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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.
G. Bandyopadhyay
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 62-78
Technical Paper | Fuel | doi.org/10.13182/NT78-A26700
Articles are hosted by Taylor and Francis Online.
To evaluate the role of fission gas in hypothetical core disruptive accidents, experimental and analytical information describing the fission gas behavior in rapid temperature transients is urgently needed. In the present work, a direct-electrical-heating apparatus was used to obtain information on the fission gas behavior and the response of mixed-oxide fuel elements to simulated thermal transient conditions. The experimental results indicate that fission gas response and swelling behavior are strongly dependent on the transient heating rate, and that fission gas can contribute significantly to the failure of a fuel stack during a temperature transient. The microstructural results from these tests were subsequently used to perform a limited verification of the fission gas release and swelling code, FRAS, which was developed to describe the fission gas release behavior in rapid temperature transients. A comparison of the measured intragranular bubble sizes (and in some cases bubble densities) with the calculated bubble sizes (and densities) revealed that the current version of the FRAS code is inadequate in some transient conditions. A nonequilibrium analysis of bubble coalescence may be necessary to describe the fission gas behavior in such temperature transients.