publication Date

In an international perspective, Sweden has come a long way in the development of safe and accepted systems for the management and disposal of radioactive waste. <br/><br/>A complete system for sea transport of spent nuclear fuel from the twelve Swedish nuclear reactors has been in operation since 1982. The spent nuclear fuel will be stored in CLAB for a period of about 40 years up until final disposal. The facility has been in operation since 1985. A final repository for low- and intermediate-level short-lived waste, SFR, has been in operation since April 1988.

sweden waste management siting hard rock laboratory
Disclaimer: Note that this page contains links to external sites. When leaving the CURIE site, please note that the U.S. Department of Energy and Pacific Northwest National Laboratory do not control or endorse the content or ads on these sites.
Sponsored by: