You need JavaScript to view this

Investigation of in service inspection for pressure vessel of the 200 MW nuclear heating reactor

Abstract

The Nuclear District Heating Reactor (NHR) is a new type of reactor. There are some differences in the arrangement of the primary circuit components and in safety features between NHR and PWR or other reactors. In this paper the safety features of the 200 MW NHR are described. The failure probability, the LBB property and the in-service inspection requirement for the 200 MW NHR pressure vessel are also discussed. (author). 16 refs, 6 figs, 4 tabs.
Authors:
Shuyan, He; Ming, Yin; Junjie, Liu; Huanjian, Chang; Ningning, Zhou [1] 
  1. Institute of Nuclear Energy and Technology, Tsingua Univ., Beijing (China)
Publication Date:
Sep 01, 1997
Product Type:
Conference
Report Number:
IAEA-TECDOC-965; CONF-9406436-
Reference Number:
SCA: 210900; 320603; PA: AIX-28:076300; EDB-97:143919; SN: 97001880653
Resource Relation:
Conference: Advisory group meeting on design approaches for heating reactors, Beijing (China), 6-10 Jun 1994; Other Information: PBD: Sep 1997; Related Information: Is Part Of Design approaches for heating reactors. Report of an advisory group meeting; PB: 278 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATION; DISTRICT HEATING; NUCLEAR POWER PLANTS; REACTOR SAFETY; PRESSURE VESSELS; IN-SERVICE INSPECTION; COGENERATION; DUAL-PURPOSE POWER PLANTS; FAILURES; POWER RANGE 100-1000 W; PROBABILITY
OSTI ID:
548264
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE98605851; TRN: XA9745328076300
Availability:
INIS; OSTI as DE98605851
Submitting Site:
INIS
Size:
pp. 183-203
Announcement Date:

Citation Formats

Shuyan, He, Ming, Yin, Junjie, Liu, Huanjian, Chang, and Ningning, Zhou. Investigation of in service inspection for pressure vessel of the 200 MW nuclear heating reactor. IAEA: N. p., 1997. Web.
Shuyan, He, Ming, Yin, Junjie, Liu, Huanjian, Chang, & Ningning, Zhou. Investigation of in service inspection for pressure vessel of the 200 MW nuclear heating reactor. IAEA.
Shuyan, He, Ming, Yin, Junjie, Liu, Huanjian, Chang, and Ningning, Zhou. 1997. "Investigation of in service inspection for pressure vessel of the 200 MW nuclear heating reactor." IAEA.
@misc{etde_548264,
title = {Investigation of in service inspection for pressure vessel of the 200 MW nuclear heating reactor}
author = {Shuyan, He, Ming, Yin, Junjie, Liu, Huanjian, Chang, and Ningning, Zhou}
abstractNote = {The Nuclear District Heating Reactor (NHR) is a new type of reactor. There are some differences in the arrangement of the primary circuit components and in safety features between NHR and PWR or other reactors. In this paper the safety features of the 200 MW NHR are described. The failure probability, the LBB property and the in-service inspection requirement for the 200 MW NHR pressure vessel are also discussed. (author). 16 refs, 6 figs, 4 tabs.}
place = {IAEA}
year = {1997}
month = {Sep}
}