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A method for determining the spent-fuel contribution to transport cask containment requirements

Description: This report examines containment requirements for spent-fuel transport containers that are transported under normal and hypothetical accident conditions. A methodology is described that estimates the probability of rod failure and the quantity of radioactive material released from breached rods. This methodology characterizes the dynamic environment of the cask and its contents and deterministically models the peak stresses that are induced in spent-fuel cladding by the mechanical and thermal d… more
Date: November 1, 1992
Creator: Sanders, T. L.; Seager, K. D.; Rashid, Y. R.; Barrett, P. R.; Malinauskas, A. P.; Einziger, R. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Burnup credit applications in a high-capacity truck cask

Description: General Atomics (GA) has designed two legal weight truck (LWT) casks, the GA-4 and GA-9, to carry four pressurized-water-reactor (PWR) and nine boiling-water-reactor (BWR) fuel assemblies, respectively. GA plans to submit applications for certification to the US Nuclear Regulatory Commission (NRC) for the two casks in mid-1993. GA will include burnup credit analysis in the Safety Analysis Report for Packaging (SARP) for the GA-4 Cask. By including burnup credit in the criticality safety analysi… more
Date: September 1, 1992
Creator: Boshoven, J.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Burnup credit applications in a high-capacity truck cask

Description: General Atomics (GA) has designed two legal weight truck (LWT) casks, the GA-4 and GA-9, to carry four pressurized-water-reactor (PWR) and nine boiling-water-reactor (BWR) fuel assemblies, respectively. GA plans to submit applications for certification to the US Nuclear Regulatory Commission (NRC) for the two casks in mid-1993. GA will include burnup credit analysis in the Safety Analysis Report for Packaging (SARP) for the GA-4 Cask. By including burnup credit in the criticality safety analysi… more
Date: September 1, 1992
Creator: Boshoven, J. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development of the GA-4 and GA-9 legal weight spent fuel casks

Description: GA is nearing the completion of the final design of two legal weight truck spent fuel shipping casks, the GA-4 Cask for PWR fuel and the GA-9 Cask for BWR fuel. GA is developing the casks under contract to the US Department of Energy (DOE) Field Office, Idaho, as part of the Office of Civilian Radioactive Waste Management (OCRWM) Cask Systems Development Program (CSDP). The casks will transport intact spent fuel assemblies fro commercial nuclear reactors sites to a monitored retrievable storage… more
Date: September 1, 1992
Creator: Grenier, R. M.; Meyer, R. J. & Mings, W. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development of the GA-4 and GA-9 legal weight spent fuel casks

Description: GA is nearing the completion of the final design of two legal weight truck spent fuel shipping casks, the GA-4 Cask for PWR fuel and the GA-9 Cask for BWR fuel. GA is developing the casks under contract to the US Department of Energy (DOE) Field Office, Idaho, as part of the Office of Civilian Radioactive Waste Management (OCRWM) Cask Systems Development Program (CSDP). The casks will transport intact spent fuel assemblies fro commercial nuclear reactors sites to a monitored retrievable storage… more
Date: September 1, 1992
Creator: Grenier, R. M.; Meyer, R. J. & Mings, W. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Thermal testing of solid neutron shielding materials

Description: Two legal-weight truck casks the GA-4 and GA-9, will carry four PWR and nine BWR spent fuel assemblies, respectively. Each cask has a solid neutron shielding material separating the steel body and the outer steel skin. In the thermal accident specified by NRC regulations in 10CFR Part 71, the cask is subjected to an 800[degree]C environment for 30 minutes. The neutron shield need not perform any shielding function during or after the thermal accident, but its behavior must not compromise the ab… more
Date: September 1, 1992
Creator: Boonstra, R.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Thermal testing of solid neutron shielding materials

