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Japan’s Spent Fuel and Plutonium Management Challenges
Japan’s Spent Fuel and Plutonium Management Challenges
Japan’s spent fuel management and fuel cycle programs are now at a critical stage. Its first commercial-scale reprocessing plant, at Rokkasho Village, will soon start full-scale operation.
Locating a radioactive waste repository in the ring of fire
Locating a radioactive waste repository in the ring of fire
The scientific, technical, and sociopolitical challenges of finding a secure site for a geological repository for radioactive wastes have created a long and stony path for many countries. Japan carried out many years of research and development before taking its first steps in site selection.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT
This report describes the actions taken in Argentina on the safety of spent fuel management
(SF) and on the safety of radioactive waste management, in order to provide evidence of the
fulfillment of its obligations under the Joint Convention. To facilitate the reading and a better
understanding of this report a summary of those parts of the 1st Report that were considered
necessary have been included.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT
The present National Report describes the actions taken in Argentina on the safety of spent fuel
(SF) management and on the safety of radioactive waste (RW) management, in order to provide
evidence of the fulfilment of the obligations derived from the Joint Convention. To facilitate the
reading and a better understanding, it has been decided to include a summary of those parts of
the two prior National Reports that are considered necessary in order to comply with this
objective.
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report
As outlined in the overall program for high-level waste (HLW) management in Japan, defined by the Atomic Energy Commission (AEC), HWL separated from spent nuclear fuel during reprocessing will be immobilized in a glass matrix and stored for a period of 30 to 50 years to allow cooling; it will then be disposed of in a stable deep geological formation.
Evaluating Site Suitability for a HLW Repository
Evaluating Site Suitability for a HLW Repository
The primary objective of government policy, and of NUMO in implementing this policy, is to
ensure that a repository for Japan’s high-level radioactive waste is located so as to provide
secure isolation of the waste and adequate safety for present and future generations. This
means that the site has to be chosen carefully, taking full account of all its characteristics. In
order to address these characteristics in an orderly and structured manner, we have established
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Supplementary Report Background of Geologic Disposal
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Supplementary Report Background of Geologic Disposal
Radioactive waste is produced from a wide range of human activities. The wastes arising from the nuclear fuel cycle occur as a wide range of materials and in many different physical and chemical forms, contaminated with varying activities of radionuclides. Their common feature is the potential hazard associated with their radioactivity and the need to manage them in such a way as to protect the human environment. The safe disposal of radioactive waste is a key reequirement of the nuclear industry worldwide.
The NUMO Structured Approach to HLW Disposal in Japan
The NUMO Structured Approach to HLW Disposal in Japan
The constraints set by the Japanese HLW disposal programme – particularly associated with
the decision to initiate siting by an open call for volunteers to host a geological repository –
pose particular challenges for repository project management. In order to maintain the
flexibility required to respond to the conditions found at volunteer sites, NUMO has not
published reference designs or site characterisation plans, as is normal for programmes
progressing by site nomination. Instead, we have developed a methodology – the NUMO
Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister
Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister
The purpose of this calculation is to estimate volumes, masses, and surface areas associated with (a) an empty Department of Energy (DOE) 18-inch diameter, 15-ft long spent nuclear fuel (SNF) canister, (b) an empty DOE 24-inch diameter, 15-ft long SNF canister, (c) Shippingport Light Water Breeder Reactor (LWBR) SNF, and (d) the internal basket structure for the 18-in. canister that has been designed specifically to accommodate Seed fuel from the Shippingport LWBR.
Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase I Intact Codisposal Canister
Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase I Intact Codisposal Canister
This evaluation is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to provide analyses of disposal of aluminum (AI)-based Department of Energy-owned research reactor spent nuclear fuel (DOE-SNF) in a codisposal waste package with five canisters of high-level waste (HLW). The analysis was performed in sufficient detail to establish the technical viability of the Al-based DOE-SNF codisposal canister option.
Reversible Bending Fatigue Testing on Zry-4 Surrogate Rods
Reversible Bending Fatigue Testing on Zry-4 Surrogate Rods
Slides - WM2014 Symposia, March 2-6, 2014, Phoenix, AZ
Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase ll Degraded Codisposal Canister Internal Criticality
Evaluation of Codisposal Viability for Aluminum-Clad DOE-Owned Spent Fuel: Phase ll Degraded Codisposal Canister Internal Criticality
This report presents the analysis and conclusions with respect to disposal criticality for canisters containing aluminum-based fuels from research reactors. The analysis has been divided into three phases. Phase I, dealt with breached and flooded waste packages containing relatively intact canisters and intact internal (basket) structures; Phase II, the subject of this report, covers the degradation of the spent nuclear fuel (SNF) and structures internal to the codisposal waste package including high level waste (HLW), canisters, and criticality control material.
