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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
April 2025
Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
S. Goluoglu, H. L. Dodds
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 142-153
Technical Note | Fission Reactor | doi.org/10.13182/NT95-A15859
Articles are hosted by Taylor and Francis Online.
An improved core physics model of the High Flux Isotope Reactor (HFIR) has been developed and evaluated by comparing calculational results with experimental results and also with calculational results obtained with earlier models. Eleven-group and 4-group cross-section libraries that are problem specific, collapsed, and weighted for the HFIR are generated from the 39-group Advanced Neutron Source Reactor cross-section library (ANSL-V general-purpose neutron library), which is based on ENDF/B-V. A diffusion theory-based procedure to analyze the static neutronics of the reactor is developed. Precise cross sections that take fuel loading variations (not considered in previous work) into account are also generated and implemented into an improved R-Z geometry model of the reactor. Point-by-point power densities are calculated using a detailed mesh structure. The results show that the improved model and procedure developed in this work give good agreement with experiments at interior locations with significant deviations at the outer boundary of the reactor core, which is near the control blades. More importantly, the improved model and procedure provide better overall agreement with experimental results than earlier models.