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
- DOI
- 10.3327/jaesj.5.510;
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
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 55020819
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- AFTER-HEAT; BWR TYPE REACTORS; CHEMICAL COMPOSITION; CLADDING; DEPRESSURIZATION; LOSS OF COOLANT; PWR TYPE REACTORS; TENSILE PROPERTIES
- Descriptors DEC
- ACCIDENTS; DEPOSITION; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 14 figs., 8 tabs., 6 photos