Published 1996 | Version v1
Miscellaneous

Numerical analysis on letdown system performance test for YGN 3

  • 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

Integrated performance test of Chemical and Volume Control System (CVCS) was successfully performed in 1994. However, an extensive effort to correct hardware and software problems in the letdown line was required mainly due to the lack of adequate simulation code to predict the test accurately. Although the LTC computer code was used during the YGN 3 and 4 NSSS design process, the code can not satisfactorily predict the test due to its insufficient letdown line modeling. This study developed a numerical model to simulate the letdown test by modifying the current LTC code, and then verified the model by comparing with the test data. The comparison shows that the modified LTC computer code can predict the transient behavior of letdown system tests very well. Especially, the model was verified to be able to predict the 'Stiction' phenomena which caused instantaneous fluctuations in the letdown back pressure and flowrate. Therefore, it is concluded that the modified LTC computer code with the ability of calculating the 'Stiction' phenomena will be very useful for future plant design and test predictions

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
3566 p.
Journal Page Range
p. 425-432

Conference

Title
1996 spring meeting of the KNS
Dates
31 May - 1 Jun 1996
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
37120238
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; CONTROL SYSTEMS; DESIGN; FLOW RATE; L CODES; NUMERICAL ANALYSIS; PERFORMANCE TESTING; STEAM SYSTEMS; TRANSIENTS; YONGGWANG-3 REACTOR; YONGGWANG-4 REACTOR
Descriptors DEC
COMPUTER CODES; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MATHEMATICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs, 11 figs, 1 tab