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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Sylvie Aniel-Buchheit, André Puill, Richard Sanchez, Mireille Coste
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 245-256
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A3029
Articles are hosted by Taylor and Francis Online.
The feasibility of 100% mixed-oxide (MOX) fuel recycling in a standard pressurized water reactor (PWR) is explored. The plutonium neutronic specificity is analyzed and compared with uranium. The objective is to identify the generic aspects that could lead to current PWR design modifications. The plutonium isotopic composition was taken as a parameter.Accidents dealing with a change of the moderator density are of particular interest (especially considering that control worth is significantly reduced with MOX fuel). Study of core global draining leads to the following conclusion: Only very poor quality plutonium fuel (low fissile content) cannot be used in a 900-MW(electric) PWR because of a positive global draining reactivity effect. Study of the cooling accident (increase of moderator density) proves that the spurious opening of a secondary side valve is the most penalizing scenario in the case of MOX fuel utilization. The core reactivity was controlled in this study by 57 control rod clusters made of B4C rods having a 90% 10B content and a hafnium clad. The hypothetical return to criticality depends on plutonium isotopic composition. But the core is kept subcritical for all isotopic compositions provided an increase of the soluble boron 10B content up to a value of 40%. No major obstacle to the 100% MOX 900-MW(electric) PWR feasibility was found.