Integrity assessment of structural models of a reactor vessel with notched nozzles under cyclic pressure loading
Conference
·
OSTI ID:4411622
From 2nd international congress for pressure vessel and piplng technology; San Antonio, Texas, USA (1 Oct 1973). See CONF-731003-P2. Tests undentaken to confirm the structural integrity of the Japan Power Demonstration Reactor (JPDR) pressure vessel are described. Prior testing considered two 1/3 scale pressure vessel models subjected to static and cyclic intemal pressure. Herein, experirnental results are reported for a 1/2 scale model of the JPDR pressure vessel with one prototypical nozzle and three additional nozzles. The strain distribution induced in the nozzles by 11O kg/cm/sup 2/ static intemal pressure was determined using many strain gages. Then, after rnachining a notch on the nozzles, crack propagation under cyclic internal pressure was determined using many strain gages. Then, after machining a notch on the nozzles, crack propagation under cyclic internal pressure was measured by an electric resistance probe (Smeck) gage. These experimental results are reported and discussed. Comparisons of measured and predicted behavior are given. The number of cycles to failure for the JPDR pressure vessel is estimated to be greater than 60,000. (auth)
- Research Organization:
- Japan Atomic Energy Research Inst., Tokai
- NSA Number:
- NSA-29-001986
- OSTI ID:
- 4411622
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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