Transportation Cask Receipt/Return Facility Criticality Safety Evaluations
- Yucca Mountain Project, Las Vegas, NV (United States)
The purpose of this design calculation is to demonstrate that the handling operations of transportation casks performed in the Transportation Cask Receipt and Return Facility (TCRRF) and Buffer Area meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC [Bechtel SAIC Company] 2004 [DIRS 171599], Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''Transportation Cask Receipt/Return Facility Description Document'' (BSC 2004 [DIRS 170217], Section 3.2.3). Specific scope of work contained in this activity consists of the following items: 1) Evaluate criticality effects for both dry and fully flooded conditions pertaining to TCRRF and Buffer Area operations for defense in depth. 2) Evaluate Category 1 and 2 event sequences for the TCRRF as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). This evaluation includes credible fuel reconfiguration conditions. In addition to the scope of work listed above, an evaluation was also performed of modeling assumptions for commercial spent nuclear fuel (CSNF) regarding inclusion of plenum and end regions of the active fuel. This calculation is limited to CSNF and US Department of Energy (DOE) SNF. it should be mentioned that the latter waste form is evaluated more in depth in the ''Canister Handling Facility Criticality Safety Calculations (BSC 2004 [DIRS 167614]). Further, the design and safety analyses of the naval SNF canisters are the responsibility of the US Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the TCRRF and Buffer Area and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the TCRRF is included in the Q-List (BSC 2004 [DIRS 168361], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].
- Research Organization:
- Yucca Mountain Project, Las Vegas, NV (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC28-01RW12101
- OSTI ID:
- 841271
- Report Number(s):
- 140-00C-HCR0-00300-000-00B; ENG.20050427.0006, DC#44549; TRN: US0600709
- Country of Publication:
- United States
- Language:
- English
Similar Records
Dry Transfer Facility Criticality Safety Calculations
Fuel Handling Facility Criticality Safety Calculations
Related Subjects
12 MANAGEMENT OF RADIOACTIVE WASTES AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BUFFERS
CASKS
CONTAINERS
CRITICALITY
DESIGN
EVALUATION
FUNCTIONALS
NUCLEAR FUELS
PROPULSION
SAFETY
SIMULATION
WASTE FORMS
SPENT FUELS
Nuclear Criticality Safety Program (NCSP)
Nuclear Fuels
Buffer Area
Simulation
Spent Fuels
TCRRF
PDC
CSNF