Modeling of Hydrodynamic Processes at a Large Leak of Water into Sodium in the Fast Reactor Coolant Circuit-Reference-Cited by-同舟云学术

Modeling of Hydrodynamic Processes at a Large Leak of Water into Sodium in the Fast Reactor Coolant Circuit

Published:2016-10 Issue:5 Volume:48 Page:1162-1173
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Perevoznikov Sergey,Shvetsov Yuriy,Kamayev Aleksey,Pakhomov Ilia,Borisov Viacheslav,Pazin Gennadiy,Mirzeabasov Oleg,Korzun Olga

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference6 articles.

1. Fast Reactor Fuel Failures and Steam Generation Leaks: Transient and Accident Analysis Approaches;Buksha,1996

2. Bezopasnost' Parogeneratorov Natriy-voda (Sodium–water Steam Generators Safety);Poplavskiy,1990

3. SWAAM Code development, Verification, and Application to Steam Generator Design;Shin,1990

4. Rabota parogeneratora s natriem i vodoy i vtorogo kontura pri malykh techakh vody v natriy (Operation of Sodium–water Steam Generator and the Secondary Circuit in Case of Small Water Leaks into Sodium);Kozlov,1974

5. Bezopasnost' AES s reaktorami na bystrykh neytronakh (Safety of NPPS with Fast Reactors);Kuznetsov,2012

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