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Background Paper on Commingling of Defense and Commercial Waste
Background Paper on Commingling of Defense and Commercial Waste
Since a 1985 decision by President Reagan that a separate permanent repository for disposal of
defense high level waste was not required1, DOE has planned for disposal of all high-level waste
and spent fuel from national defense activities and DOE’s own research activities in a repository
for commercial waste developed under the Nuclear Waste Policy Act (NWPA). The Commission
has heard recommendations from some commenters2 that this decision be revisited, or even
DOE SNF Phase I and II Summary Report
DOE SNF Phase I and II Summary Report
There are more than 250 forms of U.S. Department of Energy (DOE)owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program (NSNFP) has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. For each fuel group, a fuel type that represents the characteristics of all fuels in that group has been selected for detailed analysis.
History, Structure and Institutional Overview of the Nuclear Waste Policy Act of 1982
History, Structure and Institutional Overview of the Nuclear Waste Policy Act of 1982
The Nuclear Waste Policy Act of 1982 (NWPA) established a program to deal comprehensively with the waste byproducts of nuclear power generation, as well as defense-related radioactive wastes, if appropriate. Under this program, the federal Department of Energy (DOE) must locate and develop a site for disposal of high-level radioactive wastes in a geologic setting capable of isolating them from adverse public and environmental exposure for at least 10,000 and up to 100,000 years.
Criticality Safety and Shielding Evaluations of the Codisposal Canister in the Five-Pack DHLW Waste Package
Criticality Safety and Shielding Evaluations of the Codisposal Canister in the Five-Pack DHLW Waste Package
The objective of this analysis is to characterize a codisposal canister containing MIT or ORR fuel in the Five-Pack defense high level waste (DHLW) waste package (WP) to demonstrate concept viability related to use in the Mined Geologic Disposal System (MGDS) environment for the postclosure time frame. The purpose of this analysis is to investigate the disposal criticality and shielding issues for the DHLW WP and establish DHLW WP and codisposal canister compatibility with the MGDS, and to provide criticality and shielding evaluations for the preliminary DHLW WP design.
Letter - Request Approval to Establish and Populate the Ad Hoc Subcommittee on Co‐mingling of Defense and Commercial Wastes
Letter - Request Approval to Establish and Populate the Ad Hoc Subcommittee on Co‐mingling of Defense and Commercial Wastes
Dear Tim:
As we work to complete our final recommendations to the Secretary by January 29, 2012,
we have determined that our efforts would be aided by the formation of an ad hoc
subcommittee to investigate the issue of co‐mingling of defense and commercial wastes.
Specifically, the ad hoc subcommittee would review and make a recommendation to the
Commission on the issue of whether the 1985 Presidential decision to co‐mingle defense
and commercial wastes for disposal should be revisited in light of changes that have
Co-Mingled and Defense-Only Repositories
Co-Mingled and Defense-Only Repositories
At the request of the staff to the Blue Ribbon Commission on America’s Nuclear Future (“BRC”), we have reviewed the following questions:
1. Is there legal authority for DOE or any other entity to undertake to site a repository for “co-mingled” nuclear materials (i.e., civilian and defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW)) at any site other than Yucca Mountain?
Disposal Criticality Analysis for Aluminum-based Fuel in a Codisposal Waste Package - ORR and MIT SNF - Phase II
Disposal Criticality Analysis for Aluminum-based Fuel in a Codisposal Waste Package - ORR and MIT SNF - Phase II
The objective of this analysis is to characterize the criticality safety aspects of a degraded Department of Energy spent nuclear fuel (DOESNF) canister containing Masachusetts Institute of Technology (MIT) or Oak Ridge Research (ORR) fuel in the Five Pack defense high level waste (DHLW) waste package to demonstrate concept viability related to use in the Minded Geologic Disposal System (MGDS) environment for the postclosure time frame.
Letter - Approval of Request to Establish and Populate an Ad Hoc Subcommittee on the Co-Mingling of Defense and Commercial Waste
Letter - Approval of Request to Establish and Populate an Ad Hoc Subcommittee on the Co-Mingling of Defense and Commercial Waste
Gentlemen,
In accordance with the charter of the Blue Ribbon Commission on America's Nuclear Future and as the Secretary's designee, I approve your request to establish an ad hoc subcommittee to review and make a recommendation to the Commission regarding the co-mingling of defense and commercial waste.
This letter also serves to appoint Dr. Allison Macfarlane as the chair of the subcommittee and the membership of the subcommittee as identified in your letter to me dated October 31, 2011.
