Active Neutron Multiplication Method for Fuel Lattices in Water
Author:
Affiliation:
1. Toshiba Corporation, Nuclear Engineering Laboratory, 4-1, Ukishima-cho Kawasaki-ku, Kawasaki-shi 210, Japan
2. Toshiba Corporation, Isogo Engineering Center 8, Shinsugita-cho, Isogo-ku, Yokohama-shi 235, Japan
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT92-A34631
Reference4 articles.
1. Present status of nondestructive burnup measurement techniques for spent fuel assemblies.
2. A Nondestructive Method for Light Water Reactor Fuel Assembly Identification
3. T. B. FOWLER, D. R. VONDY, and G. W. CUNNINGHAM, “Nuclear Reactor Core Analysis Code: CITATION,” ORNL-TM-2496, Rev. 2, Oak Ridge National Laboratory (1971).
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3. BASIC STUDIES ON NEUTRON EMISSION-RATE METHOD FOR BURNUP MEASUREMENT OF SPENT LIGHT-WATER-REACTOR FUEL BUNDLE;J NUCL SCI TECHNOL;1993
4. Basic Studies on Neutron Emission-Rate Method for Burnup Measurement of Spent Light-Water-Reactor Fuel Bundle;Journal of Nuclear Science and Technology;1993-01
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