E 1.99:conf-791058--57
|
Denatured fuel cycles |
1 |
E 1.99:conf-791058--58
|
Fast-neutron capture cross sections of importance in technological applications. [Review] |
1 |
E 1.99:conf-791058--59
|
Status of neutron dosimetry and damage analysis for the fusion materials program |
1 |
E 1.99:conf-791058--60
|
Discrepancy between differential and integral results for the <sup>63</sup>Cu(n,α)<sup>60</sup>Co cross sections. [Threshold to 10 MeV] |
1 |
E 1.99:conf-791058--61
|
Total-neutron cross sections of heavy nuclei. [30 to 4800 keV] |
1 |
E 1.99:conf-791058--62
|
Evaluation of /sup 235/U(n,f) above 100 keV for ENDF/B-V and the implications of a unified /sup 235/U mass scale. [Above 100 keV] |
1 |
E 1.99: conf-791058-63
|
Use of high resolution. gamma. -ray spectroscopy for neutron cross sections |
1 |
E 1.99:conf-791058--64
|
Measured and evaluated bismuth data for fusion-fission-hybrid and electro-nuclear breeding applications. [1 to 5 MeV] |
1 |
E 1.99:conf-791058--65
|
Measurement of the fast neutron capture cross section of <sup>238</sup>U relative to <sup>235</sup>U(n,f) |
1 |
E 1.99: conf-791058-66
|
Burning nuclear wastes in fusion reactors |
1 |
E 1.99:conf-791058--67
|
Neutron cross section measurements at ORELA |
1 |
E 1.99:conf-791058--68
|
Use of thorium in fast breeder reactors |
1 |
E 1.99:conf-791058--69
|
Deep penetration integral experiment for a thorium blanket mockup |
1 |
E 1.99:conf-791058--70
|
Evaluated data collections from ENSDF. [ORNL] |
1 |
E 1.99:conf-791058--71
|
Fission product decay heat for thermal reactors |
1 |
E 1.99:conf-791058--72
|
Measurement of the 2. 35 MeV window in O + n |
1 |
E 1.99:conf-791058--73
|
Neutron total cross section of <sup>233</sup>U from 0. 01 to 1. 0 eV |
1 |
E 1.99:conf-791058--74
|
Integral experiments for fusion reactor design analysis. |
1 |
E 1.99:conf-791058--75
|
Shielding of fusion reactors |
1 |
E 1.99:conf-791059--1
|
Extraction and recovery of polycyclic aromatic hydrocarbons from highly sorptive matrices such as fly ash |
1 |