Autor:	V. A. Pakhnits, A. N. Shcherbina, Ya. Z. Kandiev, V. A. Pavshuk, Zh. R. Zhotabaev, A. P. Vasil'ev, Yu. G. Nikiporets, V. M. Malinkin, N. V. Gorin, Yu. M. Kaz'min
Rok vydání:	2002
Předmět:	Materials science Field (physics) Nuclear engineering Radiochemistry Radiation heating Nuclear reactor law.invention Nuclear Energy and Engineering law Neutron detection Neutron Research reactor Graphite Physics::Chemical Physics Communication channel
Zdroj:	Atomic Energy. 92:239-245
ISSN:	1063-4258
Popis:	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 field in the experimental channel of a pulsed graphite reactor by models fabricated from paraffin mixed with boric acid. It is suggested that a method be developed for monitoring the movement of the melt in the experimental channel of a pulsed graphite reactor on the basis of signals from small neutron detectors. It is suggested that the model components be melted in a pulsed graphite reactor by radiation heating by neutrons. In the future the method should be refined in experiments with actual assemblies.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::9dd9ba51678c8d24df3f75ad4c1c5c78 https://doi.org/10.1023/a:1016046030363 Zobrazit plný text záznamu Full text from SpringerLink