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When a nuclear plant closes
Theresa Knickerbocker, the mayor of the village of Buchanan, N.Y., where the Indian Point nuclear power plant is located, is not happy. What has gotten Ms. Knickerbocker’s ire up is the fact that Indian Point’s Unit 2 was closed on April 30, and Unit 3 is scheduled to close in 2021. The village, population 2,300, is about 1.3 square miles total, with the Indian Point site comprising 240 acres along the Hudson River, 30 miles upstream of Manhattan. Unit 2 was a 1,028-MWe pressurized water reactor; Unit 3 is a 1,041-MWe PWR.
The nuclear plant provides the revenue for half of Buchanan’s annual $6-million budget, Knickerbocker told Nuclear News. That’s $3 million in tax revenues each year that eventually will go away. How will that revenue be replaced? Where will the replacement power come from?
Marat Margulis, Erez Gilad
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 377-395
Technical Paper | dx.doi.org/10.13182/NT16-23
Articles are hosted by Taylor and Francis Online.
The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics (TH)] for safety analyses of research reactors (RRs) has gained considerable momentum during the past decade. Application of these codes is largely facilitated by the high level of technological maturity and expertise that these codes allow as a safety technology in nuclear power plants, and it is largely driven by International Atomic Energy Agency activities. The present study belongs in this framework and presents the development and application of the coupled NK and TH code THERMO-T to the analysis of protected reactivity insertion accidents and loss-of-flow accidents in a typical RR with standard Materials Testing Reactor plate-type fuel elements. The coupling is realized by considering the neutronic reactivity feedbacks of the fuel and coolant temperatures and a heat generation model for the reactor power. The neutron flux in the reactor core is solved by applying point reactor kinetic equations and employing radial and axial power distributions calculated from a three-dimensional full-core model by the continuous-energy Monte Carlo reactor physics code Serpent. The evolution of temporal and spatial distributions of the fuel, cladding, and coolant temperatures is calculated for all fuel channels by using a finite volume time implicit numerical scheme for solving a three-conservation equation model. In this study, additional features, such as critical heat flux ratio prediction and decay heat model, are implemented for both highly enriched uranium and low-enriched uranium cores, and a comprehensive comparison of THERMO-T results is performed against other codes.