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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.
Rajgopal Vijaykumar, Mohsen Khatib-Rahbar
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 313-326
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A3034
Articles are hosted by Taylor and Francis Online.
The applicability of the empirical approach in the CONTAIN computer code for the simulation of induced flow and heat transfer in asymmetrically heated, vertical parallel-plate channels is investigated. The physical situation is related to containment cooling in the Westinghouse AP600 reactor. The countercurrent flow of air in the channel is induced by the thermal buoyancy force. In CONTAIN, the heat and mass transfer analogy (with Sherwood number calculated based on an empirical Nusselt number correlation for fully developed flows), including the film theory correction for high mass transfer, is used to calculate film evaporation. The buoyancy-induced flow is calculated through coupled solutions to lumped-parameter mass, energy, and momentum equations. The CONTAIN predictions are first compared with the Purdue results of a more detailed two-dimensional model under identical conditions in a simple parallel-plate channel. Then the CONTAIN predictions are compared with the results of the Purdue two-dimensional model and with data for two selected (forced and free convection) tests performed in the Westinghouse Large Scale Test (LST) Facility. Analyses show that the CONTAIN-calculated Sherwood numbers, the total heat fluxes, the steam mass fraction, and the bulk velocity in the channel are comparable to the two-dimensional Purdue investigations for the parallel-plate simulations and for the conditions of the Westinghouse LST Facility.