Criticality analysis for FFTF fuel assemblies and fuel pins [electronic resource]
A series of calculations is presented assessing the criticality aspects of specific configurations of FTR fuel. Results for regularly spaced arrangements of fuel pins or fuel assemblies as a function of spacing in each of four media (water, Mobiltherm, sodium, or air) are given. This information is...
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Online Access |
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| Main Authors: | , |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Oak Ridge, Tenn. :
distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1977.
|
| Subjects: |
MARC
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| 245 | 0 | 0 | |a Criticality analysis for FFTF fuel assemblies and fuel pins |h [electronic resource] |
| 260 | |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 1977. | ||
| 300 | |a Pages: 37 : |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 03/01/1977. | ||
| 500 | |a "hedl-tc-807" | ||
| 500 | |a Marr, D.R.; Morford, R.J. | ||
| 500 | |a Hanford Engineering Development Lab., Richland, WA (USA) | ||
| 520 | 3 | |a A series of calculations is presented assessing the criticality aspects of specific configurations of FTR fuel. Results for regularly spaced arrangements of fuel pins or fuel assemblies as a function of spacing in each of four media (water, Mobiltherm, sodium, or air) are given. This information is intended to be of a broad general nature conservatively applicable both to normal fuel configurations likely to be encountered in the operation of the FFTF and to accident condition configurations postulated for criticality review purposes. | |
| 536 | |b EY-76-C-14-2170. | ||
| 650 | 7 | |a Fftf Reactor. |2 local. | |
| 650 | 7 | |a Fuel Assemblies. |2 local. | |
| 650 | 7 | |a Configuration. |2 local. | |
| 650 | 7 | |a Criticality. |2 local. | |
| 650 | 7 | |a Fuel Pins. |2 local. | |
| 650 | 7 | |a Epithermal Reactors. |2 local. | |
| 650 | 7 | |a Fast Reactors. |2 local. | |
| 650 | 7 | |a Fuel Elements. |2 local. | |
| 650 | 7 | |a Liquid Metal Cooled Reactors. |2 local. | |
| 650 | 7 | |a Reactor Components. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Research And Test Reactors. |2 local. | |
| 650 | 7 | |a Research Reactors. |2 local. | |
| 650 | 7 | |a Sodium Cooled Reactors. |2 local. | |
| 650 | 7 | |a Test Reactors. |2 local. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 700 | 1 | |a Marr, D.R. |4 aut. | |
| 700 | 1 | |a Morford, R.J. |4 aut. | |
| 700 | 2 | |a Hanford Engineering Development Lab., Richland, WA (USA) |4 res. | |
| 710 | 1 | |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/6611569/ |z Online Access |
| 907 | |a .b74110007 |b 03-07-23 |c 07-05-13 | ||
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