GCFR radial blanket and shield experiment [electronic resource]

This report presents integral neutron flux, energy spectra, and gamma-ray heating measurements made for the Radial Blanket and Shield Experiment at the ORNL Tower Shielding Facility as part of a continuing Gas Cooled Fast Breeder Reactor program. The experimental configurations were divided into fou...

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : Oak Ridge, Tenn. : Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1980.
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MARC

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245 0 0 |a GCFR radial blanket and shield experiment  |h [electronic resource] 
260 |a Oak Ridge, Tenn. :  |b Oak Ridge National Laboratory. ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 1980. 
300 |a Pages: 110 :  |b digital, PDF file. 
336 |a text  |b txt  |2 rdacontent. 
337 |a computer  |b c  |2 rdamedia. 
338 |a online resource  |b cr  |2 rdacarrier. 
500 |a Published through SciTech Connect. 
500 |a 12/01/1980. 
500 |a "ornl/tm-7237" 
500 |a Muckenthaler, F.J.; Hull, J.L.; Manning, J.J. 
520 3 |a This report presents integral neutron flux, energy spectra, and gamma-ray heating measurements made for the Radial Blanket and Shield Experiment at the ORNL Tower Shielding Facility as part of a continuing Gas Cooled Fast Breeder Reactor program. The experimental configurations were divided into four basic segments: a spectrum modifier inserted into the Tower Shielding Reactor II beam; blanket slabs consisting of either ThO/sub 2/ or UO/sub 2/ placed directly behind the spectrum modifier; an inner radial shield behind the blankets; and an outer radial shield to complete the mockup. The segments were added in sequence, with selected measurements made within and beyond each segment. The integral experiment was performed to provide verification of calculational methods and nuclear data used in designing a radial shield for the GCFR and determining the effectiveness of the design. The ThO/sub 2/ blanket measurements were needed to bracket the uncertainties in the nuclear cross sections for calculating both the neutron transmission through the blanket and the gamma-ray heating rates within the blanket. Measurements with a UO/sub 2/ blanket were included both as a reference for the ThO/sub 2/ analysis, neutron transmission through UO/sub 2/ having been successfully calculated in previous experiments, and to provide comparison information for other breeder reactor designs. 
536 |b W-7405-ENG-26. 
650 7 |a Gcfr Type Reactors.  |2 local. 
650 7 |a Breeding Blankets.  |2 local. 
650 7 |a Shields.  |2 local. 
650 7 |a Tsr-2 Reactor.  |2 local. 
650 7 |a Design.  |2 local. 
650 7 |a Gamma Radiation.  |2 local. 
650 7 |a Radiation Heating.  |2 local. 
650 7 |a Thorium Oxides.  |2 local. 
650 7 |a Uranium Dioxide.  |2 local. 
650 7 |a Actinide Compounds.  |2 local. 
650 7 |a Breeder Reactors.  |2 local. 
650 7 |a Chalcogenides.  |2 local. 
650 7 |a Electromagnetic Radiation.  |2 local. 
650 7 |a Epithermal Reactors.  |2 local. 
650 7 |a Fast Reactors.  |2 local. 
650 7 |a Fbr Type Reactors.  |2 local. 
650 7 |a Gas Cooled Reactors.  |2 local. 
650 7 |a Heating.  |2 local. 
650 7 |a Ionizing Radiations.  |2 local. 
650 7 |a Oxides.  |2 local. 
650 7 |a Oxygen Compounds.  |2 local. 
650 7 |a Radiations.  |2 local. 
650 7 |a Reactor Components.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Research And Test Reactors.  |2 local. 
650 7 |a Research Reactors.  |2 local. 
650 7 |a Test Reactors.  |2 local. 
650 7 |a Thorium Compounds.  |2 local. 
650 7 |a Uranium Compounds.  |2 local. 
650 7 |a Uranium Oxides.  |2 local. 
650 7 |a Water Cooled Reactors.  |2 local. 
650 7 |a Water Moderated Reactors.  |2 local. 
650 7 |a Specific Nuclear Reactors And Associated Plants.  |2 edbsc. 
710 2 |a Oak Ridge National Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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