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Title: MOLTEN-SALT REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1959

Abstract

Reactor Design Studies. A design study is being made of a 30 Mw, one- region, experimental molten-salt reactor. A preliminary design and cost estimate study was completed on a 315 Mw(e) graphite-moderated moltensalt power reactor. The effect of neutron and gammaray activity in the secondary heat exchanger of the interim design reactor using the salt mixture LiF-BeF/sub 2/ as the coolant, in place of Na, was studied. The nuclear effects of processing molten-salt fuels to remove the rare-earth flssion produets by ion exchange with CeF/sub 3/ were investigated. Investigations have been continued of salt- lubricated bearings for molten salt pumps. The modified Fulton-Sylphon bellows- mounted seal being subjected to an endurance test in a PK-P type of centrifugal pump has continued to seal satisfactorily for more than 10,000 hr of operation. Equipment for salt-to-salt heat transfer tests has been completed. A heat exchanger has been designed with which to evaluate triplex tubing for use in molten-salt or liquid metal-to-steam superheater applications. Further tests of commercial expansion joints in molten-salt lines demonstrated conclusively that such joints are not suitable. Operation of forced-circulation corrosion-testing loops eontinued. Materials Studies. Examination of three Inconel thermal- convection loops that had operated for long periods ofmore » time and one Inconel loop that had operated for 1000 hr have been completed. Mechanical property tests have been made on Inconel and INOR8 specimens that were carburized by exposure for 4000 hr at 1200 deg F in a system containing sodium and graphite. Further tests have been made in the study of the compatibility of graphite and molten- salt mixtures. The strength properties of INOR-8 at high temperatures are being investigated in tensile, creep, relaxation, and fatigue tests. Fabrication and welding and brazing studies are being made of triplex-tube heat exchangers. Studies of composites of INOR-8 and type 316 stainless steel have shown the alloys to be compatible at tempera tures up to 1800 deg F. Various means for deoxidizing and purifying ingots of INOR-8 weld metal have been studied as means for improving the ductility of INOR-8 weldments. A Nb-containing coated electrode was investigated for use in joining dissimilar metals. Molybdenumto- Inconel joints were brazed with several materials in connection with the fabrication of a pump-shaft extension. Chemistry and Radiation Damage. Phase studies are being conducted to determine whether the NaF-BeF/sub 2/-- ThF/sub 4/-- UF/sub 4/ system. Plutonium trifluoride has been found to be sufficiently soluble in LiF--BeF/sub 2/ and temperature Pu-burning reactor. The system KF- coolant. Techniques have been developed for determining the self-diffusion coefficients of Cr in Cr-- Ni alloys with Cr/sup 51/ as a radiotracer. Vapor pressures of CsF-BeF/sub 2/ are being measured to obtain values on which to base estimates of the vapor pressure of LiF--BeF/sub 2/ mixtures. Further studies have been made of gaseous aluminum chloride as a heat transfer medium. Reactorgrade graphite impregnated with LiF--MgF/sub 2/ has been tested in LiF-BeF/ sub 2/--UF/sub 4/ at 1250 deg F for 800 hr and examined for U penetration. A series of tests was run to determine the effect of thermal cycling on salt stability. Methods have been developed for synthesizing fluorides by reactions with stannous fluoride. Fuel Processing. The solubilities of fluorides of Np, corrosion products, U, and Th, were investigated to evaluate their behavior in the proposed HF dissolution process for recovering LiF-- BeF/sub 2/ salt. (For preceding period see ORNL-2626.) (W. L. H.)« less

Publication Date:
Research Org.:
Oak ridge National Lab., Tenn.
OSTI Identifier:
4275789
Report Number(s):
ORNL-2684
NSA Number:
NSA-13-009478
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
REACTORS; ALUMINUM CHLORIDES; BERYLLIUM FLUORIDES; CESIUM FLUORIDES; CHEMICAL REACTIONS; CHROMIUM; CHROMIUM 51; CHROMIUM ALLOYS; COOLANTS; CORROSION; DIFFUSION; FUELS; GASES; GRAPHITE; HEAT TRANSFER; HIGH TEMPERATURE; HYDROFLUORIC ACID; IMPREGNATION; IMPURITIES; LIQUID METAL COOLANT; MAGNESIUM FLUORIDES; MATERIALS TESTING; MEASURED VALUES; NEPTUNIUM FLUORIDES; NICKEL ALLOYS; PLUTONIUM; PLUTONIUM FLUORIDES; POROSITY; POTASSIUM FLUORIDES; PRESSURE; RADIATION EFFECTS; REPROCESSING; SALTS; SEPARATION PROCESSES; SODIUM FLUORIDES; SOLUBILITY; SOLUTIONS; STABILITY; THERMODYNAMICS; THORIUM; THORIUM FLUORIDES; TRACER TECHNIQUES; URANIUM; URANIUM TETRAFLUORIDE

