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The human factor in licensing and operating the next generation of nuclear plants
As human factors specialists working at the intersection of human performance and nuclear operations, we are witnessing one of the nuclear sector’s most significant transitions in decades. The emergence of small modular reactors, microreactors, and other advanced designs is reshaping the industry’s landscape. Digital instrumentation and controls, passive safety systems, and increased automation are creating opportunities for greater safety margins and more flexible operation. These same features also fundamentally redefine what it means to “operate” a nuclear plant. Interactions among human roles, automation, and passive systems shape how people maintain awareness, exercise judgment, and intervene when necessary. These developments affect both operational realities and the regulatory foundations on which nuclear safety is built.
Hiroaki Suzuki, Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Soji Koikari, Kunio Hasegawa, Fumio Kojima, Seiichi Koshizuka, Derek H. Lister
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 194-209
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A18111
Articles are hosted by Taylor and Francis Online.
The possibility of thousands of flow-accelerated-corrosion (FAC) zones causes long and costly inspection procedures for nuclear, as well as fossil-fuel power plants, even if the number of zones is minimized on the basis of temperature and flow velocity. In order to decrease the number of inspection zones, suitable prediction or estimation procedures for FAC occurrence should be applied, and the resulting computer programs should be tuned with as many inspection data as possible. Such coupling of the estimation and inspection procedures should allow effective and reliable preparation to be made against FAC occurrence and propagation.This paper defines the FAC risk as the mathematical product of the possibility of the occurrence of wall thinning and its hazard scale. The possibility of the occurrence of wall thinning was designated as the time margin for pipe rupture determined by applying a one-dimensional FAC code, which could predict the wall-thinning rate with an accuracy within a factor of 2, while the hazard scale was defined as the volume of effluent steam and water from the ruptured mouth, which was enthalpy of water originally flowing in the pipe multiplied by the square of the pipe inner diameter. High FAC risk zones along entire cooling systems could be evaluated in only one-tenth or one-hundredth of the computer time as for a three-dimensional FAC code to determine the priority for inspection-order importance.