Search results for: Loss, F. J.
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1
Significance of warm prestress to crack initiation during thermal shock
Authors: Loss, F. J.
Published: Naval Research Laboratory, 1977Physical Description: iii, 22 pages : illustrations ; 26 cm.Holdings: Loading…
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2
Investigation of warm prestress for the case of small [delta]T during a reactor loss-of-coolant accident
Authors: Loss, F. J.
Published: Naval Research Laboratory ; Available from National Technical Information Service, 1978Physical Description: iii, 22 pages : illustrations ; 27 cm.Holdings: Loading…
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3
Structural integrity of water reactor pressure boundary components : quarterly progress report, January-March 1980
Published: Naval Research Laboratory : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; National Technical Information Service, 1980Other Authors: “…Loss, F. J.…”
Physical Description: iv, 67 pages : illustrations ; 28 cm.Holdings: Loading…
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4
Structural integrity of water reactor pressure boundary components : progress report ending 31 May 1977
Published: Naval Research Laboratory ; National Technical Information Service [distributor], 1977Other Authors: “…Loss, F. J.…”
Physical Description: iii, 45 pages : illustrations ; 27 cm.Holdings: Loading…
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5
Structural integrity of water reactor pressure boundary components : progress report ending 28 February 1977
Published: Naval Research Laboratory, 1977Other Authors: “…Loss, F. J.…”
Physical Description: iii, 53 pages : illustrations ; 27 cm.Holdings: Loading…
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6
Structural integrity of water reactor pressure boundary components : progress report ending 31 August 1977
Published: Naval Research Laboratory, 1978Other Authors: “…Loss, F. J.…”
Physical Description: iii, 38 pages : illustrations ; 27 cm.Holdings: Loading…
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7
Structural integrity of water reactor pressure boundary components : quarterly progress report, April-June 1979
Published: Naval Research Laboratory ; Available from National Technical Information Service, 1979Other Authors: “…Loss, F. J.…”
Physical Description: iii, 66 pages : illustrations ; 27 cm.Holdings: Loading…
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8
Structural integrity of water reactor pressure boundary components : progress report ending 30 November 1977
Published: Naval Research Laboratory ; Available from National Technical Information Service, 1978Other Authors: “…Loss, F. J.…”
Physical Description: iii, 34 pages : illustrations ; 27 cm.Holdings: Loading…
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9
Proceedings of the Second CSNI Workshop on Ductile Fracture Test Methods : held at Paris, France, April 17-19, 1985
Published: The Commission, 1988Other Authors: “…Loss, F. J.…”
Physical Description: ix, 339 pages : illustrations ; 28 cm.Holdings: Loading…
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10
Structural integrity of water reactor pressure boundary components
Published: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1983Other Authors: “…Loss, F. J.…”
Physical Description: volumes : illustrations ; 28 cmHoldings: Loading…
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11
Alternative procedures for J-R curve determination
Authors: Hiser, A. L.Other Authors: “…Loss, F. J.…”
Published: The Commission, 1983
Physical Description: ix, 70 pages : illustrations ; 28 cmHoldings: Loading…
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12
Elastic-plastic fracture test methods : the user's experience : a symposium
Published: ASTM, 1985Other Authors:Physical Description: 424 pages : illustrations ; 24 cm.Holdings: Loading…
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13
Elastic-plastic fracture mechanics technology
Published: ASTM, 1985Other Authors:Physical Description: 178 pages : illustrations ; 24 cm.Holdings: Loading…
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Related Subjects
Nuclear pressure vessels
Testing
Materials
Metals
Dynamic testing
Fatigue
Fracture
Fracture mechanics
Light water reactors
Steel
Design and construction
Ductility
Effect of radiation on
Elasticity
Elastoplasticity
Loss of coolant
Plasticity
Pressurized water reactors
Safety measures
Steel, Structural
Stress-strain curves