Hazard summary report on the Experimental Boiling Water Reactor (EBWR) /

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088 ‡aANL 5781
100 1 ‡aWest, J. M.
245 1 0 ‡aHazard summary report on the Experimental Boiling Water Reactor (EBWR) / ‡cJ. M. West[and others].
260 ‡aArgonne, Ill. : ‡bArgonne National Laboratory, ‡c[1958]
300 ‡a226 pages : ‡billustrations, tables ; ‡c28 cm
336 ‡atext ‡btxt ‡2rdacontent
337 ‡aunmediated ‡bn ‡2rdamedia
338 ‡avolume ‡bnc ‡2rdacarrier
490 0 ‡aANL (Series) ; ‡v5781
500 ‡aOther authors include: J. R. Dietrich, A. S. Jameson, G. A. Anderson, J. M. Harrer, and H. F. Brush.
500 ‡a"Operated by the University of Chicago under Contract W-31-109-eng-38."
500 ‡aAt head of title: Argonne National Laboratory.
504 ‡aIncludes bibliographical references.
505 0 ‡aAppendix G. Reactor support and containment structure. pp. 222.
505 0 ‡aAppendix F. Climatology. pp. 191.
505 0 ‡aAppendix E. Inherent safety of the reactor. pp. 162.
505 0 ‡aAppendix D. Evaluation of radioactive hazards to the surrounding population. pp. 139.
505 0 ‡aAppendix C. Metal-water reactions. pp. 135.
505 0 ‡aAppendix B. Hydrology and seismology. pp. 132.
505 0 ‡aAppendix A. Shutdown cooling. pp. 126.
505 0 ‡aEnumeration and evaluation of possible hazards. pp. 112.
505 0 ‡aInherent safety of EBWR against reactivity additions. pp. 108.
505 0 ‡aOperating procedure. pp. 103.
505 0 ‡aDescription of the EBWR facility. pp. 20.
505 0 ‡aSummary. pp. 12.
505 0 ‡aIntroduction. pp. 11.
520 3 ‡aIn addition to the nine cross-shaped control rods which pass through vertical guide channels in the core, a secondary non-inherent safety mechanism in the form of a pressurized concentrated boric acid solution can reduce the reactivity by at least 12.5% k in about 20 seconds. With regard to inherent safety, the EBWR has a much stronger metal temperature coefficient, but a considerably weaker steam formation shutdown mechanism, than the Borax reactors. Estimates were made of the amount of reactivity which can be controlled by steam formation in the EBWR. The maximum heat flux in EBWR is believed to be below the burnout point by at least a factor of 4 to 5, based on laboratory tests with electrically heated plates. The EBWR is surrounded by a gas-tight steel building having a volume of about 400,000 ft/sup 3/ and designed to withstand an internal pressure of 15 psig. A 15,000-gal reservoir of water is suspended from the dome of the building for emergency cooling. The gas-tight building could easily withstand the internal pressure resulting from blow-down of the pressurized water in the reactor. The major design and operating features of the EBWR facility are summarized.
538 ‡aMode of access: Internet.
583 1 ‡adigitized ‡c2014 ‡hUniversity of North Texas ‡lcommitted to preserve ‡2pda ‡5TXdn.010
650 7 ‡aPressure. ‡2fast ‡0(OCoLC)fst01075931
650 7 ‡aNuclear reactors ‡xSafety measures. ‡2fast ‡0(OCoLC)fst01040845
650 7 ‡aNuclear reactors ‡xResearch. ‡2fast ‡0(OCoLC)fst01040842
650 7 ‡aNuclear reactors ‡xControl. ‡2fast ‡0(OCoLC)fst01040759
650 7 ‡aHeat ‡xTransmission. ‡2fast ‡0(OCoLC)fst00953826
650 7 ‡aBoron. ‡2fast ‡0(OCoLC)fst00836703
650 7 ‡aBoiling water reactors. ‡2fast ‡0(OCoLC)fst00835618
650 0 ‡aBoron.
650 0 ‡aPressure.
650 0 ‡aHeat ‡xTransmission.
650 0 ‡aNuclear reactors ‡xSafety measures.
650 0 ‡aNuclear reactors ‡xControl.
650 0 ‡aNuclear reactors ‡xResearch.
650 0 ‡aBoiling water reactors.
710 2 ‡aArgonne National Laboratory.
776 0 8 ‡iElectronic version : ‡tHazard summary report on the experimental boiling water reactor (EBWR). ‡dLemont, Ill. : Argonne National Laboratory, [1958?] ‡w(OCoLC)652842367
CID ‡a102456904
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