Description: Two legal-weight truck casks the GA-4 and GA-9, will carry four PWR and nine BWR spent fuel assemblies, respectively. Each cask has a solid neutron shielding material separating the steel body and the outer steel skin. In the thermal accident specified by NRC regulations in 10CFR Part 71, the cask is subjected to an 800{degree}C environment for 30 minutes. The neutron shield need not perform any shielding function during or after the thermal accident, but its behavior must not compromise the ab… more
Date: September 1, 1992
Creator: Boonstra, R. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Application of the ASME Code in the Design of the GA-4 and GA-9 Casks

Description: General Atomics (GA) is developing two spent fuel shipping casks for transport by legal weight truck (LWT). The casks are designed to the loading, environmental conditions and safety requirements defined in Title 10 of the Code of Federal Regulations, Part 71 (10CFR71). To ensure that all components of the cask meet the 10CFR71 rules, GA established structural design criteria for each component based on NRC Regulatory Guides and the American Society of Mechanical Engineers Boiler and Pressure V… more
Date: August 1, 1992
Creator: Mings, W. J. & Koploy, M. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Criticality safety and shielding design issues in the development of a high-capacity cask for truck transport

Description: General Atomics (GA) will be submitting an application for certification to the US Nuclear Regulatory Commission (NRC) for the GA-4 and GA-9 Casks In 1992. The GA-4 and GA-9 Casks are high-capacity legal weight truck casks designed to transport light water reactor spent fuel assemblies. To maintain a capacity of four pressurized-water-reactor (PWR) spent fuel assemblies, the GA-4 Cask uses burnup credit as part of the criticality control for initial enrichments over 3.0 wt% U-235. Using the US … more
Date: August 1, 1992
Creator: Boshoven, J. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development status of the GA-4 and GA-9 casks

Description: General Atomics (GA) has developed two legal-weight truck spent fuel shipping casks for transporting commercial reactor spent fuel. The GA-4 Cask carries four pressurized-water reactor (PWR) assemblies, and the GA-9 Cask carries nine boiling-water reactor (BWR) assemblies. Depleted uranium and a borated polymer are the gamma an neutron shielding materials. Type XM-19 stainless steel is the structural material used for the cask body, closure and the structure which supports the fuel assemblies. … more
Date: August 1, 1992
Creator: Grenier, R. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The thermal analysis of BR-100: A barge/rail nuclear spent fuel transportation container

Description: B&W Fuel Company is designing a spent-fuel container called BR-100 that can be used for either barge or rail transport. This paper presents the thermal design and analysis. Both normal operation and hypothetical accident thermal transient conditions are evaluated. The BR-100 cask has a concrete layer than contains free water. During a hypothetical accident, the free water vaporizes and flows from the cask, removing a significant amount of thermal transient energy. The BR-100 transportation pack… more
Date: August 1, 1992
Creator: Copsey, A. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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DOE Office of Civilian Radioactive Waste Management (OCRWM) system studies digest

Description: The Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) has sponsored system studies to support the evaluation of alternative configurations and operations for the Civilian Radioactive Waste Management System (CRWMS) and the development of system requirements and design specifications. These studies are generally directed toward evaluating the impacts of alternatives to the monitored retrievable storage (MRS) and fuel rod consolidation, waste form and characterist… more
Date: June 1, 1992
Creator: McLeod, N. B. (Johnson and Associates Inc., Fairfax, Virginia (United States)); Nguyen, T. D.; Drexelius, R. (USDOE Office of Civilian Radioactive Waste Management, Washington, DC (United States)) & McKee, R. W. (Pacific Northwest Lab., Richland, WA (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DOE Office of Civilian Radioactive Waste Management (OCRWM) system studies digest

Description: The Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) has sponsored system studies to support the evaluation of alternative configurations and operations for the Civilian Radioactive Waste Management System (CRWMS) and the development of system requirements and design specifications. These studies are generally directed toward evaluating the impacts of alternatives to the monitored retrievable storage (MRS) and fuel rod consolidation, waste form and characterist… more
Date: June 1, 1992
Creator: McLeod, N. B.; Nguyen, T. D.; Drexelius, R. & McKee, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fifth in situ vitrification engineering-scale test of simulated INEL buried waste sites

