Actions for A probabilistic method for leak-before-break analysis of CANDU reactor pressure tubes [electronic resource].

Email RIS file
Bookmark
Report an Issue

A probabilistic method for leak-before-break analysis of CANDU reactor pressure tubes [electronic resource].

Published
Washington, D.C. : U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, 1997.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
pages 733-740 : digital, PDF file
Additional Creators
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology and United States. Department of Energy. Office of Scientific and Technical Information
Access Online

Availability

I Want It
I Want It

Finding items...

Restrictions on Access
Free-to-read Unrestricted online access
Summary
A probabilistic code for the prediction of the cumulative probability of pressure tube ruptures in CANDU type reactors is described. Ruptures are assumed to result from the axial growth by delayed hydride cracking. The BLOOM code models the major phenomena that affect crack length and critical crack length during the reactor sequence of events following the first indications of leakage. BLOOM can be used to develop unit-specific estimates of the actual probability of pressure rupture in operating CANDU reactors and supplement the existing leak before break analysis.
Report Numbers
E 1.99:nureg/cp--0155
E 1.99: conf-9510432--
conf-9510432--
nureg/cp--0155
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
04/01/1997.
"nureg/cp--0155"
" conf-9510432--"
"TI97004806"
Seminar on leak before break in reactor piping and vessels, Lyon (France), 9-11 Oct 1995.
Wilkins, B.J.S.; Puls, M.P.; Rigby, G.L.
View MARC record | catkey: 14363954