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Vibration test on KMRR reactor structure and primary cooling system piping

Abstract

Most equipments, piping systems and reactor structures in nuclear power plants are subjected to flow induced vibration due to high temperature and high pressure coolant flowing inside or outside of the equipments, systems and structures. Because the flow induced vibration sometimes causes significant damage to reactor structures and piping systems, it is important and necessary to evaluate the vibration effect on them and to prove their structural integrity. Korea Multipurpose Research Reactor (KMRR) being constructed by KAERI is 30 MWt pool type research reactor. Since its main structures and piping systems were designed and manufactured in accordance with the standards and guidelines for commercial nuclear power plant, it was decided to evaluate their vibratory response in accordance with the standards and guidelines for commercial NPP. The objective of this vibration test is the assessment of vibration levels of KMRR reactor structure and primary cooling piping system for their structural integrity under the steady-state or transient operating condition. 38 figs, 14 tabs, 2 refs. (Author).
Authors:
Chung, Seung Hoh; Kim, Tae Ryong; Park, Jin Hoh; Park, Jin Suk; Ryoo, Jung Soo [1] 
  1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Publication Date:
Oct 01, 1994
Product Type:
Technical Report
Report Number:
KAERI-RR-1417/94
Reference Number:
SCA: 220600; PA: AIX-27:015786; EDB-96:036007; NTS-96:014566; SN: 96001546350
Resource Relation:
Other Information: PBD: Oct 1994
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; KMR REACTOR; MECHANICAL VIBRATIONS; DIGITAL FILTERS; FREQUENCY ANALYSIS; PRIMARY COOLANT CIRCUITS; REACTOR COMPONENTS; STEAM LINES
OSTI ID:
186452
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE96614687; TRN: KR9500114015786
Availability:
INIS; OSTI as DE96614687
Submitting Site:
KRN
Size:
213 p.
Announcement Date:
Feb 28, 1996

Citation Formats

Chung, Seung Hoh, Kim, Tae Ryong, Park, Jin Hoh, Park, Jin Suk, and Ryoo, Jung Soo. Vibration test on KMRR reactor structure and primary cooling system piping. Korea, Republic of: N. p., 1994. Web.
Chung, Seung Hoh, Kim, Tae Ryong, Park, Jin Hoh, Park, Jin Suk, & Ryoo, Jung Soo. Vibration test on KMRR reactor structure and primary cooling system piping. Korea, Republic of.
Chung, Seung Hoh, Kim, Tae Ryong, Park, Jin Hoh, Park, Jin Suk, and Ryoo, Jung Soo. 1994. "Vibration test on KMRR reactor structure and primary cooling system piping." Korea, Republic of.
@misc{etde_186452,
title = {Vibration test on KMRR reactor structure and primary cooling system piping}
author = {Chung, Seung Hoh, Kim, Tae Ryong, Park, Jin Hoh, Park, Jin Suk, and Ryoo, Jung Soo}
abstractNote = {Most equipments, piping systems and reactor structures in nuclear power plants are subjected to flow induced vibration due to high temperature and high pressure coolant flowing inside or outside of the equipments, systems and structures. Because the flow induced vibration sometimes causes significant damage to reactor structures and piping systems, it is important and necessary to evaluate the vibration effect on them and to prove their structural integrity. Korea Multipurpose Research Reactor (KMRR) being constructed by KAERI is 30 MWt pool type research reactor. Since its main structures and piping systems were designed and manufactured in accordance with the standards and guidelines for commercial nuclear power plant, it was decided to evaluate their vibratory response in accordance with the standards and guidelines for commercial NPP. The objective of this vibration test is the assessment of vibration levels of KMRR reactor structure and primary cooling piping system for their structural integrity under the steady-state or transient operating condition. 38 figs, 14 tabs, 2 refs. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Oct}
}