Item Details

Hazards Summary Report for the GCRE Critical-Assembly Experiments

by William S. Hogan ... [et al.]
Format
Book; Government Document; Online; EBook
Published
Columbus, OH : Battelle Memorial Institute, [1958]
Language
English
Variant Title
Hazards summary report for the Gas cooled reactor experiment critical-assembly experiments
Related Title
Technical Report Archive & Image Library (TRAIL)
Series
UC (Series). 81, Reactors - Power
TID
BMI
SuDoc Number
Y 3.At 7:22/BMI-1240 Rev.
Abstract
Critical experiments are described, and the hazards attendant to these experiments are evaluated for a gascooled water-moderated reactor design. Shutdown control of the critical assembly is achieved by cadmium control blades and by dumping the water into a storage tank. The maximum normal rats of reactivity addition is limited to an estimated 0.04 per cent per sec for all remotely controlled operations. The system is interlocked to insure that safe operational procedures are followed, Hazard calculations are made to determine the dosage from direct radiation, fall-out, and inhalation from a radioactive cloud resulting from an accident. The exclusion area is shown to be adequate for even the maximum hypothetical accident. (auth).
Description
1 v. (various pagings) : ill. ; 28 cm.
Mode of access: Internet.
Notes
  • "Contract No. W-7405-eng-92."
  • "UC-81 Reactors - Power (TID-4500, 13th Ed., Rev.)."
  • "July 22, 1958."
  • "Report No. BMI-1240 (Rev.)."
Series Statement
TID 4500 13th ed., Rev
BMI ; 1240 Rev
Logo for No Copyright - United StatesNo Copyright - United States
Technical Details

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    a| BMI ; v| 1240 Rev.
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    a| Critical experiments are described, and the hazards attendant to these experiments are evaluated for a gascooled water-moderated reactor design. Shutdown control of the critical assembly is achieved by cadmium control blades and by dumping the water into a storage tank. The maximum normal rats of reactivity addition is limited to an estimated 0.04 per cent per sec for all remotely controlled operations. The system is interlocked to insure that safe operational procedures are followed, Hazard calculations are made to determine the dosage from direct radiation, fall-out, and inhalation from a radioactive cloud resulting from an accident. The exclusion area is shown to be adequate for even the maximum hypothetical accident. (auth).
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    a| Work performed by the Battelle Memorial Institute b| Contract W-7405-eng-92 with the U.S. Atomic Energy Commission.
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    a| Mode of access: Internet.
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    a| Nuclear energy x| Safety measures.
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    a| Nuclear facilities x| Risk assessment.
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    a| Gas cooled reactors x| Risk assessment.
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    a| Jankowski, Francis J.
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    a| Hogan, William S.
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    b| MIU c| GWLA d| 20180914 s| google u| mdp.39015095118546 y| 1958 r| pd q| bib

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