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Fission Product Yields of {sup 233}U, {sup 235}U, {sup 238}U and {sup 239}Pu in Fields of Thermal Neutrons, Fission Neutrons and 14.7-MeV Neutrons

Journal Article · · Nuclear Data Sheets
; ;  [1];  [1]; ; ; ;  [1]; ;  [2]
  1. Commissariat a l'Energie Atomique, Centre DAM-Ile de France (CEA DAM DIF), 91297 Arpajon (France)
  2. Commissariat a l'Energie Atomique, Centre de Valduc, 21120 Is-sur-Tille (France)

The yields of more than fifteen fission products have been carefully measured using radiochemical techniques, for {sup 235}U(n,f), {sup 239}Pu(n,f) in a thermal spectrum, for {sup 233}U(n,f), {sup 235}U(n,f), and {sup 239}Pu(n,f) reactions in a fission neutron spectrum, and for {sup 233}U(n,f), {sup 235}U(n,f), {sup 238}U(n,f), and {sup 239}Pu(n,f) for 14.7 MeV monoenergetic neutrons. Irradiations were performed at the EL3 reactor, at the Caliban and Prospero critical assemblies, and at the Lancelot electrostatic accelerator in CEA-Valduc. Fissions were counted in thin deposits using fission ionization chambers. The number of fission products of each species were measured by gamma spectrometry of co-located thick deposits.

OSTI ID:
21499799
Journal Information:
Nuclear Data Sheets, Journal Name: Nuclear Data Sheets Journal Issue: 12 Vol. 111; ISSN NDTSBA; ISSN 0090-3752
Country of Publication:
United States
Language:
English

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