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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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Latest News
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?
Andreas Pautz, Adolf Birkhofer
Nuclear Science and Engineering | Volume 145 | Number 3 | November 2003 | Pages 299-319
Technical Paper | doi.org/10.13182/NSE03-A2385
Articles are hosted by Taylor and Francis Online.
A new neutron transport code for time-dependent analyses of nuclear systems has been developed. The code DORT-TD is based on the well-known Discrete Ordinates code DORT, which solves the steady-state neutron transport equation in two dimensions for an arbitrary number of energy groups and standard regular geometries. For the implementation of time-dependence, a fully implicit, unconditionally stable time integration scheme was employed to minimize errors due to temporal discretization. This requires several modifications to the transport equation and the extensive use of sophisticated acceleration mechanisms. The convergence criteria for fluxes and fission densities had to be strongly tightened to ensure the reliability of results. We also allowed for cross sections varying with time to couple neutronics and thermal hydraulics calculations. The neutronics code was finally applied to a research reactor to show its capabilities for both slow and fast transients.