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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Nuclear Science and Engineering
Fusion Science and Technology
The blossoming of cooperation between the U.S. and Canada
The United States and Canadian nuclear industries used to be an example of how two independent teams of engineers facing an identical problem—making electricity from uranium—could come up with completely different answers. In the 1950s, Canada began designing a reactor with tubes, heavy water, and natural uranium, while in the U.S. it was big pots of light water and enriched uranium.
But 80 years later, there is a remarkable convergence. The North American push for a new generation of nuclear reactors, mostly small modular reactors (SMRs), is becoming binational, with U.S. and Canadian companies seeking markets and regulatory certification on both sides of the border and in many cases sourcing key components in the other country.
Chao Tian, Lifeng Sun, Chao Fang
Nuclear Science and Engineering | Volume 175 | Number 2 | October 2013 | Pages 204-211
Technical Paper | doi.org/10.13182/NSE12-51
Articles are hosted by Taylor and Francis Online.
In this paper, we discuss our study of the fission product diffusion process in TRISO fuel particles used in pebble bed high-temperature reactors (HTRs). Different from the previous numerical solution, the analytical solution of this diffusion process by variables separation was derived. It was also accessible to obtain the analytical expressions of the fission product concentration distribution C(t), the corresponding release fractions F(t), and the ratio of release and productive amounts R(t)/B(t) of fission products. Furthermore, to reduce the rounding errors, parameters mentioned in the diffusion equations were nondimensionalized, which made the result fairly reliable and credible. Since the analytical solutions are exact, many unnecessary assumptions and approximations in Booth's model are avoided. On the basis of HTR-10 design benchmark, the C(t), F(t), and R(t)/B(t) of 137Cs and 134Cs in TRISO fuel particles were calculated and then compared with the finite element solutions. The results show that analytical solutions are effective and consistent with the physical picture.