SOME MAJOR FUEL-IRRADIATION TEST FACILITIES OF THE OAK RIDGE NATIONAL LABORATORY

Trauger, D. B.

doi:10.2172/4043196

Title: SOME MAJOR FUEL-IRRADIATION TEST FACILITIES OF THE OAK RIDGE NATIONAL LABORATORY

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Abstract

Irradiations of test fuel specimens and experimental fue elements are conducted both in capsules and in forcedconvection-cooled loops. The design of equipment suitable for irradiation tests pertinent to the development of boiling and pressurized-water, gas-cooled, sodium-cooled, and molten-salt reactors is described briefly, with particular emphasis on test capability. The capsules utilize thermal conduction through sodium or NaK, gas-filled annuli, and graphite for heat removal from the fuel element surface. Six basic designs have been employed, with many variations in conducting over 125 separate irradiation experiments. Capsule features include external pressurization to 900 psia, sweep gas for fission-gas removal, fission-gas sampling and daughter-trap collection for gamma-ray spectrometer analysis, continuous flux monitoring and control, and measurement of temperatures up to 4000 deg F. The loop facilities described are: (1) a pressurized-water loop for operation up to 2500 psia and 625 deg F with heat removal up to 300 kw; close control is provided over water chemistry; (2) two helium-cooled loops capable of operation up to a gas temperature of 1500 deg F, a system pressure of 300 psia, and fission and gamma heating of 60 kw; other coolants can be accommodated, and the loops are designed to operate with fission- product contaminationmore »« less

Authors:: Trauger, D. B.

Publication Date:: Wed Apr 01 00:00:00 EST 1964

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

OSTI Identifier:: 4043196

Report Number(s):: ORNL-3574

NSA Number:: NSA-18-019430

DOE Contract Number:: W-7405-ENG-26

Resource Type:: Technical Report

Resource Relation:: Other Information: Orig. Receipt Date: 31-DEC-64

Country of Publication:: United States

Language:: English

Subject:: REACTOR TECHNOLOGY; CAPSULES; CHEMICAL REACTIONS; CONTAMINATION; CONTROL; ECONOMICS; FISSION; FISSION PRODUCTS; FLUID FLOW; FUEL ELEMENTS; FUELS; FUSED SALT FUEL; GAMMA RADIATION; GAMMA SPECTROMETERS; GAS COOLANT; GASES; GRAPHITE; HEAT TRANSFER; HEATING; HELIUM; HIGH TEMPERATURE; IN PILE LOOPS; INSTRUMENTS; IRRADIATION; MATERIALS TESTING; MEASURED VALUES; MONITORING; NEUTRON FLUX; OPERATION; PLANNING; POTASSIUM ALLOYS; PRESSURE; REACTORS; SAFETY; SAMPLING; SODIUM ALLOYS; SURFACES; THERMAL CONDUCTIVITY; TRAPS; VARIATIONS; WATER COOLANT

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                    Trauger, D. B. SOME MAJOR FUEL-IRRADIATION TEST FACILITIES OF THE OAK RIDGE NATIONAL LABORATORY.  United States: N. p., 1964. 
        Web.  doi:10.2172/4043196.

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                    Trauger, D. B. SOME MAJOR FUEL-IRRADIATION TEST FACILITIES OF THE OAK RIDGE NATIONAL LABORATORY.  United States.  https://doi.org/10.2172/4043196

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                    Trauger, D. B. 1964.  
        "SOME MAJOR FUEL-IRRADIATION TEST FACILITIES OF THE OAK RIDGE NATIONAL LABORATORY".  United States.  https://doi.org/10.2172/4043196.  https://www.osti.gov/servlets/purl/4043196.

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@article{osti_4043196,

  title        = {SOME MAJOR FUEL-IRRADIATION TEST FACILITIES OF THE OAK RIDGE NATIONAL LABORATORY},

  author       = {Trauger, D. B.},

  abstractNote = {Irradiations of test fuel specimens and experimental fue elements are conducted both in capsules and in forcedconvection-cooled loops. The design of equipment suitable for irradiation tests pertinent to the development of boiling and pressurized-water, gas-cooled, sodium-cooled, and molten-salt reactors is described briefly, with particular emphasis on test capability. The capsules utilize thermal conduction through sodium or NaK, gas-filled annuli, and graphite for heat removal from the fuel element surface. Six basic designs have been employed, with many variations in conducting over 125 separate irradiation experiments. Capsule features include external pressurization to 900 psia, sweep gas for fission-gas removal, fission-gas sampling and daughter-trap collection for gamma-ray spectrometer analysis, continuous flux monitoring and control, and measurement of temperatures up to 4000 deg F. The loop facilities described are: (1) a pressurized-water loop for operation up to 2500 psia and 625 deg F with heat removal up to 300 kw; close control is provided over water chemistry; (2) two helium-cooled loops capable of operation up to a gas temperature of 1500 deg F, a system pressure of 300 psia, and fission and gamma heating of 60 kw; other coolants can be accommodated, and the loops are designed to operate with fission- product contamination when necessary; (3) a compact loop design for recirculating molten-salt fuels at high temperatures. Design features to meet safety requirements, alteration of equipment to accommodate changing program needs, and factors affecting the economics of operation are discussed briefly. The close relationship needed between the irradiation test laboratory and fuel development programs is indicated. The usefulness of assistance from other related groups in a large laboratory complex is mentioned. Finally, shop facilities are described for meeting the exacting needs of irradiation capsule assembly. (auth)},

  doi          = {10.2172/4043196},

  url          = {https://www.osti.gov/biblio/4043196},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Wed Apr 01 00:00:00 EST 1964},

  month        = {Wed Apr 01 00:00:00 EST 1964}

}

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