HIGH FLUX RESEARCH REACTOR (HFRR). Reactor Design and Feasibility Study

Technical Report · Wed Aug 01 00:00:00 EDT 1956

DOI:https://doi.org/10.2172/4344040· OSTI ID:4344040

Cheverton, R. D.; Charmatz, A. W.; Crowther, R. L.; Feinberg, R. J.; Maortensen, G. A.; Schleiter, T. G.

Feasibility studies of a high flux, solid fuel research reactor are presented. By means of a parameter study, a reactor consisting of a cylindricai fuel annulus submerged in heavy water is described. The thermal neutron flux peaks in the heavy water adjacent to the annulus and is a maximum in the region surrounded by the fuel annulus.. while the minimum thermal flux occurs in the annulus. The fast flux has the opposite shape. Calculations indicate that practical peaking factors, ratios of maximum thermal flux in the heavy water to average thermal flux in the fuel annulus, as high as eight can be obtained. A typical reactor in which the maximum thermal and fast fluxes are greater than 10/ sup 15/n/cm/sup 2/-sec is also described. (auth)

• Research Organization: Oak Ridge School of Reactor Technology, Tenn.
• NSA Number: NSA-12-008056
• OSTI ID: 4344040
• Report Number(s): CF-56-8-206
• Country of Publication: United States
• Language: English

Related Subjects

CYLINDERS
FAST NEUTRONS
FUEL ELEMENTS
FUELS
HEAVY WATER MODERATOR
NEUTRON FLUX
PHYSICS
PLANNING
RESEARCH REACTORS
SOLIDS
THERMAL NEUTRONS
ZONES