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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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
Direct waste transfer process quickens at Savannah River Site
The Department of Energy Office of Environmental Management’s liquid waste contractor at the Savannah River Site this month marked the first direct transfer of decontaminated waste from the Salt Waste Processing Facility (SWPF) to the Saltstone Production Facility (SPF). This is a new step in optimizing waste processing, according to the DOE.
Hirokazu Ohta, Takanari Ogata, Toru Obara
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 198-207
Regular Technical Paper | Fission Reactors | doi.org/10.13182/NT13-105
Articles are hosted by Taylor and Francis Online.
Innovative fuel design measures to attain a much higher burnup than that obtained using the conventional concept were investigated for a fast reactor (FR) metal fuel. Considering the typical mechanism of metal fuel degradation, three innovative design measures were proposed: (a) a decrease in plenum pressure by adopting the fission gas vent design, (b) prevention of fuel-cladding chemical interaction by lining the cladding inner wall, and (c) mitigation of fuel-cladding mechanical interaction by reducing the fuel smear density. The effects of these design measures on increasing the burnup were analyzed with ALFUS, an irradiation behavior analysis code for FR metal fuels. The ALFUS analysis revealed that a very high burnup of >40 at. % can be attained under the conventional design criteria for securing fuel integrity by applying these innovative measures. Neutronic analysis of a metal fuel core employing these design measures indicated that a high burnup of >40 at. % at the assembly peak can be attained while suppressing the burnup reactivity swing to almost the same level as that of conventional cores with normal burnup through the use of a minor actinide–containing fuel.