An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part I: SETs, and ITFs of PWRs, BWRs, VVERs-Reference-Cited by-同舟云学术

An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part I: SETs, and ITFs of PWRs, BWRs, VVERs

Published:2019-12 Issue: Volume:354 Page:110212
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Aksan N.

Funder

OECD/NEA

IAEA

PSI

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

Reference40 articles.

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3. Aksan N., Tolman E. L., Nelson R. A., 1983, Application of analytical capability to predict rapid cladding cooling and quench during the blowdown phase of a large break loss-of-coolant accident. In: Proceedings of Second International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-2), Vol. 2, Santa Barbara, California, USA, Jan.

4. User effects on the thermal hydraulic transient system code calculations;Aksan;Nucl. Eng. Des.,1993

5. User Effects on the Transient System Code Calculations;Aksan,1995

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