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DOE consortium begins new initiative aimed at growing fuel cycle
The U.S Department of Energy’s Office of Nuclear Energy, through its Defense Production Act (DPA) Nuclear Fuel Cycle Consortium, has begun a new initiative aimed at securing the nation’s nuclear fuel supply chain.
M. D. Kennedy, J. Woodcock, R. F. Wright, J. A. Gresham
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 14-20
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35195
Articles are hosted by Taylor and Francis Online.
The Heavy Water Reactor Facility is equipped with a passive cooling system to provide long-term decay heat removal during postulated beyond-design-basis accidents. The passive containment cooling system (PCCS) consists of an annular space between the steel containment vessel and the concrete shield building and optimized inlet and chimney designs. The design, analysis, and regulatory acceptance of a plant with PCCS requires an understanding of the external convective and radiative heat transfer phenomena, as well as the internal distributions of noncondensable gases. The internal distribution of noncondensable gases has a strong effect on the resistance to condensation heat transfer and therefore affects the wall temperature distribution applied to the external channel. To evaluate these phenomena, a test facility having a scale of approximately one to ten, known as the large-scale test, was constructed, and several series of tests were performed. Test results have been used to validate the Westinghouse-GOTHIC (WGOTHIC) computer code. A comparison of WGOTHIC predictions and test results has been completed. This paper shows that mixed-convection models applied to the interior and exterior surfaces as well as a heat and mass transfer analogy for internal condensation provides good comparison to test results. An axial distribution of noncondensables within the test vessel is also predicted.