Uncanistered Spent Nuclear fuel Disposal Container System Description Document
The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in the emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Multiple boiling water reactor (BWR) and pressurized water reactor (PWR) disposal container designs are needed to accommodate the expected range of spent fuel assemblies and provide long-term confinement of the commercial SNF. The disposal container will include outer and inner cylinder walls, outer cylinder lids (two on the top, one on the bottom), inner cylinder lids (one on the top, one on the bottom), and an internal metallic basket structure. Exterior labels will provide a means by which to identify the disposal container and its contents. The two metal cylinders, in combination with the cladding, Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lid will be made of high-nickel alloy. The basket will assist criticality control, provide structural support, and improve heat transfer. The Uncanistered SNF Disposal Container System interfaces with the emplacement drift environment and internal waste by transferring heat from the SNF to the external environment and by protecting the SFN assemblies and their contents from damage/degradation by the external environment. The system also interfaces with the SFN by limiting access of moderator and oxidizing agents of the SFN. The waste package interfaces with the Emplacement Drift System's emplacement drift pallets upon which the wasted packages are placed. The disposal container interfaces with the Assembly Transfer System, Waste Emplacement/Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and retrieval of the disposal container/waste package.
- Research Organization:
- Yucca Mountain Project, Las Vegas, Nevada (US)
- Sponsoring Organization:
- US Department of Energy (US); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC08-91RW00134
- OSTI ID:
- 765266
- Report Number(s):
- SDD-UDC-SE-000001, REV 01; MOL.20000822.0004, DC No. 25533
- Country of Publication:
- United States
- Language:
- English
Similar Records
Naval Spent Nuclear Fuel disposal Container System Description Document
Defense High Level Waste Disposal Container System Description
Uncanistered Spent Nuclear fuel Disposal Container System Description Document
Technical Report
·
Fri Jul 13 00:00:00 EDT 2001
·
OSTI ID:790343
Defense High Level Waste Disposal Container System Description
Technical Report
·
Thu Oct 12 00:00:00 EDT 2000
·
OSTI ID:765253
Uncanistered Spent Nuclear fuel Disposal Container System Description Document
Technical Report
·
Thu Jul 12 20:00:00 EDT 2001
·
OSTI ID:790342
Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BOILING
CONFIGURATION
CONFINEMENT
CONTAINERS
CONTAINMENT
CORROSION
CRITICALITY
HEAT TRANSFER
MODERATORS
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
OXIDIZERS
POSITIONING
PWR TYPE REACTORS
RADIOISOTOPES
SPENT FUELS
STAINLESS STEELS
WASTES
YUCCA MOUNTAIN
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BOILING
CONFIGURATION
CONFINEMENT
CONTAINERS
CONTAINMENT
CORROSION
CRITICALITY
HEAT TRANSFER
MODERATORS
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
OXIDIZERS
POSITIONING
PWR TYPE REACTORS
RADIOISOTOPES
SPENT FUELS
STAINLESS STEELS
WASTES
YUCCA MOUNTAIN