Published April 2002 | Version v1
Miscellaneous

Inspection technology of Korean standard Reactor vessel

Creators

  • 1. Korea Plant Service and Engineering Co., Ltd., New Delhi (India)

Description

This paper is for the inspection technology of Korean standard Reactor vessel. KPS performed Korean standard Reactor vessel inspection for a part of Yonggwang unit 5 and full inspection of Yonggwang unit 6 on November in 2001. Korean standard Reactor vessel is different from Westinghouse and Framatome plants in design and material. Understanding design, structure and material is very important to prepare and to perform Reactor vessel inspection. Korean standard Reactor vessel has 6 Stabilizer lugs, 6 Core stop lugs and one Flow Baffle around Lower head to Bottom head weld(G4). They make very difficult to perform scanning of G4 by transducers and to install Lower Platform of robot system. Korean standard Reactor vessel has 2 Outlet Nozzles, 4 Inlet Nozzles and small curvature of Inner Radius regions. That small curvature's Inner Radius region needs a special technology to perform the area more than 90% of whole examination volume. The most significant difference of Korean standard Reactor vessel is that it does not have Safe End region because both of Reactor vessel and main reactor coolant system piping are carbon steel. Therefore, the technology for this nozzle to piping weld is very unique to be compared with other Westinghouse or Framatome plants. Described above, the inspection technology of Korean standard Reactor Vessel is very different from other Reactor Vessel due to different internal structure and material. The company which performs this 10 years ISI in future will need much investigation of structure and material to succeed in Reactor vessel inspection of Korean standard plant

Part of:
Proceedings of the 17th KAIF/KNS Annual Conference

Additional details

Publishing Information

Publisher
KAIF-KNS
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
Proceedings of the 17th KAIF/KNS Annual Conference
Imprint Pagination
618 p.
Journal Page Range
p. 365-370

Conference

Title
17. KAIF/KNS Annual Conference
Dates
17-19 Apr 2002
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44064780
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
DESIGN; INSPECTION; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR VESSELS; TRANSDUCERS
Descriptors DEC
CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:9 figs