Advertisement

TRAC Analysis of the Crystal River Unit-3 Plant Transient of February 26, 1980

  • P. Coddington
  • G. J. E. WillcuttJr.

Abstract

This paper describes the application of the TRAC-PD2 and TRAC-PF1 codes to analyze the Crystal River transient. The PD2 and PF1 analyses used the three-dimensional and one-dimensional vessel models, respectively. Both calculations predicted the plant depressurization caused by the open PORV and the subsequent repressurization caused by closing the PORV and continuing high-pressure injection flow. Also, natural circulation was calculated in loop B following reestablishment of feedwater to the loop-B steam generator. After system repressurization, the codes calculated that pressure was relieved through the safety valves, and an intermittent flow occurred in loop A because of high-pressure-injection-driven density variations.

Keywords

Plant Data Natural Circulation Intermittent Flow Integrate Control System Alamos National Laboratory Report 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. 1.
    “Transient Assessment Report—Reactor Trip at Crystal River-3 Nuclear Station on February 26, 1980 (Preliminary),” Babcock & Wilcox report 07-08-02, Rev. 02 (March 9, 1980).Google Scholar
  2. 2.
    “Analysis and Evaluation of Crystal River—Unit 3 Incident,” Nuclear Safety Analysis Center report NSAC-3 (March 1980).Google Scholar
  3. 3.
    W. Brown, G. Caldwell, B. Chexal, and W. Layman, “Thermohydraulic Analysis of Crystal River Unit-3 Incident,” Nuclear Safety Analysis Center report NSAC-15 (June 1981).Google Scholar
  4. 4.
    “TRAC-PD2 An Advanced Best-Estimate Computer Program for Pressurized Water Reactor Loss-of-Coolant Accident Analysis,” Los Alamos National Laboratory report LA-8709-MS, NUREG/CR-2054 (April 1981).Google Scholar
  5. 5.
    “TRAC-PF1 An Advanced Best-Estimate Computer Program for Pressurized Water Reactor Analysis,” Los Alamos National Laboratory report to be published.Google Scholar
  6. 6.
    G. J. E. Willcutt, Jr. “TRAC-PD2 Calculations of the Crystal-River-3 Transient of February 26, 1980 Using Revised Assumptions”, Los Alamos National Laboratory report LA-UR-83-1078 (April 1983).Google Scholar
  7. 7.
    P. Coddington, “TRAC-PF1 One-Dimensional Analysis of the Crystal River Unit 3 Plant Transient of February 26, 1980”, Los Alamos National Laboratory report to be published.Google Scholar

Copyright information

© Springer Science+Business Media New York 1984

Authors and Affiliations

  • P. Coddington
    • 1
  • G. J. E. WillcuttJr.
    • 2
  1. 1.Group Q-9Los Alamos National LaboratoryLos AlamosUSA
  2. 2.Group Q-7Los Alamos National LaboratoryLos AlamosUSA

Personalised recommendations