Published January 1988 | Version v1
Report Restricted

Recent fuel-coolant interaction experiments conducted in the FITS [Fully Instrumented Test Site] vessel

Description

The US Nuclear Regulatory Commission has been sponsoring research at Sandia National Laboratories to investigate the interaction of molten core materials with water. These interactions play an important role during severe core-melt accidents inside a pressurized light water reactor. They influence the rates and magnitudes of hydrogen and steam generated, the characteristics of the debris bed created in the lower plenum after melt-relocation, the transient pressurization of the primary system, and the fission product release characteristics and timimg. Furthermore, since the core is cooled with water, an understanding of the parameters that control the behavior of these fuel-coolant interactions (FCIs) is necessary to make correct accident-management decisions. In an effort to assist in the understanding of these and other FCI-related issues, as well as provide important data for model development and validation, six FCI experiments were conducted at Sandia. Results discussed include the transient gas-phase pressures, the rate and magnitude of hydrogen generation and the post-test debris characteristics

Availability note (English)

Available from NTIS, PC A03/MF A01;1 as DE88005734.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
17 p.
Report number
SAND--87-2467C

Conference

Title
25. American Society of Mechanical Engineers/American Institute of Chemical Engineers/American Nuclear Society national heat transfer conference.
Dates
24-27 Jul 1988.
Place
Houston, TX (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19093416
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL-COOLANT INTERACTIONS; MELTDOWN; PWR TYPE REACTORS; REACTOR CORES; SIMULATION
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-880724--10.