A study of the sensitivity of loca heat transfer analysis for a water-cooled reactor system-Reference-Cited by-同舟云学术

A study of the sensitivity of loca heat transfer analysis for a water-cooled reactor system

Published:1978-05 Issue:1 Volume:47 Page:87-99
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Green W.J.,Lawther K.R.

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

Reference13 articles.

1. THETA1-B, A Computer Code for Nuclear Reactor Core Thermal Analysis;Hocevar;Idaho Nuclear Corporation, IN-1445,1972

2. OECD-NEA-CSNI Specialists' Meeting on the Behaviour of Water Reactor Fuel Elements under Accident Conditions;Green,1976

3. A Sensitivity Study of the Heat Transfer Processes involved in a Hot-Leg Rupture in a Pressurised Water-Cooled System;Green;AAEC Report E416,1977

4. RELAP 3 — A Computer Program for Reactor Blowdown Analysis;Rettig;IN-1321, Reactor Technology, TID-4500,1970

5. Third Water Reactor Safety Research Information Meeting;Zane,1975

Cited by 5 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Experimental and numerical studies on the temperature in a pendant water droplet heated in the hot air;International Journal of Thermal Sciences;2021-05

2. Cooling of the hot steel balls by salt –water solutions and water-based suspensions: Subcooled pool boiling experiments;International Journal of Thermal Sciences;2020-02

3. Leidenfrost phenomenon during quenching in aqueous solutions: effect of evaporation-induced concentration gradients;Soft Matter;2020

4. On the formation of vapor film during quenching in de-ionized water and elimination of film boiling during quenching in natural sea water;International Journal of Heat and Mass Transfer;2015-07

5. An investigation of transient heat transfer in the region of flow boiling dryout with freon-12 in a heated tube;Nuclear Engineering and Design;1979-12