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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.
Roberto Lenti, Luigi Mansani, Gianfranco Saiu
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 158-168
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35246
Articles are hosted by Taylor and Francis Online.
The new generation of evolutionary nuclear power plants, e.g., the Westinghouse AP600 and the General Electric simplified boiling water reactor, relies on a full reactor coolant system (RCS) depressurization to allow gravity injection from an in-containment tank and thereby assure long-term core cooling. Studies performed to support the licensing process and design of both evolutionary and innovative reactors have shown that cold water injection may, under particular plant conditions, induce a large plant depressurization. Preliminary studies have been performed to support the design of a passive injection and depressurization system (PIDS) based on the idea of depressurizing the RCS by mixing cold water with the RCS hot water and inducing steam condensation in the primary system. The analyses, performed with the RELAP5/ MOD3 computer code, show the response of a typical midsize pressurized water reactor plant [two loops, 600 MW(electric)] equipped with the PIDS. Different RCS injection locations including pressurizer, vessel upper head, and hot leg, and actuation at different residual reactor coolant masses have been investigated. Several factors, including RCS mixing, RCS residual mass at PIDS actuation, PIDS injection flow rate, and steam generator conditions, have been shown to affect the plant depressurization. The PIDS performance has also been verified against the following reference severe accident scenarios: (a) complete station blackout event, and (b) a small-break loss-of-coolant accident and concomitant station blackout event. Preliminary experimental activities to support the PIDS concept have already been performed. Additional experimental activities, including integrated system tests, have been planned to support system development and computer code validation.