Yanagisawa, T.; Akagane, K.; Yamamoto, K.; Kawashima, K.
Specialists' meeting on fission and corrosion product behaviour in primary circuits of LMFBR's, Dimitrovgrad, USSR, September 8-11, 1975. Summary report1976
Specialists' meeting on fission and corrosion product behaviour in primary circuits of LMFBR's, Dimitrovgrad, USSR, September 8-11, 1975. Summary report1976
AbstractAbstract
[en] General influence of fission and corrosion products in primary system on MONJU plant design is reviewed. Various research and development works are now in progress to decrease the generation rate, to remove the products more effectively and to develop the methods of evaluation the behaviour of radioactive products. The inventory and distribution of fission and corrosion products in the primary circuit of MONJU are given. The radiation levels on the primary components are estimated to be several roentgens per hour. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria). International Working Group on Fast Reactors; p. 108-117; Feb 1976; p. 108-117; Specialists' meeting on fission and corrosion product behaviour in primary circuits of LMFBR's; Dimitrovgrad, USSR; 8 - 11 Sep 1975
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Report
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Conference
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BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BETA-PLUS DECAY RADIOISOTOPES, BREEDER REACTORS, CHROMIUM ISOTOPES, COBALT ISOTOPES, DAYS LIVING RADIOISOTOPES, ELECTRON CAPTURE RADIOISOTOPES, EPITHERMAL REACTORS, EVEN-ODD NUCLEI, FAST REACTORS, FBR TYPE REACTORS, HOURS LIVING RADIOISOTOPES, HYDROGEN ISOTOPES, INTERMEDIATE MASS NUCLEI, IRON ISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIGHT NUCLEI, LIQUID METAL COOLED REACTORS, MANGANESE ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, POWER REACTORS, RADIOACTIVE MATERIALS, RADIOISOTOPES, REACTORS, SODIUM COOLED REACTORS, YEARS LIVING RADIOISOTOPES
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INIS VolumeINIS Volume
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Terasaka, H.; Okada, H.; Akagane, K.; Makita, A.
ICONE-4: Proceedings. Volume 1 -- Part B: Basic technological advances1996
ICONE-4: Proceedings. Volume 1 -- Part B: Basic technological advances1996
AbstractAbstract
[en] An international project, the PHEBUS Fission Project Program (von der Hardt et al., 1994), is being carried out at Cadarache, France. Six integral in-pile tests, FPT0--FPT5, have been planned in the project to evaluate the behavior of fission products (FPs) released from a light water reactor during a severe accident. This paper describes numerical analysis of the PHEBUS FP steady-state benchmark problems and the first in-pile transient test, FPT0. A two-dimensional code has been newly developed to predict thermal hydraulics in the containment vessel, including air, steam and hydrogen transport and steam condensation. A degradation factor correlation, which plays an important role in the predictions for the condensation heat transfer in the presence of noncondensable gases, has been developed and incorporated into the code. The calculation results show that the code can accurately and rapidly predict complicated phenomena in the PHEBUS containment vessel
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Rao, A.S. (ed.) (General Electric Nuclear Energy, San Jose, CA (United States)); Duffey, R.B. (ed.) (Brookhaven National Lab., Upton, NY (United States)); Elias, D. (ed.) (Commonwealth Edison, Downers Grove, IL (United States)); 564 p; ISBN 0-7918-1226-X; ; 1996; p. 557-565; American Society of Mechanical Engineers; New York, NY (United States); ICONE 4: ASME/JSME international conference on nuclear engineering; New Orleans, LA (United States); 10-13 Mar 1996; American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, NY 10017 (United States) $250.00 for the 5-volume set
Record Type
Book
Literature Type
Conference; Numerical Data
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Akagane, K.; Kiso, Y.; Fukahori, T.; Yoshino, M.
ICONE-3: Proceedings of the 3rd JSME/ASME joint international conference on nuclear engineering. Volume 31995
ICONE-3: Proceedings of the 3rd JSME/ASME joint international conference on nuclear engineering. Volume 31995
AbstractAbstract
[en] In order to evaluate the behavior of fission products released from a core at a nuclear power light water reactor during a severe accident, the Phebus FP program is under way at CADARACHE (FRANCE) as an international project. In this program, the fission products released from the core are injected via a steam current into a containment vessel which is 1/5000 in volume of the actual plant. The Phebus FP program is unique in that it is the first in the world to study the transport of real fission products from their release in the fuel to their behavior in the circuit and containment. In NUPEC, MELCOR has been applied for thermal-hydraulic pre-test analysis of the first test of the Phebus FP program (test FPT-0) to study the applicability of the code for analysis of fuel bundle degradation phenomena and to confirm that the targeted constant test conditions can be attained in the circuit and containment. This paper presents the Phebus FPT-0 pre-test analysis by MELCOR version 1.8.2. (J.P.N.)
