Determination of defective particle fraction in HTGR fuels [electronic resource]
The fuel for the High-Temperature Gas-Cooled Reactor (HTGR) consists of uranium and thorium species in the form of microspheres individually encapsulated in layers of pyrolytic carbon and silicon carbide. In the characterization of these particles, an important consideration is the fraction in a par...
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Online Access |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Oak Ridge, Tenn. : Oak Ridge, Tenn. :
Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1976.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Determination of defective particle fraction in HTGR fuels |h [electronic resource] |
| 260 | |a Oak Ridge, Tenn. : |b Oak Ridge National Laboratory. ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1976. | ||
| 300 | |a Pages: 25 : |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 11/01/1976. | ||
| 500 | |a "ornl/tm-5483" | ||
| 500 | |a Lackey, W.J.; LaValle, D.E.; Costanzo, D.A.; Caputo, A.J. | ||
| 520 | 3 | |a The fuel for the High-Temperature Gas-Cooled Reactor (HTGR) consists of uranium and thorium species in the form of microspheres individually encapsulated in layers of pyrolytic carbon and silicon carbide. In the characterization of these particles, an important consideration is the fraction in a particular sample that may have defective coatings which would allow the release of gaseous and metallic fission products. A method for this determination, which has been in use for almost a decade, is the chlorine leach in which the gas is passed over the particles at 1000°C, and the fuel that is exposed by coating defects is volatilized and collected as the heavy metal chlorides. However, when the particles have been bonded into a fuel rod, the removal of exposed fuel from particles in the intact rod requires long exposure times (16-50 hours). A much more rapid procedure (2-3 hours) is described in which the chlorination of fuel rods is done at 1500°C. The method is also applicable to loose particles. Also described is an adaptation of the chlorine leach at 1000°C for the treatment of irradiated fuel rods in a hot cell. | |
| 536 | |b W-7405-ENG-26. | ||
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Graphite Moderated Reactors. |2 local. | |
| 650 | 7 | |a Coated Fuel Particles. |2 local. | |
| 650 | 7 | |a Testing. |2 local. | |
| 650 | 7 | |a Sampling. |2 local. | |
| 650 | 7 | |a Coatings. |2 local. | |
| 650 | 7 | |a Fission Product Release. |2 local. | |
| 650 | 7 | |a Performance Testing. |2 local. | |
| 650 | 7 | |a Reactor Components. |2 local. | |
| 650 | 7 | |a Fuel Elements. |2 local. | |
| 650 | 7 | |a Htgr Type Reactors. |2 local. | |
| 650 | 7 | |a Gas Cooled Reactors. |2 local. | |
| 650 | 7 | |a Fuel Particles. |2 local. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 710 | 2 | |a Oak Ridge National Laboratory. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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