Open AccessUSNRC-OECD Halden Project fuel behavior test program: experiment data report for test assemblies IFA-226 and IFA 239
Author(s) -
E.T. Laats,
P.E. MacDonald,
W.J. Quapp
Publication year - 1975
Language(s) - English
Resource type - Reports
DOI - 10.2172/4078773
Subject(s) - cladding (metalworking) , calibration , boiling water reactor , nuclear engineering , detector , test data , neutron , nuclear physics , materials science , physics , computer science , engineering , composite material , optics , quantum mechanics , programming language
The experimental data which were obtained from the IFA-226 and IFA-239 test assemblies during operation in the Halden Boiling Water Reactor are reported. Included are cladding elongation, fuel centerline temperature, internal gas pressure, and power history data from IFA-226 which were obtained from November 1971 through April 1974, and cladding elongation, diametral profile, and power history data from IFA-239 covering the period from March 1973 through April 1974. The data, presented in the form of composite graphs, have been analyzed only to the extent necessary to assure that they are reasonable and correct. A description of these mixed oxide fuel test assemblies and their instrumentation is presented. Test pin fabrication history, instrument calibration data, assembly power calibration methods, and the neutron detector data reduction technique are included as appendices. (auth