Experimental Devices for Testing in the BOR-60 Reactor
https://doi.org/10.1134/S2304487X19050092
Abstract
At present, a wide range of tests of materials used in nuclear power engineering is carried out in the BOR-60 reactor. The study of changes in the properties of materials requires the determination of temperature irradiation conditions with high accuracy. The materials that have been tested in the BOR-60 reactor from the start up to the present are summarized in this work. Each of the research areas requires an individual approach and the creation of a unique experimental device. Experimental devices differ in various criteria that affect the efficiency of the research. The geometrical parameters of the cells of the reactor and the characteristics of the pressure collector require external similarity of the devices used, and the internal design varies considerably depending on the type of research conducted. Various classifications of experimental devices of the BOR-60 reactor differing in the method of obtaining information, in the f irradiation temperature, and in the design and testing environment are presented. In addition, a methodical experiment conducted in the instrumented cell of the BOR-60 reactor is described. For each type of irradiation devices, the design features and test applications are discussed. An autonomous loop channel that allows testing in environments different from the reactor coolant is described separately.
About the Authors
I. Yu. Zhemkov
Research Institute of Atomic Reactors
Russian Federation
Russian Federation
433507
Dimitrovgrad
N. S. Poglyad
Research Institute of Atomic Reactors; Dimitrovgrad Engineering and Technological Institute, National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)
Russian Federation
Russian Federation
433507
433511
Dimitrovgrad
V. Yu. Anisimov
Research Institute of Atomic Reactors; Dimitrovgrad Engineering and Technological Institute, National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)
Russian Federation
Russian Federation
433507
433511
Dimitrovgrad
A. V. Boev
Research Institute of Atomic Reactors; Dimitrovgrad Engineering and Technological Institute, National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)
Russian Federation
Russian Federation
433507
433511
Dimitrovgrad
References
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Review
For citations:
Zhemkov I.Yu., Poglyad N.S., Anisimov V.Yu., Boev A.V. Experimental Devices for Testing in the BOR-60 Reactor. Vestnik natsional'nogo issledovatel'skogo yadernogo universiteta "MIFI". 2019;8(5):402-409. (In Russ.) https://doi.org/10.1134/S2304487X19050092
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