Capture-To-Fission Ratios In EBR-II
Full text follows: In calculating the breeding gain of a reactor, one needs to know the neutron spectrum of the reactor and the cross sections as a function of neutron energy. When such complete sets of such data are difficult or impractical to obtain, it is useful to obtain the ratio of the capture and fission cross sections of a species in an existing fast reactor spectrum. This quantity is directly useful in; breeding gain' calculations for that reactor. Work is now in progress (see ANL-6925, p. 251) which will measure the ratios of the capture and fission cross sections of {sup 233}U, {sup 235}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, and {sup 242}Pu as a function of position in EBR-II. Three of the EBR-II subassemblies, containing several of the uranium and plutonium samples, have received the required irradiation and have been removed from the reactor; one of these has been disassembled and its samples shipped back to Argonne. The rest of the subassemblies will be removed from the reactor during the next six months. An order has been placed for samples of {sup 238}Pu and {sup 241}Pu for further capture-to-fission ratio measurement: paralleling those outlined above. At the time that the present work was started, samples of these two isotopes were not available.
- Research Organization:
- Argonne National Laboratory, Argonne, IL (United States)
- OSTI ID:
- 23134758
- Report Number(s):
- ANL-7225; TRN: US22U0103051994
- Resource Relation:
- Other Information: Country of input: International Atomic Energy Agency (IAEA); Related Information: In: Chemical Engineering Division Semiannual Report| by Vogel, R.C.; Levenson, Milton; Schraidt, J. H.; Royal, J.| 236 p.
- Country of Publication:
- United States
- Language:
- English
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