On the delay time for bubble formation in water-moderated reactors.
Delay time for bubble formation associated with heating surface thermal layer formation in water moderated reactors
BOILING WATER REACTOR↗
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Water-moderated reactor concept
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Rom, F. E.↗
Study of vibration induced stresses in design of fuel-element support assembly for tungsten water-moderated nuclear reactor
Vibration tests of concentric tube fuel element support structure for Tungsten Water Moderated Reactor
Adams, D. W.↗
Precritical calculations for the 2.9 in. pitch, twmr critical assembly
Critical loadings and precritical calculations for 2.9 inch pitch core in determining feasibility of isotopically enriched tungsten water moderated reactor for use as nuclear rocket
TUNGSTEN↗
The gamma-spectrum of the experimental reactor
Gamma radiation spectrum of experimental water moderated reactor
WATER MODERATED REACTOR↗
Corrosion of aluminum in water
Corrosion and hydrogen generation of aluminum under tungsten water-moderated reactor operating conditions
WATER MODERATED REACTOR↗
Control of a nuclear reactor with a gaseous control system
Control system concept using helium 3 in water- moderated reactor
WATER MODERATED REACTOR↗
The control of a nuclear reactor using helium- 3 gas control elements
Control system for water moderated reactor using helium-3 gas
WATER MODERATED REACTOR↗
NASA tungsten reactor radiation chemistry studies Final report
Cadmium sulfate poison control solutions for tungsten water moderated reactor
WATER MODERATED REACTOR↗
Mapping a tungsten-reactor rocket engine as a guide to operation and control
Nonlinear analog simulation of tungsten water moderated reactor to obtain steady state operating maps
MAP↗
Heat liberation in reactor screens and vessels
Ionization method of measuring radiative heat transfer in water moderated reactor vessels
IONIZATION CHAMBER↗
Calculated effect of uranium distribution on reflector control effectiveness for a water-moderated power reactor
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Fox, Thomas A↗
NASA tungsten reactor radiation chemistry studies. Phase I - Experiment design
Irradiation cell design for cadmium sulfate solution stability under electron irradiation for use in tungsten water moderated reactor
IRRADIATION↗
Precritical calculations for the 3.0 in. pitch, beryllium reflected, TWMR critical assembly
Feasibility of isotopically enriched tungsten, water moderated reactor for nuclear rocket
NUCLEAR ROCKET↗
Feasibility of a chemical poison loop system
Chemical poison loop system for reactivity control of tungsten water moderated rocket reactor
REACTOR TECHNOLOGY↗
The control of a nuclear reactor using helium-3 gas control elements.
Control of water moderated nuclear reactor using neutron absorbing helium 3 gas control elements
HELIUM 3↗
Test and analysis of design of a manifold and reentrant tube assembly. Task 3A - Feasibility of a chemical poison loop system Summary report
Poison control tube and manifold system for reactivity control of tungsten water moderated rocket reactor
WATER MODERATED REACTOR↗
Application of gaseous core reactors for transmutation of nuclear waste
An acceptable management scheme for high-level radioactive waste is vital to the nuclear industry. The hazard potential of the trans-uranic actinides and of key fission products is high due to their nuclear activity and/or chemical toxicity. Of particular concern are the very long-lived nuclides whose hazard potential remains high for hundreds of thousands of years. Neutron induced transmutation offers a promising technique for the treatment of problem wastes. Transmutation is unique as a waste management scheme in that it offers the potential for "destruction" of the hazardous nuclides by conversion to non-hazardous or more manageable nuclides. The transmutation potential of a thermal spectrum uranium hexafluoride fueled cavity reactor was examined. Initial studies focused on a heavy water moderated cavity reactor fueled with 5% enriched U-235-F6 and operating with an average thermal flux of 6 times 10 to the 14th power neutrons/sq cm-sec. The isotopes considered for transmutation were I-129, Am-241, Am-242m, Am-243, Cm-243, Cm-244, Cm-245, and Cm-246.
Schnitzler, B. G.↗