Published 1978 | Version v1
Report

Preservice and inservice inspection of light water moderated nuclear power plant pressure-containing components

  • 1. Southwest Research Inst., San Antonio, TX (USA)

Description

The early nuclear systems for production of commercial power, both pressurized and boiling water reactors, were designed and fabricated in accordance with the Codes then used for fossil-fired power generating stations with some design changes for increased inspectability during fabrication. In the past few years, major strides have been made in inservice inspection technology. Work has been underway to determine the reliability of nondestructive testing methods and to develop formal inspection programs throughout the world. The major problems associated with inservice inspection are the scarcity of qualified personnel, the variability in procedures and data recording between inspection agencies, and the radiation exposure of inspection personnel. Future work will be required to more completely mechanize piping inspections to reduce radiation exposure and to standardize inspection procedures, equipment, and certification of personnel. Worldwide attention to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, the size and integrity of inspection agencies, and such efforts as the development of SNT-TC-1A by the American Society for Nondestructive Testing emphasize the importance of inservice inspection to nuclear safety. (author)

Additional details

Publishing Information

Imprint Title
Specialist meeting on the ultrasonic inspection of reactor components, Daresbury, 27-29 September 1976. Proceedings
Journal Page Range
Paper 23.
Report number
CSNI-R--14

Conference

Title
Specialists meeting on the ultrasonic inspection of reactor components.
Dates
27 - 29 Sep 1976.
Place
Daresbury, UK.