A thermal-fluid assessment of a cooled-vessel concept for a VHTR-Reference-Cited by-同舟云学术

A thermal-fluid assessment of a cooled-vessel concept for a VHTR

Published:2008-12 Issue:12 Volume:238 Page:3360-3369
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kim Min-Hwan,Lim Hong-Sik,Lee Won-Jae

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

Reference11 articles.

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3. ASME, 2001. Use of SA-533 grade B, class 1 plate and SA-508 class 3 forgings and their weldments for limited elevated temperature service, Section III, Division 1, Case N-499-2.

4. A study of a nuclear hydrogen production demonstration plant;Chang;Nucl. Eng. Technol.,2007

5. Reactor pressure vessel temperature analysis of candidate very high temperature reactor designs;Gougar,2006

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