13 Matching Results
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1 - 13 of
13
Procedure for the estimation of carbon oxidation rates in porous spent oil shale. [Based on free stream oxygen concentration and temperature]
None
Date:
September 27, 1974
Creator:
Tyler, A.L.
Object Type:
Report
System:
The UNT Digital Library
Shield design for a mirror Fusion Research Facility (FERF)
None
Date:
June 27, 1974
Creator:
Wilcox, T.P.
Object Type:
Article
System:
The UNT Digital Library
Parametric survey for the linear two-component system
None
Date:
September 27, 1974
Creator:
Heckrotte, W.; Hiskes, J.R. & Freis, R.P.
Object Type:
Article
System:
The UNT Digital Library
Neutrino flow and the collapse of stellar cores
None
Date:
December 27, 1974
Creator:
Wilson, J. R.
Object Type:
Article
System:
The UNT Digital Library
Instability during monoenergetic neutral injection into a target plasma
None
Date:
December 27, 1974
Creator:
Fowler, T.K.
Object Type:
Report
System:
The UNT Digital Library
Recovery and purification of americium-241 from an aluminum--americium oxide mixture
None
Date:
May 27, 1974
Creator:
Proctor, S. G.
Object Type:
Report
System:
The UNT Digital Library
Helium doping of niobium with tritium
None
Date:
February 27, 1974
Creator:
Hickman, R. G.
Object Type:
Article
System:
The UNT Digital Library
Extrapolation of the ISABELLE design to 400 x 400 GeV
None
Date:
June 27, 1974
Creator:
Chasman, R. & Gluckstern, R. L.
Object Type:
Report
System:
The UNT Digital Library
Rocky Flats model 2030-1 container (AEC--AL USA/5332/BLF) safety analysis report for packaging (SARP)
Division, Dow Chemical U.S.A., for shipping unirradiated fissile material in solid form. Components consist of a 30-gal steel drum, Celotex insulation, and stainless steel containment vessel(s) of 10-in. dia. A simple venting system prevents rtupture of the outer drum in the event of accidental fire. Approved material limits include 5 kg of plutonium or 11 kg of enriched uranium. Thermal decay energy is normally limited to 20 W. Results of extensive tests show the container will function effectively when exposed to all environment and accident conditions as required. The containment vessel temperature rise will not exceed 140 deg F during the thermal test. Internal heating of 20 W will cause an additional temperature rise of 80 deg F. (auth)
Date:
February 27, 1974
Creator:
Adcock, Frank E.; McCarthy, John D. & Wackler, William F.
Object Type:
Report
System:
The UNT Digital Library
Production and waste management division waste status summary. Progress report, 1 July 1974--30 September 1974
None
Date:
November 27, 1974
Creator:
Anderson, J. D.
Object Type:
Report
System:
The UNT Digital Library
Preparation of thin actinide targets for the synthesis of the transactinide elements
None
Date:
September 27, 1974
Creator:
Lougheed, R. & Hulet, E. K.
Object Type:
Article
System:
The UNT Digital Library
Low Temperature and Neutron Physics Studies. Progress Report, September 1973--August 1974
None
Date:
August 27, 1974
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Heat of formation of plutonium hydride
None
Date:
May 27, 1974
Creator:
Oetting, Franklin L. & Horrell, David R.
Object Type:
Report
System:
The UNT Digital Library