Investigation of Processes in Lead Coolant with Loss-of-Integrity of a Heat-Exchange Tube in a Brest-OD-300 Steam Generator-Reference-Cited by-同舟云学术

Investigation of Processes in Lead Coolant with Loss-of-Integrity of a Heat-Exchange Tube in a Brest-OD-300 Steam Generator

Published:2015-12-18 Issue:3 Volume:119 Page:200-206
ISSN:1063-4258
Container-title:Atomic Energy
language:en
Short-container-title:At Energy

Author:

Abramov A. V.,Kovalev E. O.,Kolesnikov P. A.,Mukhametov R. R.,Naumenko M. Yu.,Nikitin O. A.,Petrov D. V.,Stolbikov M. Yu.,Yudov A. G.,Afremov D. A.,Lemekhov V. V.,Tutukin A. V.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering

Link

http://link.springer.com/content/pdf/10.1007/s10512-015-0041-3.pdf

Reference4 articles.

1. A. I. Filin, V. N. Leonov, M. A. Petrushin, et al., “Systems for localizing and protecting the BREST-OD-300 reactor from exceeding the admissible pressure in the gas volume,” Vopr. At. Nauki Tekhn. Ser. Yad. Tekhnol. Energ. Budush., No. 4, 106–112 (2004).

2. A. V. Beznosov and T. A. Bokova, Equipment of Power Loops with Heavy Liquid-Metal Coolants in Nuclear Power, N. Novgorod Gos. Tekhn. Univ., Nizhnii Novgorod (2012).

3. A. V. Beznosov, Yu. G. Dragunov, and V. I. Rachkov, Heavy Liquid-Metal Coolants in Nuclear Power, IzdAT, Moscow (2007).

4. V. N. Kozlovskii, Information in Pulsed Radiography, RFYaTs–VNIITF, Snezhinsk (2006).

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