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.
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Utility Working Conference and Vendor Technology Expo (UWC 2022)
August 7–10, 2022
Marco Island, FL|JW Marriott Marco Island
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
Latest Journal Issues
Nuclear Science and Engineering
Fusion Science and Technology
Arkansas PSC rejects $142 million offer from Entergy in Grand Gulf dispute
While the Mississippi Public Service Commission earlier this year accepted a $300 million offer from Entergy Corporation to settle its portion of a multistate dispute with the utility over Grand Gulf nuclear plant customer rate impacts, the Arkansas Public Service Commission last week turned down its own $142 million offer, terming it “a low-ball amount.”
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 | dx.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.