|
E 1.99:conf-791058--48
|
Fission cross section of <sup>239</sup>Th and <sup>232</sup>Th relative to <sup>235</sup>U |
1 |
|
E 1.99: conf-791058-49
|
Finite element basis used in consistent nuclear data evaluation |
1 |
|
E 1.99: conf-791058-50
|
Beta and gamma decay heat evaluation for the thermal fission of ²³⁵U |
1 |
|
E 1.99: conf-791058-51
|
Stellar nucleosynthesis and the 24-keV neutron capture cross sections of some heavy nuclei |
1 |
|
E 1.99: conf-791058-52
|
Doppler broadening effect to neutron resonance cross sections for Ag, AgCl, and Ag/sub 2/O. [Yield, Debye temperature] |
1 |
|
E 1.99:conf-791058--54
|
Photoneutron leakage from the W(gamma,n) reaction at radiation therapy centers |
1 |
|
E 1.99:conf-791058--55
|
Fast-neutron total and scattering cross sections of Cr, Fe and <sup>60</sup>Ni. [1 to 4. 5 MeV] |
1 |
|
E 1.99:conf-791058--56
|
Neutron dosimetry for radiation damage in fission and fusion reactors |
1 |
|
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 |
