Published November 15, 1985 | Version v1
Report Restricted

Fast Flux Test Facility replacement of a primary sodium pump

Creators

Description

The Fast Flux Test Facility is a 400 MW Thermal Sodium Cooled Fast Reactor operated by Westinghouse Hanford Company for the US Department of Energy. During startup testing in 1979, the sodium level in one of the primary sodium pumps was inadvertently raised above the normal height. This resulted in distortion of the pump shaft. Pump replacement was carried out using special maintenance equipment. Nuclear radiation and contamination were not significant problems since replacement operations were carried out shortly after startup of the Fast Flux Test Facility

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE87004092.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
HEDL-SA--3364-FP

Conference

Title
Nuclear power plant maintenance meeting.
Dates
23-27 Mar 1986.
Place
Salt Lake City, UT (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18057712
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FFTF REACTOR; MAINTENANCE; PRIMARY COOLANT CIRCUITS; PUMPS; REACTOR COMPONENTS; SEPARATION PROCESSES
Descriptors DEC
COOLING SYSTEMS; EPITHERMAL REACTORS; EQUIPMENT; FAST REACTORS; LIQUID METAL COOLED REACTORS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS

Optional Information

Notes
Portions of this document are illegible in microfiche products.
Secondary number(s)
CONF-860311--12.