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
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
EnergySolutions to help explore advanced reactor development in Utah
Utah-based waste management company EnergySolutions announced that it has signed a memorandum of understating with the Intermountain Power Agency and the state of Utah to explore the development of advanced nuclear power generation at the Intermountain Power Project (IPP) site near Delta, Utah.
Vedant K. Mehta, Michael W. D. Cooper, Robert B. Wilkerson, Dan Kotlyar, Dasari V. Rao, Sven C. Vogel
Nuclear Science and Engineering | Volume 195 | Number 6 | June 2021 | Pages 563-577
Technical Paper | doi.org/10.1080/00295639.2020.1851632
Articles are hosted by Taylor and Francis Online.
Yttrium hydride is being considered as a moderator material for microreactor concepts because of its excellent hydrogen retainment capacity at high temperatures. These types of reactors, operating at thermal to epithermal neutron energies, require accurate thermal scattering laws (TSLs) for yttrium hydride to predict and optimize moderator performance. Currently, TSL evaluations exist only for stoichiometric YH2. To perform high-certainty neutronics calculations and to improve the criticality safety of yttrium hydride–moderated reactors, evaluations of substoichiometric yttrium dihydride TSLs are necessary. Ab initio density functional theory (DFT) was used to generate the phonon density of states for yttrium and hydrogen under harmonic approximation in yttrium hydride (). To obtain substoichiometric yttrium dihydride, vacancies in the YH2 crystal were created using special quasi-random structures (SQS). Using NJOY2016, the TSLs for yttrium hydride were constructed from the DFT results as a function of stoichiometry and temperature. Our TSLs for the stoichiometric composition YH2 were in excellent agreement with the ENDF/B-VIII.0 evaluations. As such, this study extends the yttrium hydride TSLs for compositions between YH1.31 to YH1.91 with the interval of H/Y ≈ 0.1 for use in the MCNP code. The substoichiometric yttrium hydride scattering cross sections deviated by as much as 30% (elastic) and 60% (inelastic) when compared to the YH2 TSLs, underlining the necessity to have the TSLs presented here available, e.g., for safety-related reactor calculations. For the validation of the underlying DFT results of our model, quasi-harmonic approximation was used to compute the thermal lattice strain and constant pressure heat capacity for YH2. Neutron diffraction experiments were also carried out to characterize thermophysical properties that were adopted for stoichiometric and substoichiometric model validation. Additional properties such as heat capacity cv, and thermal displacement parameters were also computed for yttrium hydride () and compared to experimental results. Neutron diffraction validation of the YH2-x material properties and ENDF/B-VIII.0 verification of YH2 TSLs provide a very strong basis on the accuracy of the extended yttrium hydride TSL evaluations at thermal energies.