Published December 2012 | Version v1
Journal article

Qualification of the Taiwan Power Company's pressurized water reactor physics methods using CASMO-4/SIMULATE-3

  • 1. Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China)

Description

Highlights: ► Studsvik's core management system (CMS) was applied to Taiwan Power Company's pressurized water reactor. ► Advanced calculation model of shutdown cooling, B-10 depletion and integrated pin exposure were introduced. ► Core characteristic parameters such as boron letdown, low power physics test (LPPT) predictions, and reaction rate were validated to measurement data. ► The uncertainty of each item was quantified. - Abstract: This paper presents the validation of Studsvik core management system (CMS) for application to the Maanshan units 1 and 2 reactor core physics analysis (Huang and Yang, 1994). The methodology was validated by demonstrating the ability to obtain accurate and reliable results for various conditions and applications. Core characteristic parameters such as boron letdown, low power physics test (LPPT) predictions, and reaction rate were validated. Analytical results have been compared to measured data and reliability factors of the method have been quantified.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2012.07.020

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2012.07.020;
PII
S0029-5493(12)00421-9;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
253
Journal Page Range
p. 71-76
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.