LOCA simulation in NRU program : the continuous measurement of coolant liquid level during the MT-4 experiment in the NRU reactor

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088 ⊔ ⊔ ‡aNUREG/CR-3183
100 1 ⊔ ‡aMarshall, R. K. ‡eauthor.
245 1 0 ‡aLOCA simulation in NRU program : ‡bthe continuous measurement of coolant liquid level during the MT-4 experiment in the NRU reactor / ‡cprepared by R.K. Marshall [and others] ; prepared for Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
246 3 ⊔ ‡aL.O.C.A. simulation in N.R.U. program
264 ⊔ 1 ‡aWashington, D. C. : ‡bU.S. Nuclear Regulatory Commission, ‡c1983.
300 ⊔ ⊔ ‡aix, 19 pages : ‡billustrations ; ‡c28 cm
336 ⊔ ⊔ ‡atext ‡btxt ‡2rdacontent
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490 0 ⊔ ‡aNUREG/CR ; ‡v3183
500 ⊔ ⊔ ‡a"PNL-4650."
500 ⊔ ⊔ ‡a"NUREG/CR-3183."
500 ⊔ ⊔ ‡a"Date published: June 1983."
500 ⊔ ⊔ ‡aDistributed to depository libraries in microfiche.
500 ⊔ ⊔ ‡a"Pacific Northwest Laboratory."
504 ⊔ ⊔ ‡aIncludes bibliographical references.
513 ⊔ ⊔ ‡aTopical report. ‡bApril 1983.
536 ⊔ ⊔ ‡dNRC FIN B2277.
538 ⊔ ⊔ ‡aMode of access: Internet.
650 ⊔ 0 ‡aLight water reactors ‡xAccidents ‡zOntario ‡xSimulation methods.
650 ⊔ 0 ‡aPressurized water reactors ‡xLoss of coolant ‡xSimulation methods.
651 ⊔ 7 ‡aOntario. ‡2fast ‡0(OCoLC)fst01204832
700 1 ⊔ ‡aScoggin, R. A., ‡eauthor.
700 1 ⊔ ‡aMcDuffie, P. N., ‡eauthor.
700 1 ⊔ ‡aMohr, C. L., ‡eauthor.
710 2 ⊔ ‡aPacific Northwest Laboratory.
710 2 ⊔ ‡aU.S. Nuclear Regulatory Commission. ‡bOffice of Nuclear Regulatory Research. ‡bDivision of Accident Evaluation.
730 0 ⊔ ‡aTechnical Report Archive & Image Library (TRAIL)
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