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Molten salt reactor experiment

Other applications of zirconium tetrafluoride are in molten salt reactor experiments as a catalyst for the fluorination of chloroacetone to chlorofluoroacetone (17,18) as a catalyst for olefin polymerization (19) as a catalyst for the conversion of a mixture of formaldehyde, acetaldehyde, and ammonia (in the ratio of 1 1 3 3) to pyridine (20) as an inhibitor for the combustion of NH CIO (21) in rechargeable electrochemical cells (22) and in dental applications (23) (see Dentalmaterials). [Pg.262]

Table 14. Molten salt reactor experiment materials [53,54]... Table 14. Molten salt reactor experiment materials [53,54]...
Haubenreich, P.N. and Engel, J.R., Experience with the molten-salt reactor experiment, Nucl. Appl. Tech., 1970, 8, 118 136. [Pg.481]

Molten Salt Reactor Experiment showed that salt and graphite are compatible... [Pg.30]

E. L. Compere et al., Fission Product Behavior in the Molten Salt Reactor Experiment, ORNL-4865, Oak Ridge National Laboratory (1975). [Pg.102]

Another problem is corrosion due to the hot fluoride melt. Previous experience with the Molten Salt Reactor Experiment (MSRE) at the Oak Ridge National Laboratory (Weinberg 1970) seem to indicate, however, that these problems can be overcome. [Pg.2653]

A representative application of the MSR concept is thorium reactor, and MSRE (Molten-Salt Reactor Experiment) with thermal output of 8 MW was developed by Oak Ridge National Laboratory in the USA and had been operated from 1966 to 1969. In the thorium reactor, the breeding of fissile nuclide, can be achieved through prevention of parasitic absorption by... [Pg.2702]

Several fluid-fueled reactors have been built and operated as experiments. The concept is that fuel is contained within the coolant. Systems of this type include aqueous fuel systems, liquid metal-fueled systems, molten salt systems, and gaseous suspension systems. The homogeneous reactor experiment was constructed and operated at Oak Ridge Nahonal Laboratory, as was the Molten-Salt Reactor experiment. A liquid metal fuel reactor experiment was operated at Brookhaven National Laboratory. Power reactors of this type have not been built. [Pg.6]

Haubenreich, P.N. and Engle, J.R. 1970. Experience with the Molten Salt Reactor Experiment. Nuc. App. Tech. 8,118-136. [Pg.287]

Tech. 1970) during the operation of the Molten Salt Reactor Experiment showed that only the noble gases (Xe, Kr) and tritium are released to the cover gas. Most fission products are dissolved in the molten salt (CsF, SrF2, BeE) although some exist as metals and tend to deposit on metallic surfaces (Ag and others). This barrier to the release of radionuclides reduces the fuel quality requirements. [Pg.11]

ORNL Molten Salt Reactor Experiment Power level 8 MW(t) Fuel Salt Li/Be/F Clean Salt Na/Be/F... [Pg.6]

The Molten Salt Reactor Experiment Demonstrated the Concept... [Pg.7]

The Aircraft Reactor Experiment, a 2.5-MW(th) reactor, operated in the 1950s with a NaF/ZrF4molten salt, while the Molten Salt Reactor Experiment, an 8-MW(th) reactor, operated in the 1960s with a EiF/BeF2 molten salt. In these reactors, the fuel was dissolved in the salt whereas the AHTR uses solid fuel with a clean molten salt. Detailed studies will be required to determine the preferred composition of the fluoride salt. All of the candidate fluoride salts have somewhat similar properties. Preliminary nuclear calculations used Ei2BeF4 because its properties are well known. [Pg.7]

Molten Salt Reactor Experiment [8 MW(t)] Postirradiation Graphite ... [Pg.21]

The Molten Salt Reactor Experiment Demonstrated Molten Salt Fueled Reactors And Intermediate Clean-Salt Heat-Transfer Loops... [Pg.61]


See other pages where Molten salt reactor experiment is mentioned: [Pg.457]    [Pg.457]    [Pg.184]    [Pg.478]    [Pg.478]    [Pg.457]    [Pg.457]    [Pg.225]    [Pg.466]    [Pg.8]    [Pg.241]    [Pg.9]    [Pg.23]    [Pg.27]    [Pg.11]    [Pg.14]    [Pg.26]    [Pg.29]    [Pg.2666]    [Pg.631]    [Pg.3]    [Pg.21]    [Pg.62]    [Pg.157]    [Pg.184]   
See also in sourсe #XX -- [ Pg.457 ]

See also in sourсe #XX -- [ Pg.457 ]

See also in sourсe #XX -- [ Pg.457 ]

See also in sourсe #XX -- [ Pg.2653 , Pg.2666 , Pg.2702 ]

See also in sourсe #XX -- [ Pg.397 ]




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