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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
O. F. Smidts, J. Devooght
Nuclear Science and Engineering | Volume 129 | Number 3 | July 1998 | Pages 224-245
Technical Paper | doi.org/10.13182/NSE98-A1978
Articles are hosted by Taylor and Francis Online.
A biased Monte Carlo methodology is presented for solving the transport of radionuclide chains through a porous medium in the context of the risk assessment of radioactive waste repositories. It is based on the construction of random walks from an integral equation. This leads to a biased Monte Carlo simulation because it uses the solution of an adjoint reference problem to improve the efficiency of the calculations. The transport of a radionuclide chain is modeled by introducing the notion of a radionuclide "state." The consequence is that only one integral equation has to be considered for the simulation in a continuous - discrete space (r,t;i), where r is the radionuclide position vector, t is time, and i is the radionuclide state. Transport in a random velocity field is also considered by using double randomization techniques.The methodology is illustrated by numerical results on test problems; the score of the simulations being the quantity of radionuclides transferred, during the mission time, to the upper surface of the geological domain. Validations of the simulations are first realized by comparison with analytical solutions, and the influence of biasing techniques is put in evidence. Finally, simulations conducted simultaneously with the generation of a large number of random velocity fields illustrate the feasibility of the method for the transport of radionuclides in a stochastic medium.