Steam generator tube rupture in lead-cooled fast reactors: Estimation of impact on neighboring tubes

Author:

Iskhakov A.S.,Melikhov V.I.,Melikhov O.I.,Yakush S.E.

Funder

RFBR

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference38 articles.

1. A.V. Abramov Experimental validation of BREST-OD-300 reactor safety under seal failure of heat-exchange tubes. Proceedings of the international scientific and technical conference, innovative projects and technologies of nuclear power (ISTC NIKIET-2014), Section 1 Innovative designs of various-purpose nuclear power facilities 2014 Moscow, Russia.

2. Overview of lead-cooled fast reactor activities;Alemberti;Progr. Nucl. Energy,2014

3. Explosion Hazards and Evaluation;Baker,1983

4. Bernardi, D. et al., 2010. LBE-water interaction in LIFUS 5 facility to study a SGTR event under ELSY reactor conditions. Proceedings of the 18th International Conference on Nuclear Engineering ICONE18. Xi'an, China.

5. Equipment of Power Circuits with Heavy Liquid-Metal Coolants in Nuclear Power Engineering;Beznosov,2012

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