Actions for Reactor safety research programs. Quarterly report, July-September 1983 [electronic resource].

Email RIS file
Bookmark
Report an Issue

Reactor safety research programs. Quarterly report, July-September 1983 [electronic resource].

Published
Richland, Wash. : Pacific Northwest Laboratory, 1984.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators
Pacific Northwest Laboratory 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
Evaluations of nondestructive examination (NDE) techniques and instrumentation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, and examining NDE reliability and probabilistic fracture mechanics. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Experimental data and validated models are being used to determine a method for evaluating the acceptance of welded or weld-repaired stainless steel piping. Thermal-hydraulic models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Severe fuel damage accident tests are being conducted at the NRU reactor, Chalk River, Canada; and an instrumented fuel assembly irradiation program is being performed at Halden, Norway. Fuel assemblies and analytical support are being provided for experimental programs at other facilities, including the Super Sara Test Program, Ispra, Italy, and experimental programs at the Power Burst Facility.
Report Numbers
E 1.99:nureg/cr-3307-vol.3
E 1.99: pnl-4705-3
pnl-4705-3
nureg/cr-3307-vol.3
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
04/01/1984.
"nureg/cr-3307-vol.3"
" pnl-4705-3"
"DE84011212"
Edler, S.K.
Funding Information
AC06-76RL01830
View MARC record | catkey: 14369506