You need JavaScript to view this

Back pressure helium leak testing of fuel elements for Dhruva research reactor

Abstract

Leak tightness specification on fuel elements for reactor use is always very stringent. The fuel element fabricated for Dhruva reactor is specified to be leak-tight up to 1 x 10{sup -8} std. cc/sec. The fuel element consists of natural metallic uranium rod around 12.5 mm diameter and 3 meter long in encased in aluminium tube and seal welded at both ends. Since helium gas is not filled inside the fuel element while doing seal welding, the only way to do helium leak testing of such fuel rods is by back-pressure technique. This paper describes the development of test facility for carrying out such test and discusses the experiences of carrying out helium leak testing by back-pressure technique on more than 700 numbers of fuel rods for Dhruva reactor. (author). 4 refs., 3 figs., 1 tab.
Authors:
Dutta, N G; Ahmad, Anis; Kulkarni, P G; Purushotham, D S.C. [1] 
  1. Bhabha Atomic Research Centre, Bombay (India). Atomic Fuels Div.
Publication Date:
Dec 31, 1994
Product Type:
Conference
Report Number:
CONF-9412137-
Reference Number:
SCA: 220600; 210400; PA: AIX-28:043056; EDB-97:085170; SN: 97001804953
Resource Relation:
Conference: NDE `94: national seminar on non-destructive evaluation techniques, Mumbai (India), 8-9 Dec 1994; Other Information: PBD: 1994; Related Information: Is Part Of National seminar on non-destructive evaluation techniques: proceedings cum souvenir; Dutta, N.G.; Kulkarni, P.G.; Purushotham, D.S.C. [eds.] [Bhabha Atomic Research Centre, Bombay (India). Atomic Fuels Div.]; PB: [475] p.
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; FUEL RODS; LEAK TESTING; DHRUVA REACTOR; HELIUM; LEAK DETECTORS; NATURAL URANIUM; QUALITY CONTROL
OSTI ID:
490138
Research Organizations:
Indian Society for Non-Destructive Testing, Mumbai (India). Bombay Chapter
Country of Origin:
India
Language:
English
Other Identifying Numbers:
TRN: IN9700833043056
Submitting Site:
INIS
Size:
pp. [6]
Announcement Date:

Citation Formats

Dutta, N G, Ahmad, Anis, Kulkarni, P G, and Purushotham, D S.C. Back pressure helium leak testing of fuel elements for Dhruva research reactor. India: N. p., 1994. Web.
Dutta, N G, Ahmad, Anis, Kulkarni, P G, & Purushotham, D S.C. Back pressure helium leak testing of fuel elements for Dhruva research reactor. India.
Dutta, N G, Ahmad, Anis, Kulkarni, P G, and Purushotham, D S.C. 1994. "Back pressure helium leak testing of fuel elements for Dhruva research reactor." India.
@misc{etde_490138,
title = {Back pressure helium leak testing of fuel elements for Dhruva research reactor}
author = {Dutta, N G, Ahmad, Anis, Kulkarni, P G, and Purushotham, D S.C.}
abstractNote = {Leak tightness specification on fuel elements for reactor use is always very stringent. The fuel element fabricated for Dhruva reactor is specified to be leak-tight up to 1 x 10{sup -8} std. cc/sec. The fuel element consists of natural metallic uranium rod around 12.5 mm diameter and 3 meter long in encased in aluminium tube and seal welded at both ends. Since helium gas is not filled inside the fuel element while doing seal welding, the only way to do helium leak testing of such fuel rods is by back-pressure technique. This paper describes the development of test facility for carrying out such test and discusses the experiences of carrying out helium leak testing by back-pressure technique on more than 700 numbers of fuel rods for Dhruva reactor. (author). 4 refs., 3 figs., 1 tab.}
place = {India}
year = {1994}
month = {Dec}
}