Primary Subject
Source
Japan Society of Mechanical Engineers, Tokyo (Japan); 534 p; 1995; p. 1167-1173; ICONE-3: 3. JSME/ASME joint international conference on nuclear engineering; Kyoto (Japan); 23-27 Apr 1995; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, Japan; 5 refs., 15 figs., 1 tab.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
ACCIDENTS, COLLOIDS, COMPUTER CODES, DISPERSIONS, ENRICHED URANIUM REACTORS, FLUID MECHANICS, FUEL ASSEMBLIES, HYDRAULICS, ISOTOPES, MATERIALS, MATHEMATICS, MECHANICS, NUCLEAR FACILITIES, POOL TYPE REACTORS, POWER PLANTS, RADIOACTIVE MATERIALS, REACTOR ACCIDENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOLS, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Sagawa, N.; Fukushima, Y.; Yokota, N.; Akagane, K.; Mochizuki, K.
Specialists' meeting on sodium fires and prevention. Summary report1979
Specialists' meeting on sodium fires and prevention. Summary report1979
AbstractAbstract
[en] Iodine release associated with sodium pool combustion was determined by heating 20 gr sodium containing sodium iodide, which was labelled with 131I and dissolved in the sodium in concentration of 1∼1,000 ppm, to burn on a nickel crucible in conditioned atmosphere in a closed vessel of 0.4 m3. Oxygen concentration was changed in 5∼21% and humidity in 0∼89% by mixing nitrogen gas and air. Combustion products were trapped by a Maypack filter composed of particle filters, copper screens and activated charcoal beds and by a glass beads pack cooled by liquid argon. Iodine collected on these filter elements was determined by radio-gas chromatography. When the sodium sample burned in the atmosphere of air at room temperature, the release fractions observed were 6∼33% for sodium and 1∼20% for iodine added in the sodium. The release iodine was present in aerosol at a ratio of 98%, and the remainder in the gas form. The release fraction of iodine trended to decrease as oxygen concentration and humidity in the atmosphere increased. No organic iodide was detected in the combustion products. (author)
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Secondary Subject
Source
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria); 259 p; Mar 1979; p. 199-208; IAEA-IWGFR specialists' meeting on sodium fires and prevention; Cadarache (France); 20-24 Nov 1987; 10 refs, 8 figs
Record Type
Report
Literature Type
Conference
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Country of publication
ADSORBENTS, ALKALI METALS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBON, CHEMICAL REACTIONS, CHROMATOGRAPHY, DAYS LIVING RADIOISOTOPES, ELEMENTS, FLUIDS, GASES, INTERMEDIATE MASS NUCLEI, IODINE ISOTOPES, ISOTOPE APPLICATIONS, ISOTOPES, METALS, MOISTURE, NONMETALS, NUCLEI, ODD-EVEN NUCLEI, OXIDATION, RADIOISOTOPES, SEPARATION PROCESSES, THERMOCHEMICAL PROCESSES
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Sagawa, N.; Sakaguchi, S.; Suzuoki, A.; Akagane, K.; Mochizuki, M.
Specialists' meeting on sodium fires and prevention. Summary report1979
Specialists' meeting on sodium fires and prevention. Summary report1979
AbstractAbstract
[en] Energy release associated with sodium spray combustion was determined and a computer code was developed to analyze combustion of sodium particles in the atmosphere depleted of oxygen. Liquid sodium heated at 300∼500 deg. C was injected as much as 400 gr into a closed vessel of 2 m3. Atmosphere in the vessel was controlled by mixing nitrogen gas with dry air and wet air 0∼21% in oxygen concentration and 0∼75 in humidity. Temperatures and pressure of the atmosphere were recorded to observe their rises and drops with time during and after sodium injection. Peak pressure rose with increases in oxygen concentration and temperature of injected sodium being more sensitive to the concentration than the temperature. The peak pressure did not reach a level which was obtained from theoretical energy release from sodium spray combustion because of incomplete combustion and heat transfer to the vessel wall. It was assumed in the computer code that heat and mass transfer was controlled respectively by heat conduction and mass diffusion inside a reaction zone and the transfer was governed by convection outside the reaction zone. Calculation results revealed that combustion rate per unit area on the sodium particle was in proportion to oxygen concentration in the ambient gas but in reverse to the particle sizes, and that decreasing rate of square of particle sizes was about 7x10-4 cm2/s, being smaller in one order of the value of fuel oils. Change in the pressure obtained from the calculation was on the whole in agreement with that observed in the experiment. (author)
Primary Subject
Secondary Subject
Source
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria); 259 p; Mar 1979; p. 95-111; IAEA-IWGFR specialists' meeting on sodium fires and prevention; Cadarache (France); 20-24 Nov 1987; 16 refs, 13 figs
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Report
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Conference
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