Damage rates for FFTF structural components and surveillance assemblies [electronic resource]
The Fast Flux Test Facility (FFTF) surveillance program provides coupon surveillance materials that are irradiated to the expected lifetime damage dose that the represented component will experience. This methodology requires a knowledge of the damage dose rates to the surveillance assemblies and to...
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Online Access |
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| Corporate Authors: | , |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1993.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Damage rates for FFTF structural components and surveillance assemblies |h [electronic resource] |
| 260 | |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 1993. | ||
| 300 | |a 16 p. : |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 the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 08/01/1993. | ||
| 500 | |a "whc-sa--1746" | ||
| 500 | |a " conf-930809--2" | ||
| 500 | |a "DE93040112" | ||
| 500 | |a 8. ASTM-EURATOM symposium on reactor dosimetry,Vail, CO (United States),29 Aug - 3 Sep 1993. | ||
| 500 | |a Simons, R.L. | ||
| 520 | 3 | |a The Fast Flux Test Facility (FFTF) surveillance program provides coupon surveillance materials that are irradiated to the expected lifetime damage dose that the represented component will experience. This methodology requires a knowledge of the damage dose rates to the surveillance assemblies and to the critical locations of the structural components. This analysis updates the predicted exposures from a total fluence to a displacement per atom (dpa) basis using Monte Carlo (computer code for) neutron photon (transport) code (MCNP). The MCNP calculation improves the relative consistency and lowers the predicted damage rates uncertainty in a number of out-of-core locations. The results were used an part of the evaluation to extend the lifetime of the invessel components to 30 years in support of multiple missions for FFTF. | |
| 536 | |b AC06-87RL10930. | ||
| 650 | 7 | |a Radiation Effects. |2 local. | |
| 650 | 7 | |a Failures. |2 local. | |
| 650 | 7 | |a Radiation Doses. |2 local. | |
| 650 | 7 | |a Reactor Internals. |2 local. | |
| 650 | 7 | |a Reactor Safety. |2 local. | |
| 650 | 7 | |a Reactor Components. |2 local. | |
| 650 | 7 | |a Surveillance. |2 local. | |
| 650 | 7 | |a Damage. |2 local. | |
| 650 | 7 | |a Fftf Reactor. |2 local. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 710 | 2 | |a Westinghouse Hanford Company. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Richland Operations Office. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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