Search Results - "KAZ'MIN, Yu. M"
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Computational Investigation of the Lifetime Characteristics of IGR Neutrons
Published in Atomic energy (New York, N.Y.) (01-01-2004)“…It is shown computationally that the IGR neutron lifetime depends on the neutron creation location in the core and that the absorbing material of the control…”
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Monitoring of the movement of a melt of fissioning material in the experimental channel of a pulsed graphite reactor igr using small neutron detectors
Published in Atomic energy (New York, N.Y.) (01-03-2002)“…It is shown that fuel elements consisting of a fissioning material can be simulated from the standpoint of the influence on the characteristics of the neutron…”
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Investigation of the neutron field in the central channel of a pulse graphite reactor when the neutron absorber moves
Published in Atomic energy (New York, N.Y.) (01-12-1998)“…(ProQuest: Abstract omitted; see image)[PUBLICATION ABSTRACT]…”
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Study of the three-dimensional neutron field in the core of the IGR (pulsed graphite reactor)
Published in Atomic energy (New York, N.Y.) (01-06-1997)“…(ProQuest: Abstract omitted; see image)[PUBLICATION ABSTRACT]…”
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5
“Bleaching” of uranium-graphite fuel for pulse graphite reactors
Published in Atomic energy (New York, N.Y.) (01-11-1998)“…(ProQuest: Abstract omitted; see image)[PUBLICATION ABSTRACT]…”
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PRIZMA.D computational investigation of physical processes in the IGR reactor
Published in Atomic energy (New York, N.Y.) (01-02-2000)“…It is shown for one experiment that the physical processes occurring in the-core of a pulsed uranium-graphite reactor IGR can be investigated by a…”
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A computational-experimental investigation of the temperature field of IGR masonry
Published in Atomic energy (New York, N.Y.) (01-04-2000)“…The experimental measurements of the temperature in IGR reactor masonry are analyzed, and it is shown that because of the radiation heating of the…”
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Testing HTGR spherical fuel elements under reactor impulse loads
Published in Soviet Atomic Energy (01-09-1991)Get full text
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Testing of compton-emission type detectors of neutrons and of triaxial fission chambers in a pulsed reactor
Published in Soviet Atomic Energy (01-07-1988)Get full text
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Improvement of welding materials and technology for welding chlorinators made of nickel
Published in Chemical and petroleum engineering (01-04-1973)Get full text
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Measurement of the temperature of structural materials heated by radiation from a pulsed uranium-graphite reactor
Published in Atomic energy (New York, N.Y.) (2001)“…The temperature of radiation heating by radiation from a pulsed uranium graphite reactor of small samples of tungsten, tantalum, molybdenum, chromium, copper,…”
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PRIZMA.D computational investigation of physical processes in the IGR reactor
Published in Atomic energy (New York, N.Y.) (2000)Get full text
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14
Computational investigation of the lifetime characteristics of IGR neutrons
Published in Atomic energy (New York, N.Y.) (2004)Get full text
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Characteristics of the Thermal-Neutron Field in the Experimental Channel of a Pulsed Graphite Reactor
Published in Atomic energy (New York, N.Y.) (01-04-2001)“…The current of the sensitive sections of a five-section Compton emission neutron detector, which are placed at different levels in the vertical direction in…”
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Computational-Experimental Investigation of the Special Features of the Neutron Spectrum of an IGR Reactor
Published in Atomic energy (New York, N.Y.) (01-09-2000)“…The energy spectra of neutrons in the experimental channel of an IGR reactor were measured using neutron-activation detectors. Ten detectors for thermal and…”
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A computational-experimental investigation of the temperature field of IGR Masonry
Published in Atomic energy (New York, N.Y.) (2000)Get full text
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Computational-experimental investigation of the special features of the neutron spectrum of an IGR reactor
Published in Atomic energy (New York, N.Y.) (2000)Get full text
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Characteristics of the thermal-neutron field in the experimental channel of a pulsed graphite reactor
Published in Atomic energy (New York, N.Y.) (2001)Get full text
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Bleachingof uranium-graphite fuel for pulse graphite reactors
Published in Atomic energy (New York, N.Y.) (1998)Get full text
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