Category of Content
Siting Experience Documents Only
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Country
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OECD/NEA: Norway
OECD/NEA: Norway
Identifying remaining socio-technical challenges at the national level: Switzerland
Identifying remaining socio-technical challenges at the national level: Switzerland
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.
Radioactive Waste Management and Decommissioning in Canada
Radioactive Waste Management and Decommissioning in Canada
Radioactive Waste Management and Decommissioning in Czech Republic
Radioactive Waste Management and Decommissioning in Czech Republic
Radioactive Waste Management and Decommissioning in Italy
Radioactive Waste Management and Decommissioning in Italy
Radioactive Waste Management and Decommissioning in the United Kingdom
Radioactive Waste Management and Decommissioning in the United Kingdom
Radioactive Waste Management and Decommissioning in Finland
Radioactive Waste Management and Decommissioning in Finland
Radioactive Waste Management and Decommissioning in Sweden
Radioactive Waste Management and Decommissioning in Sweden
OECD/NEA: Slovak Republic
OECD/NEA: Slovak Republic
OECD/NEA: Spain
OECD/NEA: Spain
OECD/NEA: Korea
OECD/NEA: Korea
OECD/NEA: Sweden
OECD/NEA: Sweden
OECD/NEA: Hungary
OECD/NEA: Hungary
Radioactive Waste Management and Decommissioning in Korea
Radioactive Waste Management and Decommissioning in Korea
OECD/NEA: Finland
OECD/NEA: Finland
OECD/NEA: Netherlands
OECD/NEA: Netherlands
OECD/NEA: France
OECD/NEA: France
OECD/NEA: Czech Republic
OECD/NEA: Czech Republic
OECD/NEA: Mexico
OECD/NEA: Mexico
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
This report discusses the status of the commercial spent nuclear fuel (SNF) inventory in the United States, at both decommissioned and operating commercial nuclear power reactor sites; summarizes the contractual arrangement the government and utilities have under the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (10 CFR Part 961) (Standard Contract), related litigation, and the financial liabilities resulting from the Department’s delay in performance under these contracts; provides a history of interim storage policy as it relates to commercial SN
From Integral Experiments to Nuclear Data Improvement
From Integral Experiments to Nuclear Data Improvement
Target accuracy on LWR neutronics parameters is 2 to 5 times lower than the a priori uncertainty (1σ)
due to nuclear data. This paper summarizes the experimental facilities and the integral measurements that are required
for code qualification. The rigorous use of integral information through trend analysis method is described. Trends
on JEF2 data from Keff measurements and P.I.Es are presented. These trends were accounted for in the new JEFF3
evaluations. The role of fundamental experiments, such as worth measurement of separated isotopes, is emphasized.
Spent Nuclear Fuel: Accumulating Quantities at Commercial Reactors Present Storage and Other Challenges
Spent Nuclear Fuel: Accumulating Quantities at Commercial Reactors Present Storage and Other Challenges
The amount of spent fuel stored on-site at commercial nuclear reactors will continue to accumulate—increasing by about 2,000 metric tons per year and likely more than doubling to about 140,000 metric tons—before it can be moved off-site, because storage or disposal facilities may take decades to develop. In examining centralized storage or permanent disposal options, GAO found that new facilities may take from 15 to 40 years before they are ready to begin accepting spent fuel. Once an off-site facility is available, it will take several more decades to ship spent fuel to that facility.
SCALE-4 Analysis of Pressurized Water REactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
SCALE-4 Analysis of Pressurized Water REactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor
(AFR) criticality safety analyses be validated against experimental measurements. If credit for the
negative reactivity of the depleted (or spent) fuel isotopics is desired, it is necessary to benchmark
computational methods against spent fuel critical configurations. This report summarizes a portion
of the ongoing effort to benchmark AFR criticality analysis methods using selected critical
configurations from commercial pressurized-water reactors (PWR).
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
This paper presents an evaluation of the amount of burnup credit needed for high-density casks to
transport the current U.S. inventory of commercial spent nuclear fuel (SNF) assemblies. A prototypic
32-assembly cask and the current regulatory guidance were used as bases for this evaluation.
By comparing actual pressurized-water-reactor (PWR) discharge data (i.e., fuel burnup and initial
enrichment specifications for fuel assemblies discharged from U.S. PWRs) with actinide-only-based