Energy-averaged neutron cross sections of fast-reactor structural materials [electronic resource]
The status of energy-averaged cross sections of fast-reactor structural materials is outlined with emphasis on U.S. data programs in the neutron-energy range 1-10 MeV. Areas of outstanding accomplishment and significant uncertainty are noted with recommendations for future efforts. Attention is prim...
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Online Access |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Argonne, Ill. : Oak Ridge, Tenn. :
Argonne National Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1978.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Energy-averaged neutron cross sections of fast-reactor structural materials |h [electronic resource] |
| 260 | |a Argonne, Ill. : |b Argonne National Laboratory ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1978. | ||
| 300 | |a Pages: 65 : |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 02/01/1978. | ||
| 500 | |a "anl/ndm-41" | ||
| 500 | |a " conf-771233-1" | ||
| 500 | |a Meeting on neutron data of structural materials, Geel, Belgium, 5 Dec 1977. | ||
| 500 | |a Smith, A.; Smith, D.; McKnight, R. | ||
| 520 | 3 | |a The status of energy-averaged cross sections of fast-reactor structural materials is outlined with emphasis on U.S. data programs in the neutron-energy range 1-10 MeV. Areas of outstanding accomplishment and significant uncertainty are noted with recommendations for future efforts. Attention is primarily given to the main constituents of stainless steel (e.g., Fe, Ni, and Cr) and, secondarily, to alternate structural materials (e.g., V, Ti, Nb, Mo, Zr). Generally, the mass regions of interest are A approximately 50 to 60 and A approximately 90 to 100. Neutron total and elastic-scattering cross sections are discussed with the implication on the non-elastic-cross sections. Cross sections governing discrete-inelastic-neutron-energy transfers are examined in detail. Cross sections for the reactions (n;p), (n;n',p), (n;..cap alpha..), (n;n',..cap alpha..) and (n;2n') are reviewed in the context of fast-reactor performance and/or diagnostics. The primary orientation of the discussion is experimental with some additional attention to the applications of theory, the problems of evaluation and the data sensitivity of representative fast-reactor systems. | |
| 536 | |b W-31-109-ENG-38. | ||
| 650 | 7 | |a Cross Sections. |2 local. | |
| 650 | 7 | |a Neutrons. |2 local. | |
| 650 | 7 | |a Nuclear Reactions. |2 local. | |
| 650 | 7 | |a Reactor Materials. |2 local. | |
| 650 | 7 | |a Document Types. |2 local. | |
| 650 | 7 | |a Elementary Particles. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Fast Neutrons. |2 local. | |
| 650 | 7 | |a Baryon Reactions. |2 local. | |
| 650 | 7 | |a Nucleon Reactions. |2 local. | |
| 650 | 7 | |a Nucleons. |2 local. | |
| 650 | 7 | |a Hadrons. |2 local. | |
| 650 | 7 | |a Hadron Reactions. |2 local. | |
| 650 | 7 | |a Neutron Reactions. |2 local. | |
| 650 | 7 | |a Reviews. |2 local. | |
| 650 | 7 | |a Baryons. |2 local. | |
| 650 | 7 | |a Fermions. |2 local. | |
| 650 | 7 | |a Nuclear Physics And Radiation Physics. |2 edbsc. | |
| 710 | 2 | |a Argonne 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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| 952 | f | f | |p Can circulate |a University of Colorado Boulder |b Online |c Online |d Online |e E 1.99: conf-771233-1 |h Superintendent of Documents classification |i web |n 1 |