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Title: Determination of neutron multiplication coefficients for fuel elements irradiated by spallation neutrons

Journal Article · · Physical Review. C, Nuclear Physics
;  [1]
  1. H.E.N.P. Laboratory (ADS Program), Department of Physics, University of Rajasthan, Jaipur-302004 (India)

A neutron multiplication coefficient, k{sub eff}, has been estimated for spallation neutron flux using the data of spectrum average cross sections of all absorption, fission, and nonelastic reaction channels of {sup 232}Th, {sup 238}U, {sup 235}U, and {sup 233}U fuel elements. It has been revealed that in spallation neutron flux (i) nonfission, nonabsorption reactions play an important role in the calculation of k{sub eff}, (ii) one can obtain a high value of k{sub eff} even for fertile {sup 232}Th fuel, which is hardly possible in a conventional fast reactor, and (iii) spectrum average absorption cross sections of neutron poisons of a conventional reactor are relatively very small.

OSTI ID:
21386617
Journal Information:
Physical Review. C, Nuclear Physics, Vol. 81, Issue 2; Other Information: DOI: 10.1103/PhysRevC.81.024614; (c) 2010 The American Physical Society; ISSN 0556-2813
Country of Publication:
United States
Language:
English