Assessment of an engineered barrier system and design of waste packages
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:5627005
- Lawrence Livermore National Lab., CA (USA)
The US Nuclear Regulatory Commission regulation 10CFR60 establishes two major performance objectives for the engineered barrier system (EBS): substantially complete containment within the waste packages for up to 1000 yr and control of the release rate from the EBS for 10,000 yr. The EBS is defined in 10CFR60 as the waste packages and the underground structure, not including shafts and boreholes. The US Department of Energy has adopted a tentative interpretation of the EBS boundary as the edge of the emplacement hole; i.e., the EBS consists of anything inside the emplacement hole. Such a boundary is conservative and simple to define. Because the containment performance objective in 10CFR60 is qualitative, the DOE has tentatively interpreted substantially complete containment in terms of quantitative design objectives. These design objectives are briefly summarized. Assessment of performance of the waste package and EBS is based on allocating performance for various waste package components toward overall design objectives. Then, computer modeling will be used in conjunction with testing to assess whether the allocations are met or exceeded. Because of the unprecedented time period considered, computer modeling is essential. A significant issue will be validation of the computer models.
- OSTI ID:
- 5627005
- Report Number(s):
- CONF-880601--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 56
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALLOYS
BOROSILICATE GLASS
COMPUTERIZED SIMULATION
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CORROSION RESISTANCE
ENERGY SOURCES
ENGINEERED SAFETY SYSTEMS
FUELS
GLASS
HIGH ALLOY STEELS
HIGH-LEVEL RADIOACTIVE WASTES
IRON ALLOYS
IRON BASE ALLOYS
LEAKS
LINERS
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEAR FUELS
PACKAGING
PERFORMANCE
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
REACTOR MATERIALS
SIMULATION
SPENT FUELS
STAINLESS STEELS
STEELS
US DOE
US ORGANIZATIONS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALLOYS
BOROSILICATE GLASS
COMPUTERIZED SIMULATION
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CORROSION RESISTANCE
ENERGY SOURCES
ENGINEERED SAFETY SYSTEMS
FUELS
GLASS
HIGH ALLOY STEELS
HIGH-LEVEL RADIOACTIVE WASTES
IRON ALLOYS
IRON BASE ALLOYS
LEAKS
LINERS
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEAR FUELS
PACKAGING
PERFORMANCE
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
REACTOR MATERIALS
SIMULATION
SPENT FUELS
STAINLESS STEELS
STEELS
US DOE
US ORGANIZATIONS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES