Aging Facility Criticality Safety Calculations
- Yucca Mountain Project, Las Vegas, NV (United States)
The purpose of this design calculation is to revise and update the previous criticality calculation for the Aging Facility (documented in BSC 2004a). This design calculation will also demonstrate and ensure that the storage and aging operations to be performed in the Aging Facility meet the criticality safety design criteria in the ''Project Design Criteria Document'' (Doraswamy 2004, Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''SNF Aging System Description Document'' (BSC [Bechtel SAIC Company] 2004f, p. 3-12). The scope of this design calculation covers the systems and processes for aging commercial spent nuclear fuel (SNF) and staging Department of Energy (DOE) SNF/High-Level Waste (HLW) prior to its placement in the final waste package (WP) (BSC 2004f, p. 1-1). Aging commercial SNF is a thermal management strategy, while staging DOE SNF/HLW will make loading of WPs more efficient (note that aging DOE SNF/HLW is not needed since these wastes are not expected to exceed the thermal limits form emplacement) (BSC 2004f, p. 1-2). The description of the changes in this revised document is as follows: 1) Include DOE SNF/HLW in addition to commercial SNF per the current ''SNF Aging System Description Document'' (BSC 2004f). 2) Update the evaluation of Category 1 and 2 event sequences for the Aging Facility as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004c, Section 7). 3) Further evaluate the design and criticality controls required for a storage/aging cask, referred to as MGR Site-specific Cask (MSC), to accommodate commercial fuel outside the content specification in the Certificate of Compliance for the existing NRC-certified storage casks. In addition, evaluate the design required for the MSC that will accommodate DOE SNF/HLW. This design calculation will achieve the objective of providing the criticality safety results to support the preliminary design of the Aging Facility. As the ongoing design evolution remains fluid, the results from this design calculation should be evaluated for applicability to any new or modified design. Consequently, the results presented in this document are limited to the current design. The information contained in this document was developed by Environmental and Nuclear Engineering and is intended for the use of Design and Engineering in its work regarding the various criticality related activities performed in the Aging Facility. Yucca Mountain Project personnel from Environmental and Nuclear Engineering should be consulted before the use of the information for purposes other than those stated herein or use by individuals other than authorized personnel in Design and Engineering.
- 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:
- 841270
- Report Number(s):
- 170-00C-HA00-00100-000-00B; ENG.20040910.0027, DC#42794; TRN: US0504411
- Country of Publication:
- United States
- Language:
- English
Similar Records
Dry Transfer Facility Criticality Safety Calculations
Transportation Cask Receipt/Return Facility Criticality Safety Evaluations
Related Subjects
12 MANAGEMENT OF RADIOACTIVE WASTES AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
AGING
CASKS
COMPLIANCE
CRITICALITY
DESIGN
FUNCTIONALS
NUCLEAR ENGINEERING
NUCLEAR FUELS
PERSONNEL
POSITIONING
SAFETY
SPECIFICATIONS
STORAGE
WASTES
YUCCA MOUNTAIN
Nuclear Criticality Safety Program (NCSP)
Nuclear Engineering
Nuclear Fuels
Yucca Mountain
SNF
SNF Aging System
MSC