Evaluation of FSV-1 cask for the transport of LWR irradiated fuel assemblies [electronic resource]
The Model FSV-1 spent fuel shipping cask was designed by General Atomic Company (GA) to service the Fort St. Vrain (FSV) nuclear generating station, a High Temperature Gas Reactor (HTGR) owned and operated by Public Service Company of Colorado (PSC). This report presents an evaluation of the suitabi...
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Online Access |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
San Diego, Calif. : Oak Ridge, Tenn. :
General Atomic Company ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1980.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Evaluation of FSV-1 cask for the transport of LWR irradiated fuel assemblies |h [electronic resource] |
| 260 | |a San Diego, Calif. : |b General Atomic Company ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1980. | ||
| 300 | |a Pages: 180 : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through SciTech Connect. | ||
| 500 | |a 05/01/1980. | ||
| 500 | |a "ga-a-15828" | ||
| 500 | |a " ttc-0119" | ||
| 500 | |a Not Available. | ||
| 520 | 3 | |a The Model FSV-1 spent fuel shipping cask was designed by General Atomic Company (GA) to service the Fort St. Vrain (FSV) nuclear generating station, a High Temperature Gas Reactor (HTGR) owned and operated by Public Service Company of Colorado (PSC). This report presents an evaluation of the suitability of the FSV-1 cask for the transport of irradiated Light Water Reactor (LWR) fuel assemblies from both Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). The FSV-1 cask evaluation parameters covered a wide spectrum of LWR fuel assemblies, based on burnup in Megawatt Days/Metric Ton of Heavy Metal (MWD/MTHM) and years of decay since irradiation. The criteria for suitability included allowable radiation dose rates, cask surface and interior temperatures and the Gross Vehicle Weight (GVW) of the complete shipping system. | |
| 536 | |b AT03-80SF10791. | ||
| 650 | 7 | |a Casks. |2 local. | |
| 650 | 7 | |a Water Moderated Reactors. |2 local. | |
| 650 | 7 | |a Spent Fuel Casks. |2 local. | |
| 650 | 7 | |a Bwr Type Reactors. |2 local. | |
| 650 | 7 | |a Water Cooled Reactors. |2 local. | |
| 650 | 7 | |a Containers. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Transport. |2 local. | |
| 650 | 7 | |a Pwr Type Reactors. |2 local. | |
| 650 | 7 | |a Reactor Components. |2 local. | |
| 650 | 7 | |a Evaluation. |2 local. | |
| 650 | 7 | |a Fuel Elements. |2 local. | |
| 650 | 7 | |a Spent Fuel Elements. |2 local. | |
| 650 | 7 | |a Nuclear Fuel Cycle And Fuel Materials. |2 edbsc. | |
| 650 | 7 | |a Engineering. |2 edbsc. | |
| 710 | 2 | |a General Atomic Company. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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