Citation Formats

. MOLTEN-SALT REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1959. United States: N. p., 1959. Web. doi:10.2172/4275789.
. MOLTEN-SALT REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1959. United States. https://doi.org/10.2172/4275789
. Tue . "MOLTEN-SALT REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1959". United States. https://doi.org/10.2172/4275789. https://www.osti.gov/servlets/purl/4275789.
@article{osti_4275789,
title = {MOLTEN-SALT REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1959},
author = {},
abstractNote = {Reactor Design Studies. A design study is being made of a 30 Mw, one- region, experimental molten-salt reactor. A preliminary design and cost estimate study was completed on a 315 Mw(e) graphite-moderated moltensalt power reactor. The effect of neutron and gammaray activity in the secondary heat exchanger of the interim design reactor using the salt mixture LiF-BeF/sub 2/ as the coolant, in place of Na, was studied. The nuclear effects of processing molten-salt fuels to remove the rare-earth flssion produets by ion exchange with CeF/sub 3/ were investigated. Investigations have been continued of salt- lubricated bearings for molten salt pumps. The modified Fulton-Sylphon bellows- mounted seal being subjected to an endurance test in a PK-P type of centrifugal pump has continued to seal satisfactorily for more than 10,000 hr of operation. Equipment for salt-to-salt heat transfer tests has been completed. A heat exchanger has been designed with which to evaluate triplex tubing for use in molten-salt or liquid metal-to-steam superheater applications. Further tests of commercial expansion joints in molten-salt lines demonstrated conclusively that such joints are not suitable. Operation of forced-circulation corrosion-testing loops eontinued. Materials Studies. Examination of three Inconel thermal- convection loops that had operated for long periods of time and one Inconel loop that had operated for 1000 hr have been completed. Mechanical property tests have been made on Inconel and INOR8 specimens that were carburized by exposure for 4000 hr at 1200 deg F in a system containing sodium and graphite. Further tests have been made in the study of the compatibility of graphite and molten- salt mixtures. The strength properties of INOR-8 at high temperatures are being investigated in tensile, creep, relaxation, and fatigue tests. Fabrication and welding and brazing studies are being made of triplex-tube heat exchangers. Studies of composites of INOR-8 and type 316 stainless steel have shown the alloys to be compatible at tempera tures up to 1800 deg F. Various means for deoxidizing and purifying ingots of INOR-8 weld metal have been studied as means for improving the ductility of INOR-8 weldments. A Nb-containing coated electrode was investigated for use in joining dissimilar metals. Molybdenumto- Inconel joints were brazed with several materials in connection with the fabrication of a pump-shaft extension. Chemistry and Radiation Damage. Phase studies are being conducted to determine whether the NaF-BeF/sub 2/-- ThF/sub 4/-- UF/sub 4/ system. Plutonium trifluoride has been found to be sufficiently soluble in LiF--BeF/sub 2/ and temperature Pu-burning reactor. The system KF- coolant. Techniques have been developed for determining the self-diffusion coefficients of Cr in Cr-- Ni alloys with Cr/sup 51/ as a radiotracer. Vapor pressures of CsF-BeF/sub 2/ are being measured to obtain values on which to base estimates of the vapor pressure of LiF--BeF/sub 2/ mixtures. Further studies have been made of gaseous aluminum chloride as a heat transfer medium. Reactorgrade graphite impregnated with LiF--MgF/sub 2/ has been tested in LiF-BeF/ sub 2/--UF/sub 4/ at 1250 deg F for 800 hr and examined for U penetration. A series of tests was run to determine the effect of thermal cycling on salt stability. Methods have been developed for synthesizing fluorides by reactions with stannous fluoride. Fuel Processing. The solubilities of fluorides of Np, corrosion products, U, and Th, were investigated to evaluate their behavior in the proposed HF dissolution process for recovering LiF-- BeF/sub 2/ salt. (For preceding period see ORNL-2626.) (W. L. H.)},
doi = {10.2172/4275789},
url = {https://www.osti.gov/biblio/4275789}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {3}
}