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Roussanov, A.; Troyanov, V.; Jachmenev, G.; Demishonkov, A.
Advisory group meeting on design and performance of reactor and subcritical blanket systems with lead and lead-bismuth as coolant and/or target material. Working material2001
Advisory group meeting on design and performance of reactor and subcritical blanket systems with lead and lead-bismuth as coolant and/or target material. Working material2001
AbstractAbstract
[en] The corrosion resistance study of structure materials in liquid Pb, Bi and Pb-Bi have been systematically carried out in Russia since the middle fifties. A unique complex of experimental installations was created. These include convection ampoules, loops, non-isothermal loops with forced circulation of coolant and reactor loops. Systematic research for lead has been carried out since the beginning of the nineties within the framework of developing BREST reactor. The high reserve of corrosion resistance of steel EP-823 was proven by tests of fuel-cladding compatibility. On the basis of the results of compatibility of fuel rod materials (cladding of EP-823 steel, lead contact heat-transfer layer, uranium mononitride fuel) tests were done at temperatures from 600 deg. C to 700 deg. C during 9400 hours
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Source
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria); 367 p; 2001; p. 288-290; IAEA-IWGFR advisory group meeting on design and performance of reactor and subcritical blanket systems with lead and lead-bismuth as coolant and/or target material; Moscow (Russian Federation); 23-27 Oct 2000
Record Type
Report
Literature Type
Conference
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ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, DEPOSITION, ELEMENTS, ENERGY SOURCES, ENERGY TRANSFER, EPITHERMAL REACTORS, FAST REACTORS, FUELS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, METALS, NUCLEAR FUELS, REACTOR MATERIALS, REACTORS, SOLID FUELS, STEELS, SURFACE COATING, TESTING, TRANSITION ELEMENT ALLOYS
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