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Published June 1963 | Version v1
Journal article

Experimental study on mechanical strength of fuel cladding tube under the loss of coolant accident

  • 1. Mitsubishi Atomic Power Industries, Inc., Omiya, Saitama (Japan)
  • 2. Tokyo University, Tokyo (Japan)
  • 3. Japan Atomic Industrial Forum, Inc., Tokyo (Japan)

Description

The objects of this experimental study are to verify the behavior of the fuel cladding tube under the loss of coolant accident and to correlate the above result with the mechanical properties of the tube materials. AISI 304L, 347 stainless steel and Zircaloy-2 were selected for test cladding materials. The study consists of four sections as follow: (1) Analysis of the loss of coolant accident for PWR and BWR, and the determination of the experimental conditions. (2) Tensile test of cladding materials at high temperature and at the various moderate load rates. (Test A) (3) High temperature burst test of the various size cladding tubes. (Test B) (4) Dynamic burst test realizing the condition of the loss of coolant accident. (Test C) It is concluded from a series of the above experiments that the strength of the cladding tube is scarcely affected with such a load rate as the pressure decreasing rate at the loss of coolant accident and it is possible to estimate the bursting pressure of the fuel cladding tube with the results of the tensile test to the materials. (author)

Additional details

Additional titles

Original title (Japanese)
軽水炉の燃料被覆管耐圧試験

Identifiers

Publishing Information

Journal Title
Nippon Genshiryoku Gakkai-Shi
Journal Volume
5
Journal Issue
6
Series
雑誌名:日本原子力学会誌
Journal Page Range
p. 510-519
ISSN
0004-7120

Optional Information

Notes
5 refs., 14 figs., 8 tabs., 6 photos