Criticality Evaluation of Plutonium Disposition Ceramic Waste Form: Degraded Mode
Criticality Evaluation of Plutonium Disposition Ceramic Waste Form: Degraded Mode
Thep purpose of this calculation is to perform degraded mode criticality evaluations of plutonium disposed in a ceramic waste form and emplaced in a Monitored geologic Repository (MGR). A 5 Defense High-Level Waste (DHLW) Canister Waste Package (WP) design, incorporating the can-in-canister concept for plutonium immobilization is considered in this calculation. Each HLW glass pour canister contains 7 tubes. Each tube contains 4 cans, with 20 ceramic disks (immobilized plutonium) in each.
Stakeholder Involvement and Confidence in the Process of Decision-making for the Disposal of Spent Nuclear Fuel in Finland
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.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 4th 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, 4th Finnish National Report as referred to in Article 32 of the Convention
This is the Finnish National Report, in accordance with the provisions of the Article 32 of the Joint Convention, to the 4th Review Meeting of the Contracting Parties in May 2012. The aim of this report is to present the recent developments of waste management in Finland, to describe waste management facilities and practices in Finland and, for discussion and review among contracting parties, to describe how the obligations under the Convention are fulfilled in Finland.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd 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, 3rd Finnish National Report as referred to in Article 32 of the Convention
The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 29 September 1997 in the Vienna Diplomatic Conference. Finland signed the Convention on 2 October 1997 and deposited the tools of acceptance on 10 February 2000. The Convention entered into force on 18 June 2001. The fulfillment of the obligations of the Convention and the developments after the second Review Meeting are assessed in this report.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 3rd 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, 3rd Finnish National Report as referred to in Article 32 of the Convention
The Joint Convention on the Safety of Spent Fuel<br/>Management and on the Safety of Radioactive<br/>Waste Management was adopted on 29 September<br/>1997 in the Vienna Diplomatic Conference. Finland<br/>signed the Convention on 2 October 1997 and deposited<br/>the tools of acceptance on 10 February<br/>2000. The Convention entered into force on 18 June<br/>2001.<br/>The fulfilment of the obligations of the<br/>Convention and the developments after the second<br/>Review Meeting are assessed in this report.
Identifying remaining socio-technical challenges at the national level: Finland
Identifying remaining socio-technical challenges at the national level: Finland
This research report is part of the research programme International Socio-Technical Challenges for Implementing Geological Disposal (InSOTEC; see www.insotec.eu). The research programme is funded by the Seventh Framework Programme Theme [Fission-2010-1.1.2] [Research activities in support of implementation of geological disposal] (Grant agreement no: 269906).
Radioactive Waste Management and Decommissioning in Finland
Radioactive Waste Management and Decommissioning in Finland
OECD/NEA: Finland
OECD/NEA: Finland
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Kivetty Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Kivetty Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Kivetty.
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Olkiluoto Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Olkiluoto Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Olkiluoto.
Expansion of the Repository for Spent Nuclear Fuel: Environmental Impact Assessment Report
Expansion of the Repository for Spent Nuclear Fuel: Environmental Impact Assessment Report
Interim Summary Report of the Safety Case
Interim Summary Report of the Safety Case
The report outlines the current design and safety concept for the planned repository. It summarises the approach used to formulate scenarios for the evolution of the disposal system over time, describes these scenarios and presents the main models and computer codes used to analyse them. It also discusses compliance with Finnish regulatory requirements for long-term safety of a geological repository and gives the main evidence, arguments and analyses that lead to confidence, on the part of Posiva, in the long-term safety of the planned repository
Safety Case Plan
Safety Case Plan
Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy) Posiva is preparing to submit the construction license application for a spent fuel repository by the end of the year 2012. The long-term safety section supporting the license application is based on a safety case, which, according to the internationally adopted definition, is a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository.
Final Disposal of Spent Nuclear Fuel in Olkiluoto
Final Disposal of Spent Nuclear Fuel in Olkiluoto
Olkiluoto Site Description
Olkiluoto Site Description
This second version of the Olkiluoto Site Report, produced by the OMTF (Olkiluoto Modelling Task Force), updates the Olkiluoto Site Report 2004 (Posiva 2005) with the data and knowledge obtained up to December 2005.<br/>The main product of the modelling has been to develop a descriptive model of the site (the Site Descriptive Model), i.e. a model describing the geometry, properties of the bedrock and the water and the associated interacting processes and mechanisms.