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Avaev, V. N., Vasil'ev, G. A., Veselkin, A. P., Egorov, Yu. A., Orlov, Yu. V., Pankrat'ev, Yu. V. (1964) Attenuation of pile neutron flux in polyethylene. Soviet Atomic Energy, 15. 671-674 doi:10.1007/bf01119152

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Reference TypeJournal (article/letter/editorial)
TitleAttenuation of pile neutron flux in polyethylene
JournalSoviet Atomic Energy
AuthorsAvaev, V. N.Author
Vasil'ev, G. A.Author
Veselkin, A. P.Author
Egorov, Yu. A.Author
Orlov, Yu. V.Author
Pankrat'ev, Yu. V.Author
Year1964 (May)Volume15
PublisherSpringer Science and Business Media LLC
DOIdoi:10.1007/bf01119152Search in ResearchGate
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Mindat Ref. ID10261508Long-form Identifiermindat:1:5:10261508:3
GUID0
Full ReferenceAvaev, V. N., Vasil'ev, G. A., Veselkin, A. P., Egorov, Yu. A., Orlov, Yu. V., Pankrat'ev, Yu. V. (1964) Attenuation of pile neutron flux in polyethylene. Soviet Atomic Energy, 15. 671-674 doi:10.1007/bf01119152
Plain TextAvaev, V. N., Vasil'ev, G. A., Veselkin, A. P., Egorov, Yu. A., Orlov, Yu. V., Pankrat'ev, Yu. V. (1964) Attenuation of pile neutron flux in polyethylene. Soviet Atomic Energy, 15. 671-674 doi:10.1007/bf01119152
In(1963) Soviet Atomic Energy Vol. 15. Springer Science and Business Media LLC

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Avaev, V. N., Vasil'ev, G. A., Veselkin, A. P., Egorov, Yu. A., Orlov, Yu. V., Pankrat'ev, Yu. V. (1964) Spectra of fast pile neutrons in passage through polyethylene. Soviet Atomic Energy, 15. 675-677 doi:10.1007/bf01119153
Vasil'ev, G. A., Veselkin, A. P., Egorov, Yu. A., Moiseev, G. G., Pankrat'ev, Yu. V. (1965) Attenuation of pile radiations in serpentinite sand. Soviet Atomic Energy, 19. 1283-1289 doi:10.1007/bf01163834
Vasil'ev, G. A., Veselkin, A. P., Egorov, Yu. A., Kucheryaev, V. A., Pankrat'ev, Yu. V. (1965) The attenuation of reactor radiation by means of serpentine concrete. Soviet Atomic Energy, 18. 151-157 doi:10.1007/bf01115807
Veselkin, A. P., Egorov, Yu. A., Orlov, Yu. V., Pankrat'ev, Yu. V. (1969) Energy distribution of fast neutrons outside reactor shielding. Soviet Atomic Energy, 26. 606-612 doi:10.1007/bf01218774
Veselkin, A. P., Egorov, Yu. A., Orlov, Yu. V., Pankrat'ev, Yu. V. (1964) Spectra of fast reactor neutrons after passing through graphite, lead, and iron. Soviet Atomic Energy, 16. 34-40 doi:10.1007/bf01131719
Veselkin, A. P., Voskresenskii, E. V., Egorov, Yu. A., Pankrat'ev, Yu. V., Piskunov, V. I. (1971) Neutron spectra from 0.05 to 10 MeV in certain shielding materials. Soviet Atomic Energy, 30. 472 doi:10.1007/bf01182186
Veselkin, A. P., Egorov, Yu. A., Netecha, M. E., Pankrat'ev, Yu. V., Piskunov, V. I. (1969) Buildup of moderated neutrons in reactor shielding. Soviet Atomic Energy, 26. 298-306 doi:10.1007/bf01162424
Avaev, V. N., Egorov, Yu. A., Moiseev, G. G. (1964) Attenuation of neutrons with an energy of more than 1.5 Mev in iron. Soviet Atomic Energy, 16. 431 doi:10.1007/bf01116067
Veselkin, A. P., Glushchenko, A. I., Egorov, Yu. A., Orlov, Yu. V. (1969) Angular distribution of flux and intensity of ?-radiation scattered by a shield. Soviet Atomic Energy, 27. 1102-1103 doi:10.1007/bf01129287
Egorov, Yu. A., Zharkov, V. P., Orlov, Yu. V. (1970) Back scattering of neutrons from aluminum, titanium, graphite, and polyethylene. Soviet Atomic Energy, 28. 216-218 doi:10.1007/bf01162637
Veselkin, A. P., Nikitin, A. V., Orlov, Yu. V. (1966) Water reactor hot loop studies. Soviet Atomic Energy, 21. 1218-1220 doi:10.1007/bf01164244
 
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