Modeling of natural circulation for the inherent safety analysis of sodium cooled fast reactors-Reference-Cited by-同舟云学术

Modeling of natural circulation for the inherent safety analysis of sodium cooled fast reactors

Published:2016-12 Issue:4 Volume:2 Page:294-298
ISSN:2452-3038
Container-title:Nuclear Energy and Technology
language:en
Short-container-title:Nuclear Energy and Technology

Author:

Bochkarev A.S.,Alekseev P.N.,Korsun A.S.,Kharitonov V.S.

Publisher

Pensoft Publishers

Subject

General Medicine

Reference22 articles.

1. Proceedings of the Eighth International Scientific and Technical Conference “Safety, Efficiency and Economics of Nuclear Power Industry”;Alekseev,2012

2. General Provisions for Ensuring the Safety of Nuclear Power Plants. NP-001-15. Moscow. Energoatomizdat Publ., 2015, pp. 30 (in Russian).

3. Stochastic effects when determining the maximum RBMK channel power

4. A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents

5. Analysis of solutions for passively activated safety shutdown devices for SFR

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3. Two Dimensional Performance Analysis of Small HTR Residual Heat Removal System in DLOFC Condition;Journal of Physics: Conference Series;2019-04