Published January 1992 | Version v1
Report Metadata-only

Recirculation pump shaft cracking experience at Chin-Shan station

Creators

  • 1. Taiwan Nuclear Power Co., Taipei (Taiwan)

Description

This paper reviews the experience of the Chin-Shan Nuclear Power Station with recirculation pump shaft cracking experience. The topics of the paper include a description of the Chin-Shan boiling water reactor plant, a summary of the disassembly and inspection of the recirculation pump, a description of the provisions for pump inspection, the pump vibration monitoring system, and the location of accelerometers, proximity probes, keyphasor and velocity transducers

Additional details

Publishing Information

Imprint Title
Proceedings: Main coolant pump workshop, 1991
Imprint Pagination
557 p.
Journal Page Range
p. 20.1-20.10.
Report number
EPRI-TR--100299

Conference

Title
Main coolant pump workshop -- 1991.
Dates
16-18 Apr 1991.
Place
Phoenix, AZ (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23075837
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACOUSTIC TESTING; CHINSHAN-1 REACTOR; CHINSHAN-2 REACTOR; CRACK PROPAGATION; CRACKS; FRACTURES; INSPECTION; MECHANICAL SHAFTS; MECHANICAL VIBRATIONS; MONITORING; PUMPS; REACTOR COOLING SYSTEMS
Descriptors DEC
BWR TYPE REACTORS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FAILURES; MACHINE PARTS; MATERIALS TESTING; NONDESTRUCTIVE TESTING; POWER REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-9104332--.