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Damage Flux in Critical Assemblies
An important limitation on the design of an inpile thermionic reactor is the fast neutron irradiation damage to the insulators, which is expressed quantitatively by the energy weighted neutron flux, or damage flux. The behavior of the damage flux has been investigated for a set of hypothetical critical assemblies containing different types of fuel and different amounts of moderator. It is shown that for a given fuel, the damage flux is reduced by moderating the neutron spectrum, and for a given amount of moderator the damage flux is reduced by increasing the amount of fuel in the fuel pin. Some effects of damage flux considerations on reactor design are also shown.
Date:
October 31, 1968
Creator:
Anderson, R.C.
Object Type:
Report
System:
The UNT Digital Library
Isotopic Power Source Development
None
Date:
October 31, 1968
Creator:
Beaver, R. J. & Donnelly, R. G.
Object Type:
Report
System:
The UNT Digital Library
Protein and Enzyme Variation in Induced Mutants of Tobacco.
None
Date:
October 31, 1968
Creator:
Bhatia, C. R.; Hart, G. E. & Smith, H. H.
Object Type:
Report
System:
The UNT Digital Library
WASTE TREATMENT AND DISPOSAL SEMIANNUAL PROGRESS REPORT, JULY--DECEMBER 1966
None
Date:
August 31, 1968
Creator:
Blanco, R. E. & Parker, F. L.
Object Type:
Report
System:
The UNT Digital Library
PHYSICS DIVISION SUMMARY REPORT. Annual Review, April 1, 1966--March 31, 1967
None
Date:
August 31, 1968
Creator:
Bollinger, L. M.
Object Type:
Report
System:
The UNT Digital Library
SCALE MODEL TESTS OF A NUCLEAR ROCKET EXHAUST SCRUBBER.
None
Date:
October 31, 1968
Creator:
Boyer, K.; Fenstermacher, C.; Bryant, E. & Meier, K.
Object Type:
Report
System:
The UNT Digital Library
RECOVERY OF PLUTONIUM FROM ZPPR UNMEASURABLE WASTES. Progress Report, July 27, 1967--January 27, 1968.
None
Date:
October 31, 1968
Creator:
Bragg, R.L. & Fisher, F.D.
Object Type:
Report
System:
The UNT Digital Library
Processes Other Than Natural Turbulence Affecting Effluent Concentrations.
None
Date:
October 31, 1968
Creator:
Briggs, G. A.; Van der Hoven, I.; Engelmann, R. J. & Halitsky, J.
Object Type:
Report
System:
The UNT Digital Library
HEATING AND HEATING 2. A Program Description of a Generalized Heat Transfer Code for Solution of Transient and/or Steady-State Problems in One, Two, or Three Dimensional Cartesian or Cylindrical Coordinate Systems.
None
Date:
October 31, 1968
Creator:
Brunell, R. D.
Object Type:
Report
System:
The UNT Digital Library
FFTF Fuel Suppliers' Meeting, Richland, Washington, August 29--30, 1967.
None
Date:
October 31, 1968
Creator:
Burgess, C. A.; Hayward, B. R. & Roake, W. E.
Object Type:
Report
System:
The UNT Digital Library
PHYSICAL PROPERTIES OF MOLTEN-SALT REACTOR FUEL, COOLANT, AND FLUSH SALTS.
None
Date:
October 31, 1968
Creator:
Cantor, S. (ed.)
Object Type:
Report
System:
The UNT Digital Library
Quarterly Progress Report [on Snap-23a Project, Phase I], June 1--August 31, 1967.
None
Date:
October 31, 1968
Creator:
Cerni, S.
Object Type:
Report
System:
The UNT Digital Library
Demonstration Fuel Element Shipping Cask From Laminated Uranium Metal: Testing Program.
This paper covers the highlights of the Paducah Gaseous Diffusion Plant nondestructive and destructive testing programs performed on the "Demonstration Fuel Element Shipping Cask from Laminated Uranium Metal."
Date:
October 31, 1968
Creator:
Clifford, C. B.
Object Type:
Report
System:
The UNT Digital Library
FISSION PRODUCT METABOLISM AND RESPONSE IN LABORATORY AND DOMESTIC ANIMALS AND PLANNING STUDY FOR EVALUATION OF RADIOACTIVE CONTAMINATION OF THE FOOD CHAIN. Progress Report, January 1--December 31, 1967.
None
Date:
October 31, 1968
Creator:
Comar, C.L.
Object Type:
Report
System:
The UNT Digital Library
TESTING HEPA FILTERS FOR USE IN A HIGH NOISE LEVEL ENVIRONMENT.
None
Date:
October 31, 1968
Creator:
DeField, J.D.
Object Type:
Report
System:
The UNT Digital Library
Alkali- Metal Corrosion of High- Temperature
Report talking about Alkali- Metal Corrosion of High- Temperature
Date:
October 31, 1968
Creator:
DeVan, J. H.; Litman, A. P. & Harms, W. O.
Object Type:
Report
System:
The UNT Digital Library
Creep Mechanisms in B. C. C. Alloy Crystals
This report addresses the creep mechanisms in B. C. C. alloy crystals.
Date:
January 31, 1968
Creator:
Dodd, R. A. & Strutt, P. R.
Object Type:
Report
System:
The UNT Digital Library
[NUCLEAR PHYSICS]. Progress Report, January 1967--December 1967.
None
Date:
October 31, 1968
Creator:
Donahue, D.J.; McCullen, J.D. & McIntyre, L.C.
Object Type:
Report
System:
The UNT Digital Library
Research in Radiobiology. Annual Report of Work in Progress in the Internal Irradiation Program.
None
Date:
March 31, 1968
Creator:
Dougherty, T. F.
Object Type:
Report
System:
The UNT Digital Library
STATUS OF THE LOS ALAMOS NUCLEAR ROCKET PROGRAM.
None
Date:
October 31, 1968
Creator:
Durham, F.P.
Object Type:
Report
System:
The UNT Digital Library
HIGH-TEMPERATURE EDDY-CURRENT CRACK DETECTION.
None
Date:
October 31, 1968
Creator:
Edenborough, N.B.
Object Type:
Report
System:
The UNT Digital Library
RADIOACTIVITY STUDIES. Annual Progress Report, October 1, 1966--October 1, 1967.
None
Date:
October 31, 1968
Creator:
Eisenbud, M. & Kneip, T.J.
Object Type:
Report
System:
The UNT Digital Library
MTR REFLECTOR GRAPHITE AFTER 13 OPERATING YEARS.
None
Date:
October 31, 1968
Creator:
Fast, E.; Cohen, S. & Wheeler, G. V.
Object Type:
Report
System:
The UNT Digital Library
Comparison of Measured and Predicted Characteristics of the Elk River Reactor.
The Elk River Reactor is a second-round, ThO$sub 2$--UO$sub 2$ fueled, stainless-steel clad, boiling water reactor built by Allis-Chalmers Manufacturing Company under contract to he U.S. Atomic Energy Commission for the Rural Cooperative Power Company. One of the stated objectives of the reactor is the demonstration of of the thorium cycle. The final physics design and pre-start-up analysis were done in 1958 to 1962. The reactor was loaded in 1963, reached full power in 1964, and shut down for it first refueling in April 1966. At the time of shutdown, the core had achieved an average burn-up of 7040 Mwd/metric ton. Agreement between predicted and observed performance was excellent throughout the core life.
Date:
October 31, 1968
Creator:
Fisher, J.R. & Kendrick, E.D.
Object Type:
Report
System:
The UNT Digital Library