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ACRS seeking new committee member
The Nuclear Regulatory Commission’s Advisory Committee on Reactor Safeguards (ACRS) is currently seeking qualified candidates to fill an open committee member position. Applications for the position will be accepted until July 30. The ACRS is the world’s oldest organization devoted to reactor safety, and the group reports directly to the NRC’s commissioners in order to provide independent technical reviews of and advice on a wide variety of nuclear topics.
H. Yamada
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 324-331
Technical Paper | Material | doi.org/10.13182/NT79-A32187
Articles are hosted by Taylor and Francis Online.
To understand the effects of the fuel-cladding mechanical interaction on the failure of 20% cold-worked Type 316 stainless-steel cladding during anticipated nuclear reactor transients, the transient mechanical response of the cladding was investigated using a transient tube burst method at a heating rate of 5.6° C/s and axial-to-hoop-stress ratios in the range of ½ to 2. The failure temperatures were observed to remain essentially constant for the transient tests at axial-to-hoop-stress ratios between ½ and 1, but to decrease with an increase in axial-io-hoop-stress ratios above unity. The uniform diametral strains to failure were observed to decrease monotonically with an increase in axial-to-hoop-stress ratio from ½ to 2, and in general, the uniform axial strains to failure were observed to increase with an increase in axial-to-hoop-stress ratio. The fracture of the cladding during thermal transients was found to be strongly affected by the maximum principal stress but not by the effective stress.