June 2014 Most Viewed Documents for Fission And Nuclear Technologies
- Behavior of spent nuclear fuel in water pool storage
Johnson, A.B. Jr. (1977)78
- Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions]
Bomelburg, H.J. (1977)71
- Review of thorium fuel reprocessing experience
Brooksbank, R.E.; McDuffee, W.T.; Rainey, R.H. (1978)70
- Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste]
Rezvani, M.A.; Ziada, H.H. (Westinghouse Hanford Co., Richland, WA (United States)); Shurrab, M.S. (Westinghouse Savannah River Co., Aiken, SC (United States)) (1992)63
- Proceedings of the fifth annual NEA-seabed working group meeting
Anderson, D. R. [ed.] (1980)63
- Peer-review study of the draft handbook for human-reliability analysis with emphasis on nuclear-power-plant applications, NUREG/CR-1278
Brune, R.L.; Weinstein, M.; Fitzwater, M.E. (1983)56
- Graphite design handbook
Ho, F.H. (1988)41
- LWR nuclear fuel bundle data for use in fuel bundle handling
Weihermiller, W.B.; Allison, G.S. (1979)39
- Fossil superheating in geothermal steam power plants
DiPippo, R.; Khalifa, H.E.; Correia, R.J.; Kestin, J. (1978)38
- Reducing the likelihood of future human activities that could affect geologic high-level waste repositories
Not Available (1984)37
- Communication measures to bridge ten millennia. [Contains glossary]
Sebeok, T.A. (1984)30
- One-dimensional drift-flux model and constitutive equations for relative motion between phases in various two-phase flow regimes
Ishii, M. (1977)29
- Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Executive summary: main report. [PWR and BWR]
Not Available (1975)28
- Fundamental aspects of nuclear reactor fuel elements: solutions to problems
Olander, D.R. (1976)26
- Vapor-liquid equilibria for nitric acid-water and plutonium nitrate-nitric acid-water solutions
Maimoni, A. (1980)25
- Flow-induced vibration of circular cylindrical structures
Chen, S.S. (1985)24
- Composition of Insoluble Residues Generated During Spent Fuel Dissolution
Pokhitonov, Y.; Aleksandruk, V.; Bibichev, B.; Novikov, G.; Riazantsev, V.; Saprykin, V.; Rance, P. (2002)23
- Feed-pump hydraulic performance and design improvement, Phase I: research program design. Final report
Brown, W.H.; Gopalakrishnan, S.; Fehlau, R.; Thompson, W.E.; Wilson, D.G. (1982)19
- SP-100, the US Space Nuclear Reactor Power Program. Technical information report
Truscello, V.C. (1983)19
- Evaluation of methods for measuring relative permeability of anhydride from the Salado Formation: Sensitivity analysis and data reduction
Christiansen, R.L.; Kalbus, J.S. [Colorado School of Mines, Golden, CO (United States). Petroleum Engineering Dept.]; Howarth, S.M. [Sandia National Labs., Albuquerque, NM (United States)] (1997)18
Last updated on Wednesday 15 June 2016