Published May 2000 | Version v1
Miscellaneous

Gap estimation method between calandria tube and liquid injection nozzle in CANDU reactor

  • 1. Korea Electric Power Research Institute, Taejon (Korea, Republic of)

Description

As the calandria tube (made of zirconium alloy) is sagging due to its thermal and irradiation creep during the plant operation, it possibly contacts with liquid injection nozzle crossing beneath the calandria tube, which subsequently results in difficulties on the safe operation. It is therefore necessary to check the gap for the confirmation of no contacts between the two tubes, calandria tube and liquid injection tube, with a proper measure during the life of plant. In this study, a methodology to estimate the gap between the two tubes utilizing the classical beam theory is proposed. The saggings of the calandria tube and liquid injection tube are modelled as mathematical deflection curves, the coefficient of which is determined by sagging data measured at viewing port by an ultrasonic measurement device. The proposed method was found to be well fitted to some measured data, which means that the method can be applied to Wolsung-1 for the measurement of the gap between calandria tube and liquid injection tube

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
[CDROM]
Journal Page Range
[11 p.]

Conference

Title
2000 spring meeting of the KNS
Dates
26-27 May 2000
Place
Kori (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
34027551
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CALANDRIAS; CANDU TYPE REACTORS; CREEP; INJECTION; NOZZLES; TUBES; WOLSUNG-1 REACTOR
Descriptors DEC
CANDU TYPE REACTORS; CONTAINERS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INTAKE; MECHANICAL PROPERTIES; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS

Optional Information

Notes
7 refs, 7 figs, 2 tabs