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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

Radioactive Waste Disposal in Geological Formations International Conference Braunschweig ("City of Science 2007") November 6 – 9, 2007 Proceedings

SED Publication Type

Radioactive Waste Disposal in Geological Formations International Conference Braunschweig ("City of Science 2007") November 6 – 9, 2007 Proceedings

Author
GRS
Publication Date

To solve the still open question of high-level radioactive waste disposal, the countries having made the greatest progress in this
field usually choose to carry out comparing selection procedures including broad involvement of the public. This is a central
result of the “RepoSafe”symposium which took place from November 6 to 9, 2007, in Braunschweig. Within the scope of
this symposium, internationally leading experts, invited by the Federal Office for Radiation Protection (BfS) and Gesellschaft

disposal high level waste radioactive waste waste management germany public meeting

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Report of the Federal Republic of Germany for the Third Review Meeting in May 2009

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Report of the Federal Republic of Germany for the Third Review Meeting in May 2009

Author
Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU), Germany
Publication Date

The Federal Government will continue to meet Germany’s existing international obligations, particularly with regard to fulfilment of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. In submitting this report, Germany is demonstrating its compliance with the Joint Convention and how it ensures the safe operation of facilities for the management of spent fuel and radioactive waste, including the decommissioning of nu-clear installations.

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Report under the Joint Convention by the Government of the Federal Republic of Germany for the Second Review Meeting in May 2006

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Report under the Joint Convention by the Government of the Federal Republic of Germany for the Second Review Meeting in May 2006

Author
Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU), Berlin, Germany
Publication Date

The Federal Government will continue to meet Germany’s existing international obligations, par- ticularly with regard to fulfilment of the Joint Convention. In submitting this report, the Federal Re- public of Germany is demonstrating its compliance with the Joint Convention and ensuring the safe operation of facilities for the management of spent fuel and radioactive waste, including the de- commissioning of nuclear installations. At the same time, there is still a need for future action in order to maintain the required high standards of safety and ensure disposal.

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Report of the Federal Republic of Germany for the Fourth Review Meeting in May 2012

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Report of the Federal Republic of Germany for the Fourth Review Meeting in May 2012

Author
Federal Republic of Germany Federal Ministry for the Environment, Nature Conservation and Nuclear Safety
Publication Date

There are currently nine power reactors in operation in Germany. These are exclusively light-water reactors (seven pressurised water reactors and two boiling water reactors whose fuel assemblies are composed of low-enriched uranium oxide or uranium/plutonium mixed oxide (MOX)).

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Questions and Comments in 2009 on the National Report posed to Germany

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Questions and Comments in 2009 on the National Report posed to Germany

Author
Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU), Germany
Publication Date

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Questions and Comments in 2009 on the National Report posed to Germany

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

Identifying remaining socio-technical challenges at the national level: Germany

SED Publication Type

Identifying remaining socio-technical challenges at the national level: Germany

Author
Anne Minhans ,
Beate Kallenbach-Herbert
Publication Date

This report was written within the EU-project InSOTEC (www.insotec.eu) which aims to generate a better understanding of the complex interplay between the technical and the social in radioactive waste management and, in particular, in the design and implementation of geological disposal. In a first step 13 countries have been analysed in order to identify prevailing socio-technical challenges.

siting germany wp 1 ms 7
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