Nuclear Design of the High-Temperature Engineering Test Reactor (HTTR)-Reference-Cited by-同舟云学术

Nuclear Design of the High-Temperature Engineering Test Reactor (HTTR)

Published:1996-02 Issue:2 Volume:122 Page:212-228
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Yamashita Kiyonobu¹,Shindo Ryuichi¹,Murata Isao¹,Maruyama So¹,Fujimoto Nozomu¹,Takeda Takeshi¹

Affiliation:

1. Japan Atomic Energy Research Institute, 311-13 Oarai-machi Higashiibaraki-gun, Ibaraki-ken, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE96-A24156

Reference18 articles.

1. “Present Status of HTGR Research and Development,” Japan Atomic Energy Research Institute (1989).

2. “Fort St. Vrain Nuclear Generation Station Final Safety Analysis Report,” Docket-50267, Public Service Company of Colorado (1970).

3. “Sicherheitsbericht für das Atom-Versuchskraftwerk Jülich,” Arbeitsgemeinschaft Versuchsreaktor AVR GmbH (1965).

4. “Sicherheitsbericht des THTR-prototype 300 MWe,” Association EURATOM/BBC and KFA (1968).

5. H. YASUDA et al. “Construction of VHTRC (Very High Temperature Reactor Critical Assembly),” JAERI-1305, Japan Atomic Energy Research Institute (1986) (in Japanese).

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