Published 1981 | Version v1
Report Open

FFTF operating experience with sodium natural circulation: slides included

Description

The Fast Flux Test Facility (FFTF) has been designed for passive, back-up, safety grade decay heat removal utilizing natural circulation of the sodium coolant. This paper discusses the process by which operator preparation for this emergency operating mode has been assured, in paralled with the design verification during the FFTF startup and acceptance testing program. Over the course of the test program, additional insights were gained through the testing program, through on-going plant analyses and through general safety evaluations performed throughout the nuclear industry. These insights led to development of improved operator training material for control of decay heat removal during both forced and natural circulation as well as improvements in the related plant operating procedures

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.

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Additional details

Publishing Information

Imprint Pagination
33 p.
Report number
HEDL-SA--2326-FP

Conference

Title
American Nuclear Society's annual meeting.
Dates
7 - 12 Jun 1981.
Place
Miami Beach, FL, USA.

Optional Information

Secondary number(s)
CONF-810606--88.