Category of Content

Siting Experience Documents Only

Publication Date

Country

Keywords

Displaying 1 - 16 of 16

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

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

Local Liaison Committees and National Association of Local Liaison Committees: the French experience

SED Publication Type

Local Liaison Committees and National Association of Local Liaison Committees: the French experience

Author
COWAM
Publication Date

In the context of the governance of nuclear activities, especially in the field of the radioactive waste management, the self-structuring of civil society is a necessary condition of the citizens’ action. The experience of French “Commissions Locales d’Information” (CLIs) and their national federation the “Association Nationale des Commissions Locales d’Information” (ANCLI) represent an interesting and original example of local actors empowerment. In France, Local Information Commissions (CLI) are attached to most of the nuclear sites.

public perception france siting community outreach fp6/036455 d2-3/b

LONG-TERM ENVIRONMENTAL SURVEILLANCE AND HEALTH RISK ASSESSMENT

SED Publication Type

LONG-TERM ENVIRONMENTAL SURVEILLANCE AND HEALTH RISK ASSESSMENT

Author
COWAM
Publication Date

This research brief is addressing the governance issues associated with the practical implementation of long-term environmental surveillance systems on the one hand, and the health impact assessment related to radioactive waste disposal installations on the other hand. Based on feedback experiences associated with the surveillance of nuclear installations, the analysis is focused on governance stakes (how to involve local stakeholders, which information is meaningful, how to transfer the surveillance system between generations...) according to the expectations of the local stakeholders.

waste management siting fp6/036455 health risks environmental surveillance d2-5/e

Structuring local communities and development of local democracy for engagement in Radioactive Waste Management governance

SED Publication Type

Structuring local communities and development of local democracy for engagement in Radioactive Waste Management governance

Author
COWAM
Publication Date

Engagement of local communities and actors in the decision-making processes is traditionally motivated by the fact they are impacted by the decision taken. This traditional rationale for engagement of local communities and actors is driven not only by ethical concerns, but also by the necessity for public authorities to comply with national or international legal frameworks which give to stakeholders, concerned by a decision having environmental impacts, the right to be informed and participate in the decision (e.g.

siting fp6/036455 d2-5/d

Brief 3: Community Benefits and Support Packages

SED Publication Type

Brief 3: Community Benefits and Support Packages

Author
COWAM
Publication Date

The Brief introduces the concept of ‘Community Benefit and Support Packages’ following requests from a number of National Stakeholder Groups (NSGs) for more information on this issue. During the development of the Brief presentations were made to NSG meetings in Romania (June 2009), Slovenia (October 2009) and the UK (September 2008, September 2009). Some information specific to the UK from the Brief was also presented in Spain (November 2008).

siting fp6/036455 d2-5 b community benefit
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: