Analysis of a Turbine Trip Transient with the Chinshan Plant Analyzer-Reference-Cited by-同舟云学术

Analysis of a Turbine Trip Transient with the Chinshan Plant Analyzer

Published:1993-07 Issue:1 Volume:103 Page:131-137
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Wang Shih-Jen¹,Chien Chun-Sheng¹,Jang Jung-Yuh²

Affiliation:

1. Institute of Nuclear Energy Research, P.O. Box 3-3 Lungtan, Taoyuan, Taiwan 32500

2. Taiwan Power Company 242 Roosevelt Road, Section 3, Taipei, Taiwan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT93-A34836

Reference8 articles.

1. Development of the Chinshan Plant Analyzer and Its Assessment with Plant Data

2. W. WULFF, H.S. CHENG, S. V. LEKACH, and A. N. MALLEN, “The BWR Plant Analyzer,” NUREG/CR-3943, BNL-NUREG-51812, Brookhaven National Laboratory (July 1984).

3. “ADSIM Reference Manual,” Applied Dynamics International, Inc. (Aug. 1988).

4. S.J. WANG, C.S. CHIEN, and S.C. LEE, “Self-Initialization Procedure of Chinshan Plant Analyzer,” INER-1120, Institute of Nuclear Energy Research, Taiwan (July 1991).

5. T. H. CHEN, “Chinshan Nuclear Power Station Unit 1 Startup Test Procedure STP-27 Turbine Trip and Load Rejection,” STP-27, Taiwan Power Company (1978).

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Use of the Chinshan Plant Analyzer for Analysis of a Main-Steam-Isolation-Valve-Closure Anticipated Transient Without Scram;Nuclear Technology;1996-03

2. Development of the Kuosheng Plant Analyzer and Its Assessment with Plant Data;Nuclear Technology;1994-04