Open AccessHigh Flux Isotope Reactor: A General Description
Author(s) -
Thomas E. Cole
Publication year - 1960
Language(s) - English
Resource type - Reports
DOI - 10.2172/4128672
Subject(s) - neutron flux , nuclear engineering , research reactor , beryllium , burnup , oak ridge national laboratory , nuclear reactor core , flux (metallurgy) , irradiation , heat flux , control rod , materials science , light water reactor , heat transfer , nuclear physics , neutron , physics , thermodynamics , metallurgy , engineering
The High Flax lsotope Reactor (HFIR) is being planned for construction at Oak Ridge National Laboratory as a supporting facility in the program of investigation of the properties of the transplutonium elements. The reactor will be a flux-trap reactor consisting of a berylliumrefiected, light-water-cooled annular fuel region surroundin g a light-water island. An irradiation sample of 200 to 300 g of Pu/sup 242/ will be placed in the island where a thermalneutron flux of approximately 3 x 10/sup 15/ n/cm/sup 2//sec can be achieved on the average during an irradiation period of about 1 year. It is estimated that more than 100 mg of Cf/sup 252/ will be produced by such an irradiation. In addition to the central irradiation facility for heavy-element production, the HIKIR will have eight hydraulic rabbit tubes located in the beryllium refiector and four beam holes for basic research. Preliminary design of the reactor was based on the results of a parametric study of the dimensions of the island and fuel region, heat-removal rates, and fuel loading on the achievable thermal-neutron fluxes in the island and reflector. A research and development program ding critical experiments, heat transfer, corrosion, a clufuel element studies has been in progress to verify the important parameters used in the design. The present design results in an average power density of 2.2 Mw/l in the active core and requires a maximum heat-transfer rate from fuel-plate surfaces of 1.5 x 10/ sup 6/ Btu/ft/sup 2//hr. This heattransfer rate is achieved by flowing H/sub 2/ O, at an inlet temperature of 120 F, and a pressure of 600 to 900 psig, through the 0.05-in. coolant channels at a velocity of 40 fps. A preliminary analysis of the hazards brought on by a reactor core meltdown shows that a controlled-leakage, filter-scrubber, stack release system of the ORR type will limit the consequences of such an accident to an acceptable degree. Construction is scheduled to start in early 1961 with operation at power scheduled for Jan. 1964. The estimated cost of the facility including engineering i