LOCA simulation in the national research universal reactor program : postirradiation examination results for the third materials experiment (MT-3)

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100 1 ⊔ ‡aRausch, W. N. ‡eauthor.
245 1 0 ‡aLOCA simulation in the national research universal reactor program : ‡bpostirradiation examination results for the third materials experiment (MT-3) / ‡cprepared by W.N. Rausch ; prepared for Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
246 3 ⊔ ‡aL.O.C.A. simulation in the national research universal reactor program
264 ⊔ 1 ‡aWashington, D. C. : ‡bDivision of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, ‡c1984.
300 ⊔ ⊔ ‡axix, 51, 6 pages : ‡billustrations ; ‡c28 cm
336 ⊔ ⊔ ‡atext ‡btxt ‡2rdacontent
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490 0 ⊔ ‡aNUREG/CR ; ‡v3350
500 ⊔ ⊔ ‡a"PNL-4933."
500 ⊔ ⊔ ‡a"NUREG/CR-3350."
500 ⊔ ⊔ ‡a"Date published: April 1984."
500 ⊔ ⊔ ‡a"Pacific Northwest Laboratory."
504 ⊔ ⊔ ‡aIncludes bibliographical references (page 51).
536 ⊔ ⊔ ‡bNRC FIN B2277.
538 ⊔ ⊔ ‡aMode of access: Internet.
650 ⊔ 7 ‡aThermal stresses. ‡2fast ‡0(OCoLC)fst01149790
650 ⊔ 7 ‡aPressurized water reactors ‡xLoss of coolant. ‡2fast ‡0(OCoLC)fst01076032
650 ⊔ 7 ‡aNuclear fuel rods ‡xTesting. ‡2fast ‡0(OCoLC)fst01040204
650 ⊔ 7 ‡aLight water reactors ‡xAccidents. ‡2fast ‡0(OCoLC)fst00998576
650 ⊔ 0 ‡aThermal stresses.
650 ⊔ 0 ‡aLight water reactors ‡xAccidents ‡zUnited States.
650 ⊔ 0 ‡aNuclear fuel rods ‡xTesting.
650 ⊔ 0 ‡aPressurized water reactors ‡xLoss of coolant.
651 ⊔ 7 ‡aUnited States. ‡2fast ‡0(OCoLC)fst01204155
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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