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In-Pile Diameter Measurement of Light Water Reactor Test Fuel Rods for Assessment of Pellet-Cladding Mechanical Interaction

  • Published:1980-11 Issue:1 Volume:51 Page:33-44
  • ISSN:0029-5450
  • Container-title:Nuclear Technology
  • language:en
  • Short-container-title:Nuclear Technology

Author:

Uchida Masaaki1,Ichikawa Michio1

Affiliation:

1. Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference9 articles.

1. In-Core Study of the Mechanical Interaction between Fuel and Cladding

2. J. VEEDER, “Thermo-Elastic Expansion of Finite Cylinders,” AECL-2660, Atomic Energy of Canada, Ltd. (1967).

3. L. J. SIEFKEN, “FRAP-T4-A Computer Code for the Transient Analysis of Oxide Fuel Rods,” CDAP-TR-78-027, EG&G Idaho, Inc. (1978).

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1. An impedance-based diameter gauge for in-pile fuel deformation measurements;Instrumentation Science & Technology;2019-05-29

2. LWR Fuel Safety Research with Particular Emphasis on RIA/LOCA and Other Conditions;Journal of Nuclear Science and Technology;1989-01

3. The effect of cladding restraint on fission gas release behavior;Journal of Nuclear Materials;1988-08

4. IRRADIATION STUDIES OF JAERIS FUEL AT HALDEN REACTOR;J NUCL SCI TECHNOL;1988

5. Irradiation Studies of JAERI's Fuel at Halden Reactor;Journal of Nuclear Science and Technology;1988-08
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