An Advanced Boiling Water Reactor Monitoring System Using Modular Accident Analysis Program and Computer Graphical User Interface

2008 ◽  
Vol 163 (3) ◽  
pp. 435-443 ◽  
Author(s):  
Yuan-Hsiang Chang ◽  
Mu-Ping Xu ◽  
Jyh-Tong Teng ◽  
Te-Chuan Wang ◽  
Ray-Feng Chiang ◽  
...  
Keyword(s):  
User Interface ◽  
Monitoring System ◽  
Graphical User Interface ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Accident Analysis ◽  
Analysis Program ◽  
Water Reactor

Use of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension

1991 ◽  
Vol 113 (3) ◽  
pp. 349-357 ◽  
Author(s):  
G. L. Stevens ◽  
S. Ranganath
Keyword(s):  
Monitoring System ◽  
Boiling Water ◽  
Life Extension ◽  
Boiling Water Reactor ◽  
Temperature Record ◽  
Water Reactor ◽  
Plant Life ◽  
Mainframe Computer ◽  
Fatigue Monitoring ◽  
On Line

The application of an on-line fatigue monitoring system for tracking fatigue usage in operating power plants is described. The system, like several others which have been developed, uses the influence function approach, operates on a microcomputer, and determines component stresses using temperature, pressure, and flow rate data that are typically available from plant computers. Using plant-unique influence functions developed specifically for each component location, the system calculates stresses as a function of time and computes the fatigue usage. Stress values are calculated at time intervals defined by the user and the fatigue values are saved on files for use at a later time. The application of the GE Fatigue Monitoring System (GEFMS) to calculate fatigue usage in the feedwater nozzle of a GE Boiling Water Reactor is described in this paper. Stress predictions using GEFMS for a sample temperature transient show excellent agreement with results from finite element thermal and stress analysis performed on a mainframe computer. Fatigue usage calculations for a simulated 24-hr temperature record confirm that the system provides accurate results at a cost that is significantly lower than similar analysis done on mainframe computer systems. The system, which has been installed in a boiling water reactor plant, provides the technical basis to evaluate actual reactor conditions and justify plant life extension.

Severe Accident Analysis Using MAAP With Detailed Nodalization in Advanced Boiling Water Reactor

2017 ◽  
Author(s):  
Hiromasa Chitose ◽  
Naoya Kamei ◽  
Ryusuke Kimura
Keyword(s):  
Boiling Water ◽  
Severe Accident ◽  
Boiling Water Reactor ◽  
Accident Analysis ◽  
Water Reactor ◽  
Structural Temperature ◽  
The Impact

In this study, severe accident analyses were conducted for the Advanced Boiling Water Reactor (ABWR) using a detailed nodalization and the impact of MAAP nodalization on the severe accident analysis was investigated. The results of the analysis obtained using a detailed nodalization shows that the PCV temperature is more challenging in comparison to the results of the original nodalization. However, it was found that the structural temperature of the PCV head flange can be maintained below the ultimate temperature of the head gasket when passive mitigation systems are successful, even if no reactor well injection is conducted.

Fatigue Monitoring of BWR Feedwater Nozzles

2013 ◽  
Author(s):  
Keith Evon ◽  
Tim Gilman ◽  
Matthew Walter
Keyword(s):  
Monitoring System ◽  
Green's Function ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor ◽  
Design Basis ◽  
Fatigue Monitoring ◽  
Cycle Count ◽  
Single Stress ◽  
Stress Term

Implementing a stress based fatigue monitoring system, including all six stress terms per NB-3200 methodology, can help to reduce conservatism associated with design basis fatigue calculations. The boiling water reactor (BWR) feedwater nozzle is a perfect example of a location that has been analyzed in detail, but can still have many conservative assumptions in the design basis fatigue calculations or when using a single stress term Green’s function. The BWR feedwater nozzle is also typically subjected to operational changes such as transient ramp time and cycle count changes. Some important differences between the simplified single stress term methodology and the advanced six stress term methodology will be briefly outlined. Furthermore, a stress based fatigue monitoring system can automatically take into account operational changes that might affect fatigue calculations. This paper will explore the implementation and benefits for using a stress based fatigue monitoring system to monitor locations associated with a BWR feedwater nozzle.

Operational Margin Monitoring System for Boiling Water Reactor Power Plants

1992 ◽  
Vol 100 (1) ◽  
pp. 13-24 ◽  
Author(s):  
Shigeki Fukutomi ◽  
Yukio Takigawa ◽  
Hideaki Namba
Keyword(s):  
Monitoring System ◽  
Power Plants ◽  
Reactor Power ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor

Development of an on-line reactor stability monitoring system in a boiling water reactor

1988 ◽  
Vol 21 ◽  
pp. 745-752 ◽  
Author(s):  
Shigeru Kanemoto ◽  
Mitsuhiro Enomoto ◽  
Yasumasa Ando ◽  
Hideaki Namba ◽  
Shigeo Ebata ◽  
...  
Keyword(s):  
Monitoring System ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor ◽  
Stability Monitoring ◽  
Reactor Stability ◽  
On Line
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