<?xml version="1.0" encoding="UTF-8"?><collection xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xmlns="http://www.loc.gov/MARC21/slim" xsi:schemaLocation="http://www.loc.gov/MARC21/slim http://www.loc.gov/standards/marcxml/schema/MARC21slim.xsd"><record><leader>04189cam a2200673Ia 4500</leader><controlfield tag="001">102456904</controlfield><controlfield tag="003">MiAaHDL</controlfield><controlfield tag="005">20180827000000.0</controlfield><controlfield tag="006">m        d        </controlfield><controlfield tag="007">cr bn ---auaua</controlfield><controlfield tag="008">111004s1958    ilua     tb  f000 0 eng d</controlfield><datafield tag="019" ind1=" " ind2=" "><subfield code="a">260839805</subfield></datafield><datafield tag="027" ind1=" " ind2=" "><subfield code="a">ANL-5781</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">sdr-umn9973951861601701</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(OCoLC)755760436</subfield></datafield><datafield tag="040" ind1=" " ind2=" "><subfield code="a">LHL</subfield><subfield code="c">LHL</subfield><subfield code="d">OCLCF</subfield><subfield code="d">AZU</subfield><subfield code="d">OCLCO</subfield><subfield code="d">MNU</subfield></datafield><datafield tag="086" ind1="0" ind2=" "><subfield code="a">Y 3.AT 7:22/ANL-5781</subfield></datafield><datafield tag="088" ind1=" " ind2=" "><subfield code="a">ANL 5781</subfield></datafield><datafield tag="100" ind1="1" ind2=" "><subfield code="a">West, J. M.</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Hazard summary report on the Experimental Boiling Water Reactor (EBWR) /</subfield><subfield code="c">J. M. West[and others].</subfield></datafield><datafield tag="260" ind1=" " ind2=" "><subfield code="a">Argonne, Ill. :</subfield><subfield code="b">Argonne National Laboratory,</subfield><subfield code="c">[1958]</subfield></datafield><datafield tag="300" ind1=" " ind2=" "><subfield code="a">226 pages :</subfield><subfield code="b">illustrations, tables ;</subfield><subfield code="c">28 cm</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="a">text</subfield><subfield code="b">txt</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="a">unmediated</subfield><subfield code="b">n</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="a">volume</subfield><subfield code="b">nc</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="490" ind1="0" ind2=" "><subfield code="a">ANL (Series) ;</subfield><subfield code="v">5781</subfield></datafield><datafield tag="500" ind1=" " ind2=" "><subfield code="a">Other authors include: J. R. Dietrich, A. S. Jameson, G. A. Anderson, J. M. Harrer, and H. F. Brush.</subfield></datafield><datafield tag="500" ind1=" " ind2=" "><subfield code="a">"Operated by the University of Chicago under Contract W-31-109-eng-38."</subfield></datafield><datafield tag="500" ind1=" " ind2=" "><subfield code="a">At head of title: Argonne National Laboratory.</subfield></datafield><datafield tag="504" ind1=" " ind2=" "><subfield code="a">Includes bibliographical references.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Appendix G. Reactor support and containment structure. pp. 222.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Appendix F. Climatology. pp. 191.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Appendix E. Inherent safety of the reactor. pp. 162.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Appendix D. Evaluation of radioactive hazards to the surrounding population. pp. 139.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Appendix C. Metal-water reactions. pp. 135.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Appendix B. Hydrology and seismology. pp. 132.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Appendix A. Shutdown cooling. pp. 126.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Enumeration and evaluation of possible hazards. pp. 112.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Inherent safety of EBWR against reactivity additions. pp. 108.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Operating procedure. pp. 103.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Description of the EBWR facility. pp. 20.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Summary. pp. 12.</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Introduction. pp. 11.