Published 1985 | Version v1
Book

Experience in the application of the IAEA QA code and guides to the manufacture of nuclear reactor components

  • 1. Bhabha Atomic Research Centre, Bombay (India)

Description

India has made considerable progress in the indigenous manufacture of 'Quality' nuclear reactor components. All activities associated with the development of atomic energy from mining of strategic minerals to the design, construction, and operation of nuclear power plants including supporting research and development efforts are mainly carried out by the Department of Atomic Energy (DAE). Through the sustained efforts of DAE, the major industries, both in public and private sectors supplying nuclear components have now adopted the practice of systematic quality assurance (QA). The stringent QA steps are mandatory for achieving the desired quality in the manufactured nuclear components. Control blades for BWRs are now indigenously manufactured by the Atomic Fuels Division (AFD) of Bhabha Atomic Research Centre (BARC), a constituent unit of DAE. For the Project Dhruva, a 100 MW(th) nuclear reactor, constructed at BARC, Trombay, Bombay, an independent cell was formed to carry out quality audit on the manufactured components. The components were designed, fabricated, inspected and tested to the desired quality level. The QA activities were enforced from the procurement of raw materials to the audit of the completed component for monitoring the manufacturer's continued compliance with the design. The major components of Dhruva, viz. calandria, end-shield, coolant channels, heat exchangers, etc., were covered under these quality audit activities. The paper highlights the QA programme implemented in the manufacture of control blades for BWRs, illustrated with a typical example, the end-shield for Dhruva. The authors consider that the recommendations and guidelines provided in the documents 50-SG-QA3, 50-SG-QA8, 50-SG-QA10, etc., were useful in providing a formal and systematic framework, under which various quality assurance functions have been carried out

Additional details

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna (Austria)
ISBN
92-0-020185-7
Imprint Title
IAEA safety codes and guides (NUSS) in the light of current safety issues
Imprint Pagination
718 p.
Series
Proceedings series.
Journal Page Range
p. 471-486.

Conference

Title
International symposium on safety codes and guides (NUSS) in the light of current safety issues.
Dates
29 Oct - 2 Nov 1984.
Place
Vienna (Austria).

INIS

Country of Publication
Austria
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
16081136
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTROL ELEMENTS; FABRICATION; INDIA; INSPECTION; NUCLEAR POWER PLANTS; QUALITY ASSURANCE; QUALITY CONTROL; SPECIFICATIONS; STANDARDIZATION
Descriptors DEC
ASIA; CONTROL; DEVELOPING COUNTRIES; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
IAEA-SM--275/24.