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
Reactor Physics
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
B. D. Murphy, R. T. Primm III
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 258-269
Technical Paper | doi.org/10.13182/NSE02-A2306
Articles are hosted by Taylor and Francis Online.
This work examines the capabilities of simulation codes to predict the concentration of nuclides in spent reactor fuel, in particular mixed-oxide (MOX) fuel, via comparisons with destructive radiochemical analyses performed on irradiated samples. We report on three MOX samples irradiated in a pressurized water reactor (PWR) and two UO2 samples irradiated in a different PWR. Actinide and fission-product concentrations were measured and were compared with concentration values obtained from simulation studies. The actinides include isotopes of uranium, neptunium, plutonium, americium, and curium. The fission products include isotopes of cesium, neodymium, samarium, europium, and gadolinium as well as 90Sr, 95Mo, 99Tc, 101Ru, 106Ru, 103Rh, 109Ag, 125Sb, 129I, and 144Ce. For many of the actinides, the predictions are quite good when compared with the measured values; but concentrations of some tend to be overpredicted. The cesium and neodymium, and some samarium concentrations, are well predicted, but some of the other fission products show variable results. The sensitivity of some of the results to sample-burnup estimates is discussed.