BWR spent fuel storage cask performance test. Volume 1. Cask handling experience and decay heat, heat transfer, and shielding data

Technical Report · Sat Feb 01 04:00:00 EST 1986

DOI:https://doi.org/10.2172/5853284· OSTI ID:5853284

McKinnon, M A; Doman, J W; Tanner, J E; Guenther, R J; Creer, J M; King, C E

This report documents a heat transfer and shielding performance test conducted on a Ridihalgh, Eggers and Associates REA 2023 boiling water reactor (BWR) spent fuel storage cask. The testing effort consisted of three parts: pretest preparations, performance testing, and post-test activities. Pretest preparations included conducting cask handling dry runs and characterizing BWR spent fuel assemblies from Nebraska Public Power District's Cooper Nuclear Station. The performance test matrix included 14 runs consisting of two loadings, two cask orientations, and three backfill environments. Post-test activities included calorimetry and axial radiation scans of selected fuel assemblies, in-basin sipping of each assembly, crud collection, video and photographic scans, and decontamination of the cask interior and exterior.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5853284
• Report Number(s): PNL-5777-Vol.1; ON: DE86010253
• Country of Publication: United States
• Language: English

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
AFTER-HEAT
CASKS
CLEANING
CONTAINERS
DATA
DECONTAMINATION
ENERGY TRANSFER
EXPERIMENTAL DATA
FUEL INTEGRITY
HEAT TRANSFER
INFORMATION
MATERIALS HANDLING
NUMERICAL DATA
PERFORMANCE TESTING
RADIATION PROTECTION
SHIELDING
SPENT FUEL CASKS
TESTING