High Flux Isotope Reactor: A General Description

Technical Report · Tue Mar 15 00:00:00 EST 1960

DOI:https://doi.org/10.2172/4128672· OSTI ID:4128672

Cole, T. E. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

The High Flux 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 beryllium reflected, light-water-cooled annular fuel region surrounding a light-water island. An irradiation sample of 200 to 300 g of Pu²⁴² will be placed in the island where a thermal neutron flux of approximately 3 x 10¹⁵ n/cm²/sec can be achieved on the average during an irradiation period of about 1 year. It is estimated that more than 100 mg of Cf²⁵² 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 reflector 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 fuel 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 10⁶ Btu/ft²/hr. This heat transfer rate is achieved by flowing H²O, 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 is $12,000,000.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-14-026500
• OSTI ID: 4128672
• Report Number(s): CF-60-3-33
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-60
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACCIDENTS
BERYLLIUM MODERATOR
CALIFORNIUM 252
CORROSION
CRITICALITY
ECONOMICS
HEAT TRANSFER
HFIR
HYDRAULICS
IRRADIATION
LIQUID FLOW
MELTING
NEUTRON FLUX
PLUTONIUM 242
POWER
PRESSURE
PRODUCTION
REACTOR CORE
REACTOR SAFETY
REFLECTORS
RESEARCH REACTORS
VELOCITY
WATER COOLANT
ZONES
Nuclear Criticality Safety Program (NCSP)
Criticality
Corrosion
Californium
Heat Transfer
Transplutonium
Beryllium
Flux-Trap Reactor
High Flux Isotope Reactor