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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
QSA Global, Niowave to collaborate on Ac-225 production using Ra-226
QSA Global, a provider of radioisotope products, and Niowave, a Michigan-based producer of medical radioisotopes, announced that the companies will codevelop a scalable radium purification process using Niowave’s radium-226 processing technology to meet the demand for actinium-225, an alpha-emitter used in the treatment of cancer. According to the companies, the strategic partnership marks a significant advancement in the field of radiopharmaceutical technology, enhancing the supply chain for critical radioisotopes, including Ac-225.
Niowave uses a closed-loop cycle to produce high-purity Ac-225 and other alpha emitters from Ra-226 using a superconducting electron linear accelerator. According to the company’s website, the electron beam impinges on a photon converter to irradiate the Ra-226, inducing a photon-neutron reaction to Ra-225, which decays to Ac-225.
M. Yousif Alhaj, Alya Badawi, Hanaa H. Abou-Gabal, Nader M. A. Mohamed
Nuclear Technology | Volume 194 | Number 3 | June 2016 | Pages 314-323
Technical Paper | doi.org/10.13182/NT15-78
Articles are hosted by Taylor and Francis Online.
This research focuses on the utilization of thorium-plutonium fuel in pressurized water reactors (PWRs). The reference PWR selected in this research was the Westinghouse AP1000. Thorium-plutonium mixed-oxide (MOX) fuel assemblies partially replaced the uranium oxide fuel assemblies to reduce uranium demand. The cases studied contained 36, 48, 60, 72, and 84 thorium-plutonium MOX fuel assemblies, with the rest of the 193 fuel assemblies loaded with UO2 fuel. The core cycle length, the amount of plutonium incinerated, the amount of generated 233U in the spent fuel, and the conversion ratios were determined using MCNP6. For the different cases, safety parameters such as the power peaking factor and delayed neutron fraction (βeff) were evaluated. The study showed that using thorium-plutonium MOX can achieve good peaking power factors with delayed neutron fractions within the safety limits. Also a conversion factor of about 10% was achieved.