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Titre du document / Document title

Current status and technical description of Chinese 2 x 250 MWth HTR-PM demonstration plant

Auteur(s) / Author(s)

ZUOYI ZHANG (1) ; ZONGXIN WU (1) ; DAZHONG WANG (1) ; YUANHUI XU (1) ; YULIANG SUN (1) ; FU LI (1) ; YUJIE DONG (1) ;

Affiliation(s) du ou des auteurs / Author(s) Affiliation(s)

(1) Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, CHINE

Résumé / Abstract

After the nuclear accidents ofThree Mile Island and Chernobyl the world nuclear community made great efforts to increase research on nuclear reactors and to develop advanced nuclear power plants with much improved safety features. Following the successful construction and a most gratifying operation of the 10 MWth high-temperature gas-cooled test reactor (HTR-10), the Institute of Nuclear and New Energy Technology (INET) ofTsinghua University has developed and designed an HTR demonstration plant, called the HTR-PM (high-temperature-reactor pebble-bed module). The design, having jointly been carried out with industry partners from China and in collaboration of experts worldwide, closely follows the design principles of the HTR-10. Due to intensive engineering and R&D efforts since 2001, the basic design of the HTR-PM has been finished while all main technical features have been fixed. A Preliminary Safety Analysis Report (PSAR) has been compiled. The HTR-PM plant will consist of two nuclear steam supply system (NSSS), so called modules, each one comprising of a single zone 250 MWth pebble-bed modular reactor and a steam generator. The two NSSS modules feed one steam turbine and generate an electric power of 210 MW. A pilot fuel production line will be built to fabricate 300,000 pebble fuel elements per year. This line is closely based on the technology of the HTR-10 fuel production line. The main goals of the project are two-fold. Firstly, the economic competitiveness of commercial HTR-PM plants shall be demonstrated. Secondly, it shall be shown that HTR-PM plants do not need accident management procedures and will not require any need for offsite emergency measures. According to the current schedule of the project the completion date of the demonstration plant will be around 2013. The reactor site has been evaluated and approved; the procurement of long-lead components has already been started. After the successful operation of the demonstration plant, commercial HTR-PM plants are expected to be built at the same site. These plants will comprise many NSSS modules and, correspondingly, a larger turbine.

Revue / Journal Title

Nuclear engineering and design    ISSN  0029-5493   CODEN NEDEAU 

Source / Source

2009, vol. 239, no7, pp. 1212-1219 [8 page(s) (article)] (1/4 p.)

Langue / Language

Anglais

Editeur / Publisher

Elsevier, Amsterdam, PAYS-BAS  (1966) (Revue)

Mots-clés anglais / English Keywords

Steam turbine

;

Steam generator

;

Water vapor

;

Research and development

;

Pebble bed reactor

;

Nuclear energy

;

Gas cooled reactor

;

Safety

;

Nuclear power plant

;

Nuclear reactor

;

Research reactor

;

Accident

;

High temperature reactor

;

Mots-clés français / French Keywords

Turbine vapeur

;

Générateur vapeur

;

Vapeur eau

;

Recherche et développement

;

Réacteur lit boulet

;

Energie nucléaire

;

Réacteur refroidi gaz

;

Sécurité

;

Centrale nucléaire

;

Réacteur nucléaire

;

Réacteur recherche

;

Accident

;

Réacteur haute température

;

Mots-clés espagnols / Spanish Keywords

Turbina vapor

;

Generador vapor

;

Vapor agua

;

Investigación desarrollo

;

Reactor bolas combustibles

;

Energía nuclear

;

Reactor enfríado gas

;

Seguridad

;

Central nuclear

;

Reactor nuclear

;

Reactor investigación

;

Accidente

;

Reactor alta temperatura

;

Localisation / Location

INIST-CNRS, Cote INIST : 12262, 35400018852013.0060

Nº notice refdoc (ud4) : 21538737



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