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Primary view of Evaluation of storing Shippingport Core II spent blanket fuel assemblies in the T Plant PWR Core II fuel pool without active cooling
Gilbert, E. R.; Lanning, D. D.; Dana, C. M. & Hedengren, D. C.
October 1, 1994
Primary view of Safety Analysis Report for Packaging: The unirradiated fuel shipping container USA/9853/AF
unknown creator
October 18, 1991
Primary view of Effect of sweep gas composition on ionization chamber response in the BEATRIX-II tritium recovery experiment
Slagle, O. D.; Hollenberg, G. W. & Baker, D. E.
October 1, 1992
Primary view of An assessment of testing requirement impacts on nuclear thermal propulsion ground test facility design
Shipers, L. R.; Ottinger, C. A. & Sanchez, L. C.
October 25, 1993
Primary view of Nonswelling behavior of HT9 alloy irradiated to high exposure
Pitner, A. L.; Hecht, S. L. & Trenchard, R. G.
October 1, 1993
Primary view of Tests to determine effect of humidity on high-efficiency filters when installed horizontally
Palmer, J.H.
October 4, 1960
Primary view of Special hazards report - I E fuel loads
Brown, J.H.; Fullmer, G.C.; Trumble, R.E. & VanWormer, F.W.
October 15, 1957
Primary view of Radiation damage study on the lithium hydride SNAP shield
Doctor, R.D.
October 4, 1961
Primary view of P Division monthly report, September 1949
Lee, E.P.
October 6, 1949
Primary view of Characterization of spent fuel approved testing material: ATM-106
Guenther, R.J.; Blahnik, D.E.; Campbell, T.K.; Jenquin, U.P.; Mendel, J.E. & Thornhill, C.K.
October 1, 1988
Primary view of Postirradiation examination of capsule GF-4. [HTGR]
Kovacs, W.J. & Sedlak, B.J.
October 1, 1980
Primary view of Thermal-hydraulic studies on molten core-concrete interactions
Greene, G.A.
October 1, 1986
Primary view of Thermal-hydraulic response and iodine transport during a steam generator tube rupture
Callow, R.A.
October 1, 1988
Primary view of Fluid composition in the tube sheet crevices of a nuclear steam generator
Weres, O. & Tsao, L.
October 1, 1985
Primary view of Surface radiation properties between nuclear reactor materials in contact. [LMFBR core disruptive accident]
Chan, S.H. & Tseng, H.H.
October 18, 1978
Primary view of Heat transfer from internally-heated molten UO/sub 2/ pools. [PWR; BWR]
Stein, R.P.; Baker, L. Jr.; Gunther, W.H. & Cook, C.
October 10, 1978
Primary view of FX2-TH: A Two-Dimensional Nuclear Reactor Kinetics Code With Thermal-Hydraulic Feedback
Shober, R. A.; Daly, T. A. & Ferguson, D. R.
October 1, 1978
Primary view of Improved algorithms for the calculation of resolved resonance cross sections with applications to the structural Doppler effect in fast reactors
Hwang, R.N.; Toppel, B.J. & Henryson, H. II
October 1, 1980
Primary view of Aging degradation of cast stainless steel
Chopra, O.K. & Chung, H.M.
October 1, 1985
Primary view of Environmentally assisted cracking in light water reactors
Shack, W.J.; Kassner, T.F.; Maiya, P.S.; Park, J.Y. & Ruther, W.E.
October 1, 1988
Primary view of BWR pipe crack remedies evaluation
Shack, W.J.; Kassner, T.F.; Maiya, P.S.; Park, J.Y. & Ruther, W.E.
October 1, 1986
Primary view of ELAF failed fuel plate examination. [Extended Life Aluminide Fuel]
Beeston, J.M.; Miller, L.G.; Brown, K.R. & McGinty, D.M.
October 1, 1984
Primary view of Irradiation-induced sensitization of austenitic stainless steel in-core components
Chung, H.M.; Sanecki, J.E.; Ruther, W.E. & Kassner, T.F.
October 1, 1990
Primary view of Technical basis for hydrogen-water chemistry: Laboratory studies of water chemistry effects on SCC (stress-corrosion-cracking)
Kassner, T.F.; Ruther, W.E. & Soppet, W.K.
October 1, 1986