Description: In September 1990, an engineering-scale in situ vitrification (ISV) test was conducted on sealed canisters containing a combined mixture of buried waste materials expected to be present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). The test was part of a Pacific Northwest Laboratory (PNL) program to assist INEL in treatability studies of the potential application of ISV to mixed transuranic wastes at the INEL SDA. The purpose of this test was to determine t… more
Date: June 1, 1992
Creator: Bergsman, T.M.; Shade, J.W. (Pacific Northwest Lab., Richland, WA (United States)) & Farnsworth, R.K. (EG and G Idaho, Inc., Idaho Falls, ID (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fifth in situ vitrification engineering-scale test of simulated INEL buried waste sites

Description: In September 1990, an engineering-scale in situ vitrification (ISV) test was conducted on sealed canisters containing a combined mixture of buried waste materials expected to be present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). The test was part of a Pacific Northwest Laboratory (PNL) program to assist INEL in treatability studies of the potential application of ISV to mixed transuranic wastes at the INEL SDA. The purpose of this test was to determine t… more
Date: June 1, 1992
Creator: Bergsman, T. M.; Shade, J. W. & Farnsworth, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Foreign Experience in Extended Dry Storage of Spent Nuclear Fuel

Description: Most countries with nuclear power are planning for spent nuclear fuel (or high-level waste from reprocessing of spent fuel) to be disposed of in national deep geological repositories starting in the time period of about 2010 to 2050. While spent fuel has been stored in water basins for the early years after discharge from the reactors, interim dry storage for extended periods (i.e., several tens of years) is being implemented or considered in an increasing number of countries. Dry storage techn… more
Date: June 1992
Creator: Schneider, K. J. & Mitchell, S. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Foreign experience in extended dry storage of spent nuclear fuel

Description: Most countries with nuclear power are planning for spent nuclear fuel (or high-level waste from reprocessing of spent fuel) to be disposed of in national deep geological repositories starting in the time period of about 2010 to 2050. While spent fuel has been stored in water basins for the early years after discharge from the reactors, interim dry storage for extended periods (i.e., several tens of years) is being implemented or considered in an increasing number of countries. Dry storage techn… more
Date: June 1, 1992
Creator: Schneider, K. J. & Mitchell, S. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Facility Interface Capability Assessment (FICA) summary report

Description: The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from the commercial facilities. In support of the development of the CRWMS, OCRWM sponsored the Facility Interface Capability Assessment (FICA) project. The objective of this project was to assess the capability of each commercial facility to handle various spent nuclear fuel shipping casks. The purpose of this report is … more
Date: May 1, 1992
Creator: Viebrock, J. M.; Mote, N. & Pope, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Facility Interface Capability Assessment (FICA) summary report

Description: The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from the commercial facilities. In support of the development of the CRWMS, OCRWM sponsored the Facility Interface Capability Assessment (FICA) project. The objective of this project was to assess the capability of each commercial facility to handle various spent nuclear fuel shipping casks. The purpose of this report is … more
Date: May 1, 1992
Creator: Viebrock, J. M.; Mote, N. & Pope, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of radiation doses from operation of postulated commercial spent fuel transportation systems: Analysis of a system containing a monitored retrievable storage facility. Addendum 1

Description: This addendum report extends the original study of the estimated radiation doses to the public and to workers resulting from transporting spent nuclear fuel from commercial nuclear power reactor stations through the federal waste management system (FWMS), to a system that contains a monitored retrievable storage (MRS) facility. The system concepts and designs utilized herein are consistent with those used in the original study (circa 1985--1987). Because the FWMS design is still evolving, the r… more
Date: April 1, 1992
Creator: Smith, R. I.; Daling, P. M. & Faletti, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel

Description: This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integr… more
Date: April 1, 1992
Creator: Schneider, K.J. & Mitchell, S.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel

Description: This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integr… more
Date: April 1, 1992
Creator: Schneider, K. J. & Mitchell, S. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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