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E 1.99: conf-850507-3
|
Observations on /sup 3/He neutron spectrometry |
1 |
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E 1.99: conf-850507-4
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Possibilities for studying short-lived nuclei produced at LAMPF |
1 |
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E 1.99: conf-850507-6
|
Burn-up cross sections of ⁵¹Cr, ⁵⁹Fe, ⁶⁵Zn, ⁸⁶Rb, ¹°³Ru |
1 |
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E 1.99:conf-850507-7
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Pairing correction of particle-hole state densities for two kinds of Fermions |
1 |
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E 1.99:conf-850507-8
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High-resolution structural material (n,x. gamma. ) production cross sections for 0. 2 < E/sub n/ less than or equal to 40 MeV |
1 |
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E 1.99:conf-850507-9
|
Measurement of the energy dependence of prompt fission neutron emission from ²³³U, ²³⁵U, and ²³⁹Pu for E = 0. 0005 to 10 MeV relative to emission from spontaneous fission of ²⁵²Cf |
1 |
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E 1.99:conf-850507-10
|
Capture in the 1. 15-keV iron resonance |
1 |
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E 1.99:conf-850507-11
|
Uncertainty propagation from raw data to final results. [ALEX] |
1 |
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E 1.99:conf-850507-12
|
Analysis of neutron data in the resonance region via the computer code SAMMY |
1 |
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E 1.99:conf-850507-13
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Calculated neutron-induced cross sections for /sup 63,65/Cu /sup 58,60/Ni, and ⁵²Cr from 1 to 20 MeV and comparisons with experiments |
1 |
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E 1.99:conf-850507-14
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Neutronic calculations for a new high flux reactor |
1 |
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E 1.99:conf-850507-15
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Fast-neutron interaction with niobium |
1 |
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E 1.99: conf-850507-16
|
Gamma-ray production cross sections for alpha-particle induced reactions on ¹⁹F and ²³Na |
1 |
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E 1.99: conf-850507-17
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Application of evaluated fission-product delayed-neutron precursor data in reactor kinetics calculations |
1 |
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E 1.99: conf-850507-18
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R-matrix analysis of the /sup 7/Li system with peripheral channel overlap exchange effects |
1 |
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E 1.99: conf-850507-19
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Measurements and calculations of neutron scattering angular distributions over a wide mass and energy range |
1 |
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E 1.99: conf-850507-20
|
Some nuclear data needs in astrophysics |
1 |
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E 1.99: conf-850507-21
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Hydrogen fusion-energy reactions |
1 |
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E 1.99: conf-850507-22
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Los Alamos National Laboratory neutron-neutron scattering program |
1 |
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E 1.99: conf-850507-23
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Application of detailed fission-product decay gamma spectra in the calculation of photoneutron spectra from D(. gamma. ,n) reactions in PWR fuel |
1 |
