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OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask

OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask

Author(s)
Nouri, A.
Publication Date
The OECD/NEA “Burn-up Credit Criticality Benchmark” working group has studied the effect of axial burn-up profile on the criticality of a realistic PWR spent fuel transport cask (Phase II-B). The final results of this benchmark are presented and analysed in this report. Nine basic cases and two additional accident configurations were considered with the following varying parameters: burn-up (0 GWd/t for fresh fuel, 30 and 50 GWd/t), fuel composition (actinides only and actinides with fifteen fission products), axial burn-up discretisation (1 or 9 zones).
criticality pwr fuel transport cask end effect source convergence burnup axial burnup profile

PWR Axial Burnup Profile Analysis

PWR Axial Burnup Profile Analysis

Author(s)
OCRWM
Publication Date

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 commercial spent nuclear fuel end effect storage axial burnup profile isotopic concentrations 21 pwr waste package pwr snf cal-dsu-nu-000012

BWR Axial Profile

BWR Axial Profile

Author(s)
OCRWM
Publication Date

The purpose of this calculation is to develop axial profiles for estimating the axial variation in burnup of a boiling water reactor (BWR) assembly spent nuclear fuel (SNF) given the average burnup of an assembly. A discharged fuel assembly typically exhibits higher burnup in the center and lower burnup at the ends of the assembly. Criticality safety analyses taking credit for SNF burnup must account for axially varying burnup relative to calculations based on uniformly distributed assembly average burnup due to the under-burned tips.

criticality end effect axial burnup profile bwr snf cal-dsu-nu-000005

PWR Axial Burnup Profile Analysis

PWR Axial Burnup Profile Analysis

Author(s)
John M. Scaglione
Publication Date

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

burnup credit commercial spent nuclear fuel axial burnup profile 21 pwr waste package pwr snf

PWR Axial Profile Evaluation

PWR Axial Profile Evaluation

Author(s)
Harold Massie
Publication Date

This calculation compares results from criticality evaluations for a 21-assembly pressurized water reactor (PWR) waste package based on 12 axial burnup profile representations for commercial spent nuclear fuel (SNF) assemblies. The burnup profiles encompass the axial variations caused by different fuel assembly irradiation histories in a commercial PWR, including end effects, and the concomitant effect on reactivity in the waste package. The bounding axial burnup profiles in Table T of reference 6.3 are used for this analysis.

waste package mcnp axial burnup profile isotopic concentrations

Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks

Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks

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

In 1999, the United States Nuclear Regulatory Commission (U.S. NRC) initiated a research program
to support the development of technical bases and guidance that would facilitate the implementation of burnup
credit into licensing activities for transport and dry cask storage. This paper reviews the following major areas of
investigation: (1) specification of axial burnup profiles, (2) assumption on cooling time, (3) allowance for
assemblies with fixed and removable neutron absorbers, (4) the need for a burnup margin for fuel with initial

burnup credit dry cask storage transport axial burnup profile

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
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