McCoy, H.E.
Molten-salt reactor program. Semiannual progress report for period ending August 31, 19741975
Molten-salt reactor program. Semiannual progress report for period ending August 31, 19741975
AbstractAbstract
[en] Tests on the weldability and mechanical properties of Hastelloy N are reported. Transmission electron microscopy was used to characterize the microstructure of Ti-modified Hastelloy N alloys. Molten salt and steam corrosion studies are also reported. Work on chemical processing materials is concentrated on graphite. Results of studies on the extent of penetration of graphite by Bi and Bi--Li solutions at 6500C are reported. Properties of neutron-irradiated graphite are tabulated. (JGB)
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Source
McNeese, L.E.; Oak Ridge National Lab., Tenn. (USA); p. 56-98; Jun 1975
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Report
Literature Type
Progress Report
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ACTINIDE COMPOUNDS, ALKALI METAL COMPOUNDS, ALKALINE EARTH METAL COMPOUNDS, ALLOYS, BERYLLIUM COMPOUNDS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, FLUORIDES, FLUORINE COMPOUNDS, GRAPHITE MODERATED REACTORS, HALIDES, HALOGEN COMPOUNDS, IRON ALLOYS, KINETICS, LITHIUM COMPOUNDS, MOLTEN SALT COOLED REACTORS, MOLTEN SALT REACTORS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NICKEL BASE ALLOYS, POWER REACTORS, REACTION KINETICS, REACTORS, RESEARCH AND TEST REACTORS, SALTS, THERMAL REACTORS, THORIUM COMPOUNDS, TRANSITION ELEMENT ALLOYS, URANIUM COMPOUNDS, URANIUM FLUORIDES
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Hightower, J.R. Jr.
Molten-salt reactor program. Semiannual progress report for period ending August 31, 19741975
Molten-salt reactor program. Semiannual progress report for period ending August 31, 19741975
AbstractAbstract
[en] Progress is reported on the development of processes for the isolation of protactinium and for the removal of fission products from molten-salt breeder reactors. The metal transfer experiment MTE-3 (for removing rare earths from MSRE fuel salt) was completed and the equipment used in that experiment was examined. The examination showed that no serious corrosion had occurred on the internal surfaces of the vessels, but that serious air oxidation occurred on the external surfaces of the vessels. Analyses of the bismuth phases indicated that the surfaces in contact with the salts were enriched in thorium and iron. Mass transfer coefficients in the mechanically agitated nondispersing contactors were measured in the Salt/Bismuth Flow-through Facility. The measured mass transfer coefficients are about 30 to 40 percent of those predicted by the preferred literature correlation, but were not as low as those seen in some of the runs in MTE-3. Additional studies using water--mercury systems to simulate molten salt-bismuth systems indicated that the model used to interpret results from previous measurements in the water--mercury system has significant deficiencies. Autoresistance heating studies were continued to develop a means of internal heat generation for frozen-wall fluorinators. Equipment was built to test a design of a side arm for the heating electrode. Results of experiments with this equipment indicate that for proper operation the wall temperature must be held much lower than that for which the equipment was designed. Studies with an electrical analog of the equipment indicate that no regions of abnormally high current density exist in the side arm. (JGB)
Primary Subject
Secondary Subject
Source
McNeese, L.E.; Oak Ridge National Lab., Tenn. (USA); p. 99-132; Jun 1975
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Report
Literature Type
Progress Report
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Ferris, L.M.
Molten-salt reactor program. Semiannual progress report for period ending August 31, 19741975
Molten-salt reactor program. Semiannual progress report for period ending August 31, 19741975
AbstractAbstract
[en] Research and development activities dealing with the chemical problems related to design and ultimate operation of molten-salt reactor systems are described. An experimental test stand was constructed to expose metallurgical test specimens to Te2 vapor at defined temperatures and deposition rates. To better define the chemistry of fluoroborate coolant, several aspects are being investigated. The behavior of hydroxy and oxy compounds in molten NaBF4 is being investigated to define reactions and compounds that may be involved in corrosion and/or could be involved in methods for trapping tritium. Two corrosion products of Hastelloy N, Na3CrF6 and Na5Cr3F14, were identified from fluoroborate systems. The evaluation of fluoroborate and alternate coolants continued. Research on the behavior of hydrogen and its isotopes is summarized. The solubilities of hydrogen, deuterium, and helium in Li2BeF4 are very low. The sorption of tritium on graphite was found to be significant (a few milligrams of tritium per kilogram of graphite), possibly providing a means of sequestering a portion of the tritium produced. Development of analytical methods continued with emphasis on voltammetric and spectrophotometric techniques for the in-line analysis of corrosion products such as Fe2+ and Cr3+ and the determination of the U3+/U4+ ratio in MSBR fuel salt. Similar studies were conducted with the NaBF4--NaF coolant salt. Information developed during the previous operation of the CSTF has been assessed and used to formulate plans for evaluation of in-line analytical methods in future CSTF operations. Electroanalytical and spectrophotometric research suggests that an electroactive protonic species is present in molten NaBF4--NaF, and that this species rapidly equilibrates with a volatile proton-containing species. Data obtained from the CSTF indicated that tritium was concentrated in the volatile species. (JGB)
Primary Subject
Source
McNeese, L.E.; Oak Ridge National Lab., Tenn. (USA); p. 20-55; Jun 1975
Record Type
Report
Literature Type
Progress Report
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Country of publication
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBON, ELEMENTS, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, GRAPHITE MODERATED REACTORS, HYDROGEN ISOTOPES, ISOTOPES, LIGHT NUCLEI, MOLTEN SALT COOLED REACTORS, MOLTEN SALT REACTORS, NONMETALS, NUCLEI, ODD-EVEN NUCLEI, POWER REACTORS, RADIOISOTOPES, REACTORS, RESEARCH AND TEST REACTORS, SALTS, THERMAL REACTORS, YEARS LIVING RADIOISOTOPES
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Engel, J.R.
Molten-salt reactor program. Semiannual progress report for period ending August 31, 19741975
Molten-salt reactor program. Semiannual progress report for period ending August 31, 19741975
AbstractAbstract
[en] Information is presented concerning the development and performance testing of MSBR systems and components. Failure modes and safety aspects of MSBRs are analyzed. (DCC)
Primary Subject
Source
McNeese, L.E.; Oak Ridge National Lab., Tenn. (USA); p. 1-19; Jun 1975
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Report
Literature Type
Progress Report
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