HIGH FLUX ISOTOPE REACTOR
Journal Article
·
· Nuclear Sci. and Eng.
OSTI ID:4224936
A comparison of possible types of reactors for the production of transplutonium elements and other isotopes indicates that a flux-trap reactor consisting of a beryllium-reflected, light-water-cooled annular fuel region surrounding a light-water island provides the required thermal neutron fluxes (3 x 10/sup 15/) at minimum cost. The preliminary design of such a reactor was carried out on the basis of a parametric study of the effect of dimensions of the island and fuel region, size and weight of the sample of material to be irradiated, heat removal rates, and fuel loading on the achievable thermal neutron fluxes in the island and reflector. (W.D.M.)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- NSA Number:
- NSA-13-017416
- OSTI ID:
- 4224936
- Journal Information:
- Nuclear Sci. and Eng., Journal Name: Nuclear Sci. and Eng. Vol. Vol: 2, No. 1, Suppl.
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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