ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Framatome, KHNP to investigate producing Lu-177 in South Korea
Framatome and Korea Hydro & Nuclear Power (KHNP) announced the signing of a memorandum of understanding to explore the possibility of producing the medical isotope Lutetium-177 at KHNP’s Wolsong nuclear power plant in South Korea. The companies also will investigate the feasibility of using the plant to support Korean production of medical radioisotopes in the future.
S. Bznuni, N. Baghdasaryan, A. Amirjanyan, G. Nazaryan, P. Kohut, J. Ramsey
Nuclear Science and Engineering | Volume 186 | Number 1 | April 2017 | Pages 98-102
Technical Paper | doi.org/10.1080/00295639.2016.1273012
Articles are hosted by Taylor and Francis Online.
Bounding axial profiles for WWER-440 spent fuel pool burnup credit analysis were developed. A database of axial burnup profiles of WWER-440 type fuel assemblies and fuel followers was developed and studied to determine the burnup axial profile that results in the maximal neutron multiplication factor. Bounding axial profiles were determined based on the statistical analysis of keff of the analyzed profiles from the statistical outliers of the axial profile database. The influence of the identified bounding profiles on keff is quantified for the WWER-440 spent fuel pool. Criticality calculations using the database axial profiles were conducted by the MCNP6.1 program. The isotopic compositions of the spent WWER-440 fuels were quantified by the ORIGEN program of the SCALE 6.1 package.
