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Donald L. Hagrman

Observed names: D Hagrman, D. Hagrman, D. L. Hagrman, D.L. Hagrman, Hagrman, D L, Hagrman, D. L. (EG and G Idaho, Inc., Idaho Falls, ID (USA)), Hagrman, D.L., Hagrman, Donald L., Hagrman, Donald L., author., Hagrman, Donald L., compiler.
OpenAlex ID: A5046528148
MATPRO-Version 11: a handbook of materials properties for use in the analysis of light water reactor fuel rod behavior
1979 · D.L. Hagrman, G.A. Reymann · 199
SCDAP/RELAP5/MOD 3.1 code manual: MATPRO, A library of materials properties for Light-Water-Reactor accident analysis. Volume 4
1995 · Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology, D Hagrman, et al. · 89
Power Burst Facility (PBF) severe fuel damage test 1-4 test results report
1989 · D.A. Petti, Z.R. Martinson, et al. · 60
A handbook of materials properties for use in the analysis of light water reactor fuel rod behavior
1979 · D.L. Hagrman · Medical Entomology and Zoology · 56
Review of Experimental Results on Light Water Reactor Core Melt Progression
1991 · Richard R. Hobbins, David A. Petti, et al. · Nuclear Technology · 45
Fission Product Release from Fuel under Severe Accident Conditions
1993 · Richard R. Hobbins, David A. Petti, et al. · Nuclear Technology · 26
MELCOR aerosol transport module modification for NSSR-1
1996 · Lockheed Idaho Technologies Co., Idaho Falls, ID (United States), B Merrill, et al. · 12
The Composition of Aerosols Generated During a Severe Reactor Accident: Experimental Results from the Power Burst Facility Severe Fuel Damage Test 1-4
1994 · David A. Petti, Richard R. Hobbins, et al. · Nuclear Technology · 9
Summary of oxidation driven mobilization data and their use in fusion safety assessments
1996 · K.A. McCarthy, G.R. Smolik, et al. · Journal of Nuclear Materials · 8
Severe core damage and associated in-vessel fission product release
1987 · C. Allison, J. Rest, et al. · Progress in Nuclear Energy · 8
Assessment of CONTAIN and MELCOR for performing LOCA and LOVA analyses in ITER
1994 · B Merrill, USDOE, Washington, DC (United States), et al. · 7
Dose Due to Mobilization of Vanadium Alloy Activation Products
1996 · Kathryn A. McCarthy, Galen R. Smolik, et al. · Fusion Technology · 6
Investigation of the coolability of a continuous mass of relocated debris to a water-filled lower plenum. Technical report
1994 · Idaho National Engineering Lab., Idaho Falls, ID (United States), J Rempe, et al. · 5
Nuclear-Magnetic-Resonance Study of the Hydrogen Nucleus in O H− in the Potassium Chloride Lattice
1971 · Donald L. Hagrman, W. D. Ohlsen · Physical review. B, Solid state · 5
Volatilization from PCA Steel Alloy
1996 · D. L. Hagrman, G. R. Smolik, et al. · Fusion Technology · 4
Mobilization Processes from Vanadium Alloys During Oxidation
1996 · G. R. Smolik, D. L. Hagrman, et al. · Fusion Technology · 3
Fission Product Release as a Function of Chemistry and Fuel Morphology
2020 · R. R. Hobbins, D. J. Osetek, et al. · CRC Press eBooks · 2
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Estimates of Activation Product Transport Through ITER Confinement Barriers
1996 · D.A. Petti, D. L. Hagrman · Fusion Technology · 2
An Experimental Study of Twin-Wire Electric Arc Sprayed Zinc and Aluminum Coatings
1996 · D.J. Varacalle, D.L. Hagrman, et al. · Thermal spray · 2
Cobalt release from PCA steel during possible fusion reactor accidents
1995 · G.R. Smolik, K.A. McCarthy, et al. · University of North Texas Digital Library (University of North Texas) · 2
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In situ vitrification model development and implementation plan
1990 · R.J. MacKinnon, P.E. Murray, et al. · 2
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Influence of zircaloy oxidation and melting behavior on core behavior during a severe accident
1984 · C.M. Allison, D.L. Hagrman, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
PBF LOCA test LOC-6 fuel-behavior report. [PWR]
1983 · T.M. Broughton, K. Vinjamuri, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
Fission product release from fuel under severe-accident conditions
1991 · R.R. Hobbins, David A. Petti, et al. · Transactions of the American Nuclear Society · 1
SCDAP/RELAP5 code extensions for modeling vapor source rates in Savannah River Site reactors
1989 · D Hagrman · 1
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Works count: 59
Citation count: 562
H-index: 8
I10-index: 7
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