Published October 1993 | Version v1
Report Restricted

Overview of the CSNI Project FALSIRE

Creators

  • 1. Gesellschaft fuer Anlagen- und Reaktorsicherheit, Koeln (Germany)

Description

This paper provides an overview of the activities of the Principal Working Group No. 3 of CSNI, the Fracture Assessment Group (FAG) which was given the task of reviewing work on fracture assessment methods as they relate to safety concerns in the nuclear industry. It provides an overview of project FALSIRE which was a coordinated program to assess a limited number of large scale reactor component tests. The tests were conducted under pressurized thermal shock conditions, such as might occur as a consequence of a LOCA in a reactor. The objective was to get detailed analyses on these experiments, to aid in the development of analytic capabilities, while avoiding the duplication of experimental efforts about the world community. The committee has also documented other large scale experiments beyond those included in the FALSIRE project, as well as experiments on reactor pressure vessel response to such thermal shock loading conditions. On the basis of information collected to this point the committee has suggestions related to further data needs on the part of this program. These are both experimental and analytic. 20 figs., 5 tabs

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Part of:
Proceedings of the Joint IAEA/CSNI Specialists' Meeting on Fracture Mechanics Verification by Large-Scale Testing held at Pollard Auditorium, Oak Ridge, Tennessee

Additional details

Publishing Information

Imprint Title
Proceedings of the Joint IAEA/CSNI Specialists' Meeting on Fracture Mechanics Verification by Large-Scale Testing held at Pollard Auditorium, Oak Ridge, Tennessee
Imprint Pagination
893 p.
Journal Page Range
p. 3-37.
Report number
NUREG/CP--0131

Conference

Title
Joint IAEA/CSNI specialists' meeting on fracture mechanics verification by large-scale testing.
Dates
26-29 Oct 1992.
Place
Oak Ridge, TN (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26001770
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRACTURE PROPERTIES; MATHEMATICAL MODELS; PRESSURE VESSELS; REACTOR MATERIALS; REACTORS; TESTING; THERMAL SHOCK
Descriptors DEC
CALCULATION METHODS; CONTAINERS; MATERIALS; MECHANICAL PROPERTIES; MECHANICS; NUMERICAL SOLUTION

Optional Information

Secondary number(s)
ORNL/TM--12413; CONF-9210411--.