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Development of advanced design features for KNGR reactor vessel and internals

Abstract

Developments of KNGR design require to enhance the design to implement the design requirements, such as plant life time from 40 years to 60 years, safety, performance and structure and components design. The designs used for existing nuclear power plants should be modified or improved to meet the requirements in KNGR design. The purpose of the task is to develop the Advanced Design Features (ADF) related to mechanical and structural design for KNGR reactor vessel and reactor internals. The structural integrity for the System 80+ reactor vessel, of which design life is 60 years, was reviewed. EPRI-URD, CESSAR-DC, and the present design status and characteristics of System 80+ reactor vessel were comparatively studied and the improvement of reactor vessel surveillance program was investigated. The performance and aseismic characteristics of the CE-type CEDM, which will be used in System 80+, are investigated. The driving cycles of CEDM are evaluated for the load follow operation(LFO), of which Mode K is being developed by KAERI. The position of the USNRC, EPRI, ABB-CE, and industries on the elimination of OBE are reviewed, and especially ABB-CE System 80+ FSER is reviewed in detail. For the pre-stage of the verification of the OBE elimination from the  More>>
Authors:
Park, Jong Kyun; Ru, Bong; Lee, Jae Han; Lee, Hyung Yeon; Kim, Jong Bum; Ku, Kyung Heoy; Lee, Ki Young; Lee, Jun; Kim, Young In [1] 
  1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Publication Date:
Dec 01, 1995
Product Type:
Technical Report
Report Number:
KAERI/TR-613/95
Reference Number:
SCA: 210200; 220200; PA: AIX-27:063032; EDB-96:126217; NTS-97:001446; SN: 96001653170
Resource Relation:
Other Information: PBD: Dec 1995
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR VESSELS; CONTROL ELEMENTS; CONTROL ROD DRIVES; EARTHQUAKES; FATIGUE; SEISMIC DETECTORS
OSTI ID:
281032
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE96634432; TRN: KR9600047063032
Availability:
INIS; OSTI as DE96634432
Submitting Site:
KRN
Size:
122 p.
Announcement Date:

Citation Formats

Park, Jong Kyun, Ru, Bong, Lee, Jae Han, Lee, Hyung Yeon, Kim, Jong Bum, Ku, Kyung Heoy, Lee, Ki Young, Lee, Jun, and Kim, Young In. Development of advanced design features for KNGR reactor vessel and internals. Korea, Republic of: N. p., 1995. Web.
Park, Jong Kyun, Ru, Bong, Lee, Jae Han, Lee, Hyung Yeon, Kim, Jong Bum, Ku, Kyung Heoy, Lee, Ki Young, Lee, Jun, & Kim, Young In. Development of advanced design features for KNGR reactor vessel and internals. Korea, Republic of.
Park, Jong Kyun, Ru, Bong, Lee, Jae Han, Lee, Hyung Yeon, Kim, Jong Bum, Ku, Kyung Heoy, Lee, Ki Young, Lee, Jun, and Kim, Young In. 1995. "Development of advanced design features for KNGR reactor vessel and internals." Korea, Republic of.
@misc{etde_281032,
title = {Development of advanced design features for KNGR reactor vessel and internals}
author = {Park, Jong Kyun, Ru, Bong, Lee, Jae Han, Lee, Hyung Yeon, Kim, Jong Bum, Ku, Kyung Heoy, Lee, Ki Young, Lee, Jun, and Kim, Young In}
abstractNote = {Developments of KNGR design require to enhance the design to implement the design requirements, such as plant life time from 40 years to 60 years, safety, performance and structure and components design. The designs used for existing nuclear power plants should be modified or improved to meet the requirements in KNGR design. The purpose of the task is to develop the Advanced Design Features (ADF) related to mechanical and structural design for KNGR reactor vessel and reactor internals. The structural integrity for the System 80+ reactor vessel, of which design life is 60 years, was reviewed. EPRI-URD, CESSAR-DC, and the present design status and characteristics of System 80+ reactor vessel were comparatively studied and the improvement of reactor vessel surveillance program was investigated. The performance and aseismic characteristics of the CE-type CEDM, which will be used in System 80+, are investigated. The driving cycles of CEDM are evaluated for the load follow operation(LFO), of which Mode K is being developed by KAERI. The position of the USNRC, EPRI, ABB-CE, and industries on the elimination of OBE are reviewed, and especially ABB-CE System 80+ FSER is reviewed in detail. For the pre-stage of the verification of the OBE elimination from the design, the review of the seismic responses, i.e.. shear forces and moments, of YGN 3/4 RI was performed and the ratio of OBE response to SSE response was analysed. The screening criteria were reviewed to evaluate the integrity against pressurized thermal shock (PTS) for RV belt-line of System 80+. The evaluation methods for fracture integrity when screening criteria are not met were reviewed. The structural characteristics of IRWST spargers of System 80+ were investigated and the effect of hydrodynamic loads on NSSS was reviewed. 18 figs., 9 tabs., 40 refs. (Author) .new.}
place = {Korea, Republic of}
year = {1995}
month = {Dec}
}