Published May 2015 | Version v1
Miscellaneous

Application of Full Equation in Kinematic Shock on Emergency Core Cooling System

  • 1. KHNP Central Research Institute, Daejeon (Korea, Republic of)

Description

Generic Letter 2008-01shows that the void packet inner of pipes in front of ECCS(Emergency Core Cooling System) pumps is very important effect element in analyzing head loss. The purpose of this paper is to develop the solution of the kinematic shock equation. In this work, the simplified equation of Perdu test study is changed into Full equation by our development study of calculating a kinematic shock. The development result of the solution of full equation is applied and compared with current simplified equation. Finally, the full equation method is used for calculating the criteria of void packet in Westinghouse type NPP in preliminary sample study. In this work's theoretical base is on the study of Seung-Chan Lee et al in KHNP in 2012. The new method of calculating the depth of the kinematic shock in U-type pipe in ECCS is introduced. The kinematic shock is strongly depended on the void packet velocity. In the part of verification, the difference between this work and Perdu experiment result is nothing in the condition of many iterations of Perdu simple model. In conclusion, this work's method is more efficient than Perdu simple model because of the use of only one-step calculation. In void packet criteria, using full equation, some results are calculated. The results are ranged from 0.3 ft''3 to 6.12ft''3 in Westinghouse type NPP

Part of:
Proceedings of the KNS 2015 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2015 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[3 p.]

Conference

Title
2015 spring meeting of the KNS
Dates
6-8 May 2015
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
47023377
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; COOLING SYSTEMS; ECCS; EQUATIONS; PIPES; USES; VOIDS
Descriptors DEC
ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; REACTOR PROTECTION SYSTEMS; TUBES

Optional Information

Notes
3 refs, 5 figs, 4 tabs