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RHODIUM SELF-POWERED NEUTRON DETECTOR'S LIFETIME FOR KOREAN STANDARD NUCLEAR POWER PLANTS  

YOO CHOON SUNG (Korea Atomic Energy Research Institute)
KIM BYOUNG CHUL (Korea Atomic Energy Research Institute)
PARK JONG-HO (Chungnam National University)
FERO ARNOLD H. (Korea Atomic Energy Research Institute)
ANDERSON S. L. (Westinghouse Electric Company, Nuclear Service)
Publication Information
Nuclear Engineering and Technology / v.37, no.6, 2005 , pp. 605-610 More about this Journal
Abstract
A method to estimate the relative sensitivity of a self-powered rhodium detector for an upcoming cycle is developed by combining the rhodium depletion data from a nuclear design with the site measurement data. This method can be used both by nuclear power plant designers and by site staffs of Korean standard nuclear power plants for determining which rhodium detectors should be replaced during overhauls.
Keywords
SPND; Sensitivity; Rhodium Detector; Lifetime; ICI Replacement; KSNP;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
1 W. B. Terney, J. L. Biffer, C. O. Dechand, A. Jonsson, and R. M. Versluis, 'The C-E CECOR Fixed In-Core Detector Analysis System,' Trans. Am. Nucl. Soc., 44, 542 (1983)
2 G. G. Kim and N. Z. Cho, 'Investigation of the Sensitivity Depletion Lows for Rhodium Self-Powered Neutron Detectors (SPNDs),' J. of KNS, vol. 33, no. 2, p.121-131, April (2001)   과학기술학회마을
3 T. G. Ober and J. W. Malloy, 'An Advanced Model for the Prediction of the Total Burnup-Dependent Self-Powered Rhodium Detector Response,' Proc. Int. Conf. on Mathematics and Computations, Reactor Physics and Environmental Analysis, vol. 2, p.22-31, Portland, Oregon (1995)
4 A. Jonsson, W. B. Terney and M. W. Crump, 'Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed In-core Detector System,' CENPD-153-P, Rev. 1-P-A (1980)
5 Final Safety Analysis Report for Yonggwang Unit 3 & 4, Korea Electric Power Company
6 'Users Manual for ROCS: Coarse- and Fine-Mesh Advanced Diffusion Theory Code for Reactor Core Analysis,' Combustion Engineering, Inc., CE-CES-4-P Revision 11-P (1996)
7 'Overview Description of the Core Operation Limit Supervisory System (COLSS),' CEN-312-P, Revision 01-P, Combustion Engineering, Inc. (1986)