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Title: Eddy Current Flow Measurements in the FFTF

Abstract

The Fast Flux Test Facility (FFTF) is the most recent liquid metal reactor (LMR) to be designed, constructed, and operated by the U.S. Department of Energy (DOE). The 400-MWt sodium-cooled, fast-neutron flux reactor plant was designed for irradiation testing of nuclear reactor fuels and materials for liquid metal fast breeder reactors. Following shut down of the Clinch River Breeder Reactor Plant (CRBRP) project in 1983, FFTF continued to play a key role in providing a test bed for demonstrating performance of advanced fuel designs and demonstrating operation, maintenance, and safety of advanced liquid metal reactors. The FFTF Program provides valuable information for potential follow-on reactor projects in the areas of plant system and component design, component fabrication, fuel design and performance, prototype testing, site construction, and reactor control and operations. This report provides HEDL-TC-1344, “ECFM Flow Measurements in the FFTF Using Phase-Sensitive Detectors”, March 1979.

Authors:
 [1];  [1];  [1];  [1]
  1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1406803
Report Number(s):
PNNL-26202
453060037
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats

Nielsen, Deborah L., Polzin, David L., Omberg, Ronald P., and Makenas, Bruce J.. Eddy Current Flow Measurements in the FFTF. United States: N. p., 2017. Web. doi:10.2172/1406803.
Nielsen, Deborah L., Polzin, David L., Omberg, Ronald P., & Makenas, Bruce J.. Eddy Current Flow Measurements in the FFTF. United States. doi:10.2172/1406803.
Nielsen, Deborah L., Polzin, David L., Omberg, Ronald P., and Makenas, Bruce J.. Thu . "Eddy Current Flow Measurements in the FFTF". United States. doi:10.2172/1406803. https://www.osti.gov/servlets/purl/1406803.
@article{osti_1406803,
title = {Eddy Current Flow Measurements in the FFTF},
author = {Nielsen, Deborah L. and Polzin, David L. and Omberg, Ronald P. and Makenas, Bruce J.},
abstractNote = {The Fast Flux Test Facility (FFTF) is the most recent liquid metal reactor (LMR) to be designed, constructed, and operated by the U.S. Department of Energy (DOE). The 400-MWt sodium-cooled, fast-neutron flux reactor plant was designed for irradiation testing of nuclear reactor fuels and materials for liquid metal fast breeder reactors. Following shut down of the Clinch River Breeder Reactor Plant (CRBRP) project in 1983, FFTF continued to play a key role in providing a test bed for demonstrating performance of advanced fuel designs and demonstrating operation, maintenance, and safety of advanced liquid metal reactors. The FFTF Program provides valuable information for potential follow-on reactor projects in the areas of plant system and component design, component fabrication, fuel design and performance, prototype testing, site construction, and reactor control and operations. This report provides HEDL-TC-1344, “ECFM Flow Measurements in the FFTF Using Phase-Sensitive Detectors”, March 1979.},
doi = {10.2172/1406803},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Feb 02 00:00:00 EST 2017},
month = {Thu Feb 02 00:00:00 EST 2017}
}

Technical Report:

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