DART Analysis of Irradiation Behavior of U-Mo/Al Dispersion Fuels

B Ye,J R Rest,Yeon Soo Kim, G L Hofman, B J Dionne

NUCLEAR TECHNOLOGY(2015)

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摘要
DART (Dispersion Analysis Research Tool) is a computational code developed for integrated simulation of the irradiation behavior of aluminum dispersion fuels used in research reactors. The DART computational code uses a mechanistic fission gas behavior model and a set of up-to-date empirical correlations to simulate the fuel morphology change as a function of burnup. Integrating a thermal calculation subroutine enables fuel material properties to be updated at each time step. This paper describes the primary physical models that form the basis of the DART computational code. A baseline validation was performed through the modeling of several U-Mo/Al mini-plate tests (RERTR-6, 7, and 9) in the Advanced Test Reactor (ATR). A demonstration problem is also presented through the calculation of fuel plate swelling and constituent volume fractions in full-sized plates from the AFIP-1 test in ATR.
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关键词
irradiation behavior modeling,U-Mo/Al dispersion fuel,irradiation-induced swelling
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