Investigation of Processes in Lead Coolant with Loss-of-Integrity of a Heat-Exchange Tube in a Brest-OD-300 Steam Generator
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- 作者：A. V. Abramov ; E. O. Kovalev ; P. A. Kolesnikov ; R. R. Mukhametov…
- 刊名：Atomic Energy
- 出版年：2016
- 出版时间：January 2016
- 年：2016
- 卷：119
- 期：3
- 页码：200-206
- 全文大小：751 KB
- 参考文献：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). - 作者单位：A. V. Abramov (1)
E. O. Kovalev (1)
P. A. Kolesnikov (1)
R. R. Mukhametov (1)
M. Yu. Naumenko (1)
O. A. Nikitin (1)
D. V. Petrov (1)
M. Yu. Stolbikov (1)
A. G. Yudov (1)
D. A. Afremov (2)
V. V. Lemekhov (2)
A. V. Tutukin (2)
1. Russian Federal Nuclear Center – Zababakhin All-Russia Research Institute of Technical Physics (RFYaTs – VNIITF), Snezhinsk, Chelyabinsk Oblast, Russia
2. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia - 刊物类别：Engineering
- 刊物主题：Nuclear Engineering
Nuclear Physics, Heavy Ions and Hadrons
Nuclear Chemistry
Russian Library of Science - 出版者：Springer New York
- ISSN：1573-8205
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