TEV Collision with an Emplaced 5-DHLW/DOE SNF Short Co-Disposal Waste Package
TEV Collision with an Emplaced 5-DHLW/DOE SNF Short Co-Disposal Waste Package
The objective of this calculation is to determine the structural response of the 5-DHLW/DOE (Defense High Level Waste/Department of Energy) SNF (Spent Nuclear Fuel) Short Co-disposal Waste Package (WP) when subjected (while in the horizontal orientation emplaced in the drift) to a collision by a loaded (with WP) Transport and Emplacement Vehicle (TEV) due to an over-run. The scope of this calculation is limited to reporting the calculation results in terms of maximum total stress intensities (Sis) in the outer corrosion barrier (dCB).
UFD Storage and Transportation - Transportation Working Group Report
UFD Storage and Transportation - Transportation Working Group Report
The Used Fuel Disposition (UFD) Transportation Task commenced in October 2010. As its first task, Pacific Northwest National Laboratory (PNNL) compiled a list of structures, systems, and components (SSCs) of transportation systems and their possible degradation mechanisms during extended storage. The list of SSCs and the associated degradation mechanisms [known as features, events, and processes (FEPs)] were based on the list of used nuclear fuel (UNF) storage system SSCs and degradation mechanisms developed by the UFD Storage Task (Hanson et al. 2011).
NUREG-1768 United States Nuclear Regulatory Commisssion Package Performance Study Test Protocals
NUREG-1768 United States Nuclear Regulatory Commisssion Package Performance Study Test Protocals
This test protocols report presents the NRC staff’s preliminary plans for an experimental phase of the Package Performance Study (PPS), which is examining the response of transportation casks to extreme transportation accident conditions. The staff proposes to conduct tests of full-scale rail and full-scale truck casks including a high-speed impact with an unyielding surface followed by an extreme fire test. The NRC has a contract in place with Sandia National Laboratories (SNL) to conduct the impact and fire tests and to carry out a series of analyses to support the test program.
Gap Analysis to Support Extended Storage of Used Nuclear Fuel
Gap Analysis to Support Extended Storage of Used Nuclear Fuel
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<p><span style="font-size: 12.000000pt; font-family: 'TimesNewRomanPSMT'">This report fulfills the M1 milestone M11UF041401, “Storage R&D Opportunities Report” under Work Package Number FTPN11UF0414. </span></p>
SITING PROCESS FOR HLW REPOSITORY IN JAPAN
SITING PROCESS FOR HLW REPOSITORY IN JAPAN
In the year 2000, the geological disposal program for high-level radioactive waste in Japan moved from the phase of generic research and development (R&D) into the phase of implementation. Following legislation entitled the “Specified Radioactive Waste Final Disposal Act”, the Nuclear Waste Management Organization of Japan (NUMO) was established as the implementing organization.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report
This report provides - a detailed description of the Austrian policy and the usual practices concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section B); - a detailed description of the Austrian legal regime concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section E).
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3
. On 25 March 1999 the Government of the Czech Republic approved the Joint Convention which came into effect in the Czech Republic on 18 June 2001. In agreement with the obligations resulting from its accession to the Joint Convention the Czech Republic has already drawn the second National Report for the purposes of Review Meetings of the Contracting Parties, which describes the system of spent fuel and radioactive waste management in the scope required by selected articles of the Joint Convention.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, USA National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, USA National Report
The United States of America ratified the “Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management” (Joint Convention) on April 9, 2003. The Joint Convention establishes an international peer review process among Contracting Parties and provides incentives for nations to take appropriate steps to bring their nuclear activities into compliance with general safety standards and practices. This first Review Meeting of the Contracting Parties under the Joint Convention is scheduled to take place in November 2003 in Vienna, Austria.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2nd Finnish National Report as referred to in Article 32 of the Convention
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2nd Finnish National Report as referred to in Article 32 of the Convention
Finland signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management on 2 October 1997 and deposited the tools of acceptance on 10 February 2000. The Convention entered into force on 18 June 2001. The major generators of radioactive waste in Finland are the two nuclear power plants, the Loviisa and Olkiluoto plants. The Loviisa plant has two PWR units, operated by Fortum Power and Heat Oy, and the Olkiluoto plant two BWR units, operated by Teollisuuden Voima Oy.
Second Meeting of the Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Kingdom of Belgium National Report
Second Meeting of the Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Kingdom of Belgium National Report
On 8 December 1997 Belgium has signed the Joint Convention. The Belgian legislator has expressed its consent with the obligations resulting from the Convention via the Law of 2 August 2002. The ratification was obtained on 5 September 2002. The Convention became effective on 4 December 2002, or 90 days after the Ratification Act had been deposited. Belgium belongs to the group of Contracting Parties having at least one operational nuclear generating unit on their territory.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Denmark National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Denmark National Report
Denmark signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management 29 September 1997, the day it opened for signature. The Convention was accepted 3 September 1999 by letter from the Foreign Ministry to the International Atomic Energy Agency (IAEA). Until further notice the Convention does not apply for the autonomous territories Greenland and the Faroe Islands, which both do not possess spent nuclear fuel or radioactive waste. The present report is the Danish National Report for the Second Review Meeting to the Convention.