Author

L.M. Lowry

Observed names: L Lowry, L. M. Lowry, Larry Lowry, Larry M. Lowry, Lowry, L. M.

Observed institutions: Battelle, Pacific Northwest National Laboratory

OpenAlex ID: A5112509528

Tensile Properties and Annealing Characteristics of H. B. Robinson Spent Fuel Cladding

1978 · A. A. Bauer, L. M. Lowry · Nuclear Technology · 13

Evaluating strength and ductility of irradiated zircaloy, task 5

1978 · A.A. Bauer, W. J. Gallagher, et al. · Quarterly Progress Report · 10

Examination of Zircaloy-clad spent fuel after extended pool storage

1981 · E.R. Bradley, W.J. Bailey, et al. · 5

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Remote disassembly and examination of nuclear pressure vessel surveillance capsules

1977 · J.S. Perrin, E.O. Fromm, et al. · Transactions of the American Nuclear Society · 2

The Properties of CrN/Au and Cr/CrN/Au Multilayers

1994 · E. Kolawa, Donald Y.C. Lie, et al. · NASA Technical Reports Server (NASA) · 1

Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5: Quarterly Progress Report October Through December, 1977

1978 · Battelle Columbus Labs., OH (United States), Arthur Bauer, et al. · 1

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Evaluating strength and ductility of irradiated zircaloy: Task 5. Quarterly progress report, April--June 1977

1977 · A.A. Bauer, L.M. Lowry, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1

Progress on evaluating strength and ductility of irradiated Zircaloy during July through September 1975. Quarterly progress report on Task Agreement No. 61

1975 · A.A. Bauer, L.M. Lowry, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1

Mechanical Burst Properties of Irradiated and Annealed Zircaloy Fuel-Rod Cladding

1985 · Larry M. Lowry, James S. Perrin, et al.

Nuclear Regulatory Commission Report NUREG/CR-1729

1981 · Lowry, L. M., Markworth, A. J., et al. · University of North Texas Digital Library (University of North Texas)

Fittings for high-pressure burst testing of reactor component material

1980 · V. Pasupathi, Glynton Smith, et al. · Transactions of the American Nuclear Society

Remote fatigue crack growth measurement system

1979 · L.M. Lowry, H.J. Malik, et al. · Transactions of the American Nuclear Society

Effects of annealing on irradiated spent-fuel cladding. [BWR; PWR]

1978 · A.A. Bauer, L.M. Lowry, et al. · Transactions of the American Nuclear Society

Evaluating strength and ductility of irradiated Zircaloy: Task 5. Quarterly progress report, July--September 1977

1977 · A.A. Bauer, W. J. Gallagher, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

Removal of fuel from irradiated fuel-rod sections. [Mechanical drilling, vibration, and pressing method]

1976 · L.M. Lowry, J.S. Perrin, et al. · Transactions of the American Nuclear Society

Effect of temperature, strain rate, and annealing on the tensile properties of irradiated Zircaloy cladding

1976 · L.M. Lowry, J.S. Perrin, et al. · Transactions of the American Nuclear Society

Evaluating strength and ductility of irradiated zircaloy. Quarterly progress report for October--December 1975

1975 · A.A. Bauer, L.M. Lowry, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

Final report on production of Pu-238 in commercial power reactors: target fabrication, postirradiation examination, and plutonium and neptunium recovery

1975 · Battelle Columbus Labs., Ohio (USA), M Pobereskin, et al.

Postirradiation examination of NpO$sub 2$--ZrO$sub 2$ target rods. Interim progress report

1973 · Battelle Columbus Lab., Ohio (USA), L Lowry, et al.

Cleaning and Passivation of Corrosion Resisting Steels

1956 · L.M. Lowry, J. Thompson · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

Works count: 20

Citation count: 34

H-index: 3

I10-index: 2