Published March 1987 | Version v1
Report Restricted

The role of natural circulation in the FFTF [Fast Flux Test Facility] passive safety tests

Creators

Description

A series of tests were completed at the Fast Flux Test Facility to demonstrate the passive safety characteristics of liquid metal reactors with natural circulation flow. The first test consisted of transition from forced to natural circulation flow at an initial decay power of 0.3%. The second test represented an unprotected loss-of-flow transient to natural circulation from 50% power with the control rods prevented from scramming into the core. The third test was a steady-state, natural circulation condition with core fission powers up ato about 2.3%. Core sodium data and results of single and multi-channel computer models confirmed the reliability and effectiveness of natural circulation flow for liquid metal reactor safety

Availability note (English)

Available from NTIS, PC A03/MF A01; 1 as DE87010717.

Files

Restricted

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Additional details

Publishing Information

Imprint Pagination
28 p.
Report number
HEDL-SA--3652

Conference

Title
Symposium on technology of glass, ceramic, or glass-ceramic to metal sealing.
Dates
13-18 Dec 1987.
Place
Boston, MA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19046577
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; FLOW MODELS; HEAT TRANSFER; I CODES; LMFBR TYPE REACTORS; LOSS OF FLOW; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; S CODES; SODIUM
Descriptors DEC
ACCIDENTS; ALKALI METALS; BREEDER REACTORS; COMPUTER CODES; COOLING SYSTEMS; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MATHEMATICAL MODELS; METALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS

Optional Information

Notes
Portions of this document are illegible in microfiche products.
Secondary number(s)
CONF-871207--4.