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E 1.99:conf-791058--28
|
Relative consistency of ENDF/B-IV and -V with fast-reactor benchmarks |
1 |
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E 1.99:conf-791058--29
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Least squares methodology applied to LWR-PV damage dosimetry, experience and expectations |
1 |
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E 1.99:conf-791058--30
|
Consistent nuclear model for compound and precompound reactions with conservation of angular momentum. [14. 6 MeV] |
1 |
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E 1.99:conf-791058--31
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Simultaneous evaluation of <sup>32</sup>S(n,p), <sup>56</sup>Fe(n,p), <sup>65</sup>Cu(n,2n) cross sections |
1 |
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E 1.99:conf-791058--32
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Neutron emission spectra induced by 14-MeV neutrons from the Evaluated Nuclear Data File (ENDF/B-V) a critical review. |
1 |
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E 1.99:conf-791058--33
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Measurement of <sup>238</sup>U(n,n'gamma)<sup>238</sup>U* cross sections |
1 |
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E 1.99:conf-791058--34
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VITAMIN E a multipurpose ENDF/B-V coupled neutron-gamma cross section library. |
1 |
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E 1.99:conf-791058--35
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Integral experiments for fusion reactor design experimentation. |
1 |
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E 1.99:conf-791058--36
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Calculated particle production spectra and multiplicities from nucleon-fissile element collisions at medium energies |
1 |
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E 1.99:conf-791058--37
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Evaluation of the fission and capture cross sections of <sup>240</sup>Pu; and <sup>241</sup>Pu for ENDF/B-V. [10/sup -5/ eV to 20 MeV] |
1 |
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E 1.99:conf-791058--38
|
High-resolution fission cross section of <sup>231</sup>Pa. [0. 4 eV to 12 MeV] |
1 |
|
E 1.99:conf-791058--39
|
Neutron total cross section measurements on <sup>249</sup>Cf. [0. 01 to 90 eV] |
1 |
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E 1.99: conf-791058-40
|
Evaluations of the ⁵⁸Fe(n,. gamma. )⁵⁹Fe, and ⁵⁴Fe(n,p)⁵⁴Mn reactions for the ENDF/B-V dosimetry file. [E < 15 MeV] |
1 |
|
E 1.99: conf-791058-41
|
Measurements of neutron spectra from 35 MeV deuterons on thick lithium for the FMIT facility |
1 |
|
E 1.99: conf-791058-42
|
Evaluations of fission product capture cross sections for ENDF/B-V |
1 |
|
E 1.99: conf-791058-43
|
Nuclear data needs for FMIT |
1 |
|
E 1.99: conf-791058-44
|
Coupled channels model for radiative capture of nucleons by ¹²C. [1 to 10 MeV] |
1 |
|
E 1.99: conf-791058-45
|
Neutron spectrum at 90/sup 0/ from 800 MeV (p,n) reactions on a Ta target |
1 |
|
E 1.99: conf-791058-46
|
Capture cross section and gamma-ray spectrum calculations for medium-weight nuclei. [Double-peak, energy-dependent Breit-Wigner model] |
1 |
|
E 1.99: conf-791058-47
|
Spatial dependence of flux and damage in the FMIT test cell |
1 |
