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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Yukio Ishiguro, Keisuke Okumura
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 331-343
Technical Paper | Probabilistic Safety Assessment and Risk Management / Fission Reactor | doi.org/10.13182/NT89-A34217
Articles are hosted by Taylor and Francis Online.
A new concept is proposed for a high conversion light water reactor (HCL WR) that achieves both high conversion and high burnup while maintaining a negative void reactivity coefficient. This HCLWR has a flat “pancake” core with thick axial blankets. By using the flat core, a potential problem of HCLWRs, the positive void reactivity coefficient, can be reduced by neutron leakage, and a fuel assembly of very tight lattice pitch can be used. The leakage neutrons are utilized in the axial blankets to enhance the conversion ratio. With the axial blankets, the core shows a small value for the axial power peaking factor, and the plutonium enrichment can be largely reduced by the neutron reflection, including the fast fission due to 238U, compared with the bare core. Moreover, upgraded burnup characteristics can be obtained by the accumulation of fissile plutonium in the blankets. The flat core with the blankets can be applied to a small- or intermediate-scale light water reactor. The analysis combines a cell burnup calculation and a one-dimensional burnup calculation based on the diffusion method. The evaluation method of the void coefficient is validated for the flat core with axial blankets under practical, controlled conditions. Moreover, the accuracy of the present method is validated for the transport effect on the major physics parameters of interest by using the one-dimensional transport code ANISN and the Monte Carlo code VIM.