Distribution of fission yields for fission spectrum neutron-induced fission of uranium-238 from the White Sands Missile Range fast burst reactor
Harris, D.C.; Beck, J.N.; Raines, W.L.; Harvey, J.T.; Inn, K.G.W.; Meason, J.L.; Wright, H.L.
Dosimetry methods for fuels, cladding, and structural materials1977
Dosimetry methods for fuels, cladding, and structural materials1977
AbstractAbstract
[en] The mass-yield distribution for the neutron-induced fission of 238U by degraded fission spectrum neutrons with an average energy of 1.52 MeV has been measured radiochemically for 26 mass chains in the region A = 89 to 153. Germanium-lithium gamma-ray spectroscopy coupled with beta-particle counting techniques was used to determine the absolute activities of each nuclide measured. The absolute cumulative fission yield of mass chain 140 (140Ba-140La) was determined to be 6.07 +- 0.24, and all other reported yields were measured relative to that value. Measured yields ranged from a maximum of 6.33 +- 0.55 for 103Ru on the light mass wing and 6.54 +- 0.28 for 133I on the heavy mass wing to a minimum of 0.030 +- 0.007 for 121Sn in the valley region. Results from this investigation provide a consistent set of cumulative mass yields from 238U fission induced by a well-characterized neutron spectrum
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Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; p. 1323-1331; 1977; p. 1323-1331; 2. ASTM-EURATOM symposium on reactor dosimetry: dosimetry methods for fuels, cladding and structural materials; Palo Alto, CA, USA; 2 - 7 Oct 1977
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