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|a (TOE)ost81037
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|a (TOE)81037
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|a TOE
|c TOE
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|a GDWR
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|a E 1.99:WHC-SD-FF-CSER--004
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|a E 1.99:WHC-SD-FF-CSER--004
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|a WHC-SD-FF-CSER--004
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|a DE95012576
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| 245 |
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|a Criticality safety evaluation for long term storage of FFTF fuel in interim storage casks
|h [electronic resource]
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| 260 |
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|a Washington, D.C. :
|b United States. Dept. of Energy ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1995.
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| 300 |
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|a 40 p.
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| 336 |
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|a text
|b txt
|2 rdacontent.
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| 337 |
|
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|a computer
|b c
|2 rdamedia.
|
| 338 |
|
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|a online resource
|b cr
|2 rdacarrier.
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| 500 |
|
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|a Published through the Information Bridge: DOE Scientific and Technical Information.
|
| 500 |
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|a 05/11/1995.
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| 500 |
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|a "WHC-SD-FF-CSER--004"
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| 500 |
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|a "DE95012576"
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| 500 |
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|a Richard, R.F.
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| 520 |
3 |
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|a It has been postulated that a degradation phenomenon, referred to as ̀̀hot cell rot̀̀, may affect irradiated FFTF mixed plutonium-uranium oxide (MOX) fuel during dry interim storage. ̀̀Hot cell rot̀̀ refers to a variety of phenomena that degrade fuel pin cladding during exposure to air and inert gas environments. It is thought to be a form of caustic stress corrosion cracking or environmentally assisted cracking. Here, a criticality safety analysis was performed to address the effect of the ̀̀hot cell rot̀̀ phenomenon on the long term storage of irradiated FFTF fuel in core component containers. The results show that seven FFTF fuel assemblies or six Ident-69 pin containers stored in core component containers within interim storage casks will remain safely subcritical.
|
| 536 |
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|b AC06-87RL10930.
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| 650 |
|
7 |
|a Fftf Reactor.
|2 local.
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| 650 |
|
7 |
|a Spent Fuel Elements.
|2 local.
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| 650 |
|
7 |
|a Dry Storage.
|2 local.
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| 650 |
|
7 |
|a Spent Fuel Storage.
|2 local.
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| 650 |
|
7 |
|a Safety Analysis.
|2 local.
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| 650 |
|
7 |
|a Criticality.
|2 local.
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| 650 |
|
7 |
|a Spent Fuel Casks.
|2 local.
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| 650 |
|
7 |
|a Mixed Oxide Fuels.
|2 local.
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| 650 |
|
7 |
|a Fuel Cans.
|2 local.
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| 650 |
|
7 |
|a Crack Propagation.
|2 local.
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| 650 |
|
7 |
|a Failures.
|2 local.
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| 650 |
|
7 |
|a Storage Facilities.
|2 local.
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| 650 |
|
7 |
|a Theoretical Data.
|2 local.
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| 650 |
|
7 |
|a Nuclear Fuels ;42 Engineering Not Included In Other Categories.
|2 edbsc.
|
| 710 |
2 |
|
|a Westinghouse Hanford Company.
|4 res.
|
| 710 |
2 |
|
|a United States.
|b Department of Energy.
|4 spn.
|
| 710 |
2 |
|
|a Hanford Site (Wash.
|b ).
|4 res.
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| 710 |
2 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
|
| 856 |
4 |
0 |
|u http://www.osti.gov/servlets/purl/81037-nSOMkn/webviewable/
|z Online Access
|
| 907 |
|
|
|a .b56600203
|b 03-06-23
|c 12-20-09
|
| 998 |
|
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|a web
|b 12-20-09
|c f
|d m
|e p
|f eng
|g dcu
|h 0
|i 1
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| 956 |
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|a Information bridge
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| 999 |
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|i 95822be7-5e7b-5ab8-add9-0591572effc1
|s 3aeeec99-6253-5ce3-9d75-5591d8ebc730
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:WHC-SD-FF-CSER--004
|h Superintendent of Documents classification
|i web
|n 1
|
