Criticality Calculation for the Most Reactive Degraded Configurations of the FFTF SNF Codisposal WP Containing an Intact Ident-69 Container

Technical Report · Wed Aug 14 00:00:00 EDT 2002

DOI:https://doi.org/10.2172/859174· OSTI ID:859174

Moscalu, D. R. ^[1]

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1. Yucca Mountain Project, Las Vegas, NV (United States)

The objective of this calculation is to perform additional degraded mode criticality evaluations of the Department of Energy's (DOE) Fast Flux Test Facility (FFTF) Spent Nuclear Fuel (SNF) codisposed in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP). The scope of this calculation is limited to the most reactive degraded configurations of the codisposal WP with an almost intact Ident-69 container (breached and flooded but otherwise non-degraded) containing intact FFTF SNF pins. The configurations have been identified in a previous analysis (CRWMS M&O 1999a) and the present evaluations include additional relevant information that was left out of the original calculations. The additional information describes the exact distribution of fissile material in each container (DOE 2002a). The effects of the changes that have been included in the baseline design of the codisposal WP (CRWMS M&O 2000) are also investigated. The calculation determines the effective neutron multiplication factor (k_eff) for selected degraded mode internal configurations of the codisposal waste package. These calculations will support the demonstration of the technical viability of the design solution adopted for disposing of MOX (FFTF) spent nuclear fuel in the potential repository. This calculation is subject to the Quality Assurance Requirements and Description (QARD) (DOE 2002b) per the activity evaluation under work package number P6212310M2 in the technical work plan TWP-MGR-MD-000010 REV 01 (BSC 2002).

• Research Organization: Yucca Mountain Project, Las Vegas, NV (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 859174
• Report Number(s): CAL-DSD-NU-000002-REV-A; MOL.20021028.0128 DC#32952; TRN: US0600531
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CONTAINERS
CRITICALITY
DESIGN
DISTRIBUTION
EVALUATION
FFTF REACTOR
FISSILE MATERIALS
MULTIPLICATION FACTORS
NEUTRONS
NUCLEAR FUELS
QUALITY ASSURANCE
VIABILITY
WASTES
Nuclear Criticality Safety Program (NCSP)
Criticality
Quality Assurance
Flux Flux Test Reactor
FFTF
Fissile Materials
Spent Nuclear Fuel
Codisposal
Ident-69
Containment