</subfield></datafield><datafield tag="520" ind1="3" ind2=" "><subfield code="a">In 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.</subfield></datafield><datafield tag="538" ind1=" " ind2=" "><subfield code="a">Mode of access: Internet.</subfield></datafield><datafield tag="583" ind1="1" ind2=" "><subfield code="a">digitized</subfield><subfield code="c">2014</subfield><subfield code="h">University of North Texas</subfield><subfield code="l">committed to preserve</subfield><subfield code="2">pda</subfield><subfield code="5">TXdn.010</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Pressure.</subfield><subfield code="2">fast</subfield><subfield code="0">(OCoLC)fst01075931</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Nuclear reactors</subfield><subfield code="x">Safety measures.</subfield><subfield code="2">fast</subfield><subfield code="0">(OCoLC)fst01040845</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Nuclear reactors</subfield><subfield code="x">Research.</subfield><subfield code="2">fast</subfield><subfield code="0">(OCoLC)fst01040842</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Nuclear reactors</subfield><subfield code="x">Control.</subfield><subfield code="2">fast</subfield><subfield code="0">(OCoLC)fst01040759</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Heat</subfield><subfield code="x">Transmission.</subfield><subfield code="2">fast</subfield><subfield code="0">(OCoLC)fst00953826</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Boron.</subfield><subfield code="2">fast</subfield><subfield code="0">(OCoLC)fst00836703</subfield></datafield><datafield tag="650" ind1=" " ind2="7"><subfield code="a">Boiling water reactors.</subfield><subfield code="2">fast</subfield><subfield code="0">(OCoLC)fst00835618</subfield></datafield><datafield tag="650" ind1=" " ind2="0"><subfield code="a">Boron.</subfield></datafield><datafield tag="650" ind1=" " ind2="0"><subfield code="a">Pressure.</subfield></datafield><datafield tag="650" ind1=" " ind2="0"><subfield code="a">Heat</subfield><subfield code="x">Transmission.</subfield></datafield><datafield tag="650" ind1=" " ind2="0"><subfield code="a">Nuclear reactors</subfield><subfield code="x">Safety measures.</subfield></datafield><datafield tag="650" ind1=" " ind2="0"><subfield code="a">Nuclear reactors</subfield><subfield code="x">Control.</subfield></datafield><datafield tag="650" ind1=" " ind2="0"><subfield code="a">Nuclear reactors</subfield><subfield code="x">Research.</subfield></datafield><datafield tag="650" ind1=" " ind2="0"><subfield code="a">Boiling water reactors.</subfield></datafield><datafield tag="710" ind1="2" ind2=" "><subfield code="a">Argonne National Laboratory.</subfield></datafield><datafield tag="776" ind1="0" ind2="8"><subfield code="i">Electronic version :</subfield><subfield code="t">Hazard summary report on the experimental boiling water reactor (EBWR).</subfield><subfield code="d">Lemont, Ill. : Argonne National Laboratory, [1958?]</subfield><subfield code="w">(OCoLC)652842367</subfield></datafield><datafield tag="CID" ind1=" " ind2=" "><subfield code="a">102456904</subfield></datafield><datafield tag="DAT" ind1="0" ind2=" "><subfield code="a">20170407064646.0</subfield><subfield code="b">20180827000000.0</subfield></datafield><datafield tag="DAT" ind1="1" ind2=" "><subfield code="a">20180905090618.0</subfield><subfield code="b">2024-05-13T18:32:26Z</subfield></datafield><datafield tag="CAT" ind1=" " ind2=" "><subfield code="a">SDR-UMN</subfield><subfield code="d">EX LIBRIS - ALMA</subfield><subfield code="l">prepare.pl-004-007</subfield></datafield><datafield tag="FMT" ind1=" " ind2=" "><subfield code="a">BK</subfield></datafield><datafield tag="HOL" ind1=" " ind2=" "><subfield code="0">sdr-umn9973951861601701</subfield><subfield code="a">umn</subfield><subfield code="b">SDR</subfield><subfield code="c">UMN</subfield><subfield code="p">umn.31951d03801473z</subfield><subfield code="s">UMN</subfield><subfield code="1">9973951861601701</subfield></datafield><datafield tag="974" ind1=" " ind2=" "><subfield code="b">UMN</subfield><subfield code="c">UMN</subfield><subfield code="d">20240513</subfield><subfield code="s">google</subfield><subfield code="u">umn.31951d03801473z</subfield><subfield code="y">1958</subfield><subfield code="r">pd</subfield><subfield code="q">bib</subfield><subfield code="t">US fed doc</subfield></datafield></record></collection>