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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Latest News
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
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.