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.
Dutta, N G;
Ahmad, Anis;
Kulkarni, P G;
Purushotham, D S.C.
[1]
- Bhabha Atomic Research Centre, Bombay (India). Atomic Fuels Div.
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}
}
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}
}