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Thermal-hydraulic design of the 200 MW NHR

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Abstract

The main problems regarding the AST-500 NHR thermal-hydraulics are considered. Basic thermal data of the reactor plant are given and peculiarities of coolant parameters at natural convection in the primary circuit are discussed. The in-reactor instrumentation system is briefly describes, as well as the results of natural-convective flow characteristics investigations using reactor test models. (author). 4 refs, 5 figs.
Authors:
Jincai, Li; Zuying, Gao; Baocheng, Xu; Junxiao, He [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; PA: AIX-28:076293; EDB-97:143901; SN: 97001880646
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; VORONEZH AST-500 REACTOR; HYDRAULICS; TEMPERATURE DEPENDENCE; COGENERATION; COOLANTS; DESIGN; DISTRICT HEATING; DUAL-PURPOSE POWER PLANTS; NATURAL CONVECTION; NUCLEAR POWER PLANTS; REACTOR INSTRUMENTATION
OSTI ID:
548257
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: XA9745321076293
Availability:
INIS; OSTI as DE98605851
Submitting Site:
INIS
Size:
pp. 83-89
Announcement Date:
Dec 11, 1997

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Citation Formats

Jincai, Li, Zuying, Gao, Baocheng, Xu, and Junxiao, He. Thermal-hydraulic design of the 200 MW NHR. IAEA: N. p., 1997. Web.
Jincai, Li, Zuying, Gao, Baocheng, Xu, & Junxiao, He. Thermal-hydraulic design of the 200 MW NHR. IAEA.
Jincai, Li, Zuying, Gao, Baocheng, Xu, and Junxiao, He. 1997. "Thermal-hydraulic design of the 200 MW NHR." IAEA.
@misc{etde_548257,
title = {Thermal-hydraulic design of the 200 MW NHR}
 author = {Jincai, Li, Zuying, Gao, Baocheng, Xu, and Junxiao, He}
 abstractNote = {The main problems regarding the AST-500 NHR thermal-hydraulics are considered. Basic thermal data of the reactor plant are given and peculiarities of coolant parameters at natural convection in the primary circuit are discussed. The in-reactor instrumentation system is briefly describes, as well as the results of natural-convective flow characteristics investigations using reactor test models. (author). 4 refs, 5 figs.}
 place = {IAEA}
 year = {1997}
 month = {Sep}
 }