SRTC criticality safety technical review: Nuclear criticality safety evaluation 94-02, uranium solidification facility pencil tank module spacing
- Westinghouse Savannah River Co., Aiken, SC (United States)
Review of NMP-NCS-94-0087, ``Nuclear Criticality Safety Evaluation 94-02: Uranium Solidification Facility Pencil Tank Module Spacing (U), April 18, 1994,`` was requested of the SRTC Applied Physics Group. The NCSE is a criticality assessment to show that the USF process module spacing, as given in Non-Conformance Report SHM-0045, remains safe for operation. The NCSE under review concludes that the module spacing as given in Non-Conformance Report SHM-0045 remains in a critically safe configuration for all normal and single credible abnormal conditions. After a thorough review of the NCSE, this reviewer agrees with that conclusion.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10165429
- Report Number(s):
- SRT-CMA--940017; ON: DE94014648
- Country of Publication:
- United States
- Language:
- English
Similar Records
SRTC criticality technical review: Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility`s Waste Handling Facility
SRTC criticality safety technical review: Nuclear Criticality Safety Evaluation 93-04 enriched uranium receipt
SRTC criticality safety technical review of SRT-CMA-930039
Technical Report
·
Thu Sep 30 20:00:00 EDT 1993
·
OSTI ID:10196085
SRTC criticality safety technical review: Nuclear Criticality Safety Evaluation 93-04 enriched uranium receipt
Technical Report
·
Tue Oct 12 20:00:00 EDT 1993
·
OSTI ID:140424
SRTC criticality safety technical review of SRT-CMA-930039
Technical Report
·
Thu Dec 02 19:00:00 EST 1993
·
OSTI ID:10133403
Related Subjects
054000
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420203
COMPUTER CODES
CRITICALITY
FISSILE MATERIALS
HANDLING EQUIPMENT AND PROCEDURES
HEALTH AND SAFETY
MATHEMATICAL MODELS
NUCLEAR FACILITIES
Nuclear Criticality Safety Program (NCSP)
POSITIONING
RADIATION ACCIDENTS
SAFETY ANALYSIS
SAVANNAH RIVER PLANT
SOLUTIONS
URANIUM COMPOUNDS
VERIFICATION
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420203
COMPUTER CODES
CRITICALITY
FISSILE MATERIALS
HANDLING EQUIPMENT AND PROCEDURES
HEALTH AND SAFETY
MATHEMATICAL MODELS
NUCLEAR FACILITIES
Nuclear Criticality Safety Program (NCSP)
POSITIONING
RADIATION ACCIDENTS
SAFETY ANALYSIS
SAVANNAH RIVER PLANT
SOLUTIONS
URANIUM COMPOUNDS
VERIFICATION