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Performance Qualification Test of the CRDM for JRTR
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 Title & Authors
Performance Qualification Test of the CRDM for JRTR
Choi, M.H.; Cho, Y.G.; Kim, J.H.; Lee, K.H.;
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A control rod drive mechanism(CRDM) is a reactor regulating system, which inserts, withdraws or maintains a control rod containing a neutron absorbing material within a reactor core to control the reactivity of the core. The top-mounted CRDM for Jordan Research and Training Reactor(JRTR) with 5 MW power has been designed and fabricated based on the HANARO's experience through KAERI and DAEWOO consortium project. This paper describes the performance qualification test results to demonstrate the operability of a prototype and four production CRDMs during the reactor lifetime. The driving performance, the drop performance and the endurance tests for CRDM are carried out at a test rig simulating the actual reactor conditions. A vibration of internal components due to the coolant flow is also measured using a laser vibrometer. As a result, the CRDMs are driven having a good driving performance without a malfunction between command and output signals for the stepping motor. Also, the pure drop time and the impact acceleration are within 0.72 s and 4.2 g to meet the design requirements, and the vibrational displacement of control rod is measured as maximum .
JRTR;CRDM;Performance Qualification;Drop Test;Endurance Test;Test Rig;
 Cited by
JRTR 제어봉구동장치의 내진시험,최명환;김경호;선종오;조영갑;

한국소음진동공학회논문집, 2016. vol.26. 5, pp.552-558 crossref(new window)
Lee, J. S., Choi, S. and Song, C. H., 2008, State of Art Report for Developing a Control Element Drive Mechanism of the APR+ Reactor, KAERI/AR-805/ 2008, KAERI.

Choi, M. H., Kim, J. H., Huh, H. and Yu, J. Y., 2010, Drop and Damping Characteristics of the CEDM for the Integral Reactor, Transactions of the Korean Society for Noise and Vibration Engineering, Vol. 20, No. 7, pp. 658-644. crossref(new window)

Park, C., Lee, B. C., Chae, H. T., Jeong, H. S., Cho, Y. G. and Seo, C. G., 2002, Status and Design Characteristics of Research Reactor, KAERI/AR-657/ 2002, KAERI.

Hanliang, B., Wenxiang, Z. and Duo, D., 2000, Studies on the Performance of the Hydraulic Control Rod Drive for the NHR-200, Nuclear Engineering and Design, Vol. 195, No. 1, pp. 117-121. crossref(new window)

Seo, C. G., Cho, Y. G., Ryu, J. S. and Shin, J. W., 2008, Improvement the CRDM Damping Mechanism for an AHR, Trans. of the KNS Spring Meeting.

Choi, M. H., Cho, Y. G., Kim, S. H., Huh, H. and Kim, J. I., 2011, Basic Design of the Top-mounted CRDM for a Reactor with Plate Type Fuels, Trans. of the KNS Autumn Meeting, pp. 71-72.

Huh, H. et al., 2011, Guidelines for Qualification Test of Control Rod Drive Mechanism, JR-317-KM-418-002, Rev.0, KAERI.

Kim, J. H. et al., 2012, Procedure for Qualification Test of CRDM, JR-317-SJ-442-001, Rev.1, POSCO Plantec.

ASME QME-1, 1997, Qualification of Active Mechanical Equipment Used in Nuclear Power Plants, ASME.

Choi, M. H., Cho, Y. G., Kim, J. H. and Lee, K. H., 2015, Performance and Endurance Tests of the Top-mounted CRDM for JRTR, Trans. of the KNS Spring Meeting.