The TN-24P PWR spent-fuel storage cask: Testing and analyses: Interim report
Creators
- Creer, J.M.
- Michener, T.E.
- McKinnon, M.A.
- Tanner, J.E.
- Gilbert, E.R.
- Dziadosz, D.A.
- Moore, E.V.
- Schoonen, D.H.
- Jensen, M.F.
- Pacific Northwest Lab., Richland, WA (USA)
- Virginia Electric and Power Co., Richmond (USA)
- Idaho National Engineering Lab., Idaho Falls (USA)
- Electric Power Research Inst., Palo Alto, CA (USA)
Description
A performance test of a Transnuclear, Inc. TN-24P storage cask configured for pressurized water reactor (PWR) spent fuel was performed. The test was the second of a series of cask performance tests planned under a cooperative agreement between Virginia Power and the US Department of Energy. The performance test consisted of loading the TN-24P cask with 24 PWR spent fuel assemblies from Virginia Power's Surry reactor. Cask surface and fuel assembly guide tube temperatures were measured, as were cask surface gamma and neutron dose rates. Testing was performed with vacuum, nitrogen, and helium backfill environment in both vertical and horizontal cask orientations. Limited spent fuel integrity data were also obtained
Availability note (English)
Available from NTIS, PC A11/MF A01 - Report Research Center, Box 50490, Palo Alto, CA 94303; 1 as DE87009214.
Files
Restricted
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Additional details
Publishing Information
- Imprint Pagination
- 248 p.
- Report number
- EPRI-NP--5128
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19002181
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- AFTER-HEAT REMOVAL; BACKFILLING; C CODES; CASKS; DATA ACQUISITION SYSTEMS; EXPERIMENTAL DATA; FUEL ASSEMBLIES; GAMMA DOSIMETRY; HEAT TRANSFER; HELIUM; HYDRAULICS; MATHEMATICAL MODELS; MODIFICATIONS; NEUTRON DOSIMETRY; NITROGEN; O CODES; PERFORMANCE TESTING; PWR TYPE REACTORS; RADIATION MONITORING; RADIATION PROTECTION; REMOTE HANDLING EQUIPMENT; SHIELDING; SHIELDING MATERIALS; SPECIFICATIONS; SPENT FUEL STORAGE; TEMPERATURE DISTRIBUTION; ULTRASONIC TESTING
- Descriptors DEC
- ACOUSTIC TESTING; COMPUTER CODES; CONTAINERS; DATA; DOSIMETRY; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; INFORMATION; MATERIALS; MATERIALS HANDLING EQUIPMENT; MATERIALS TESTING; MONITORING; NONDESTRUCTIVE TESTING; NONMETALS; NUMERICAL DATA; POWER REACTORS; RARE GASES; REACTORS; STORAGE; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.