ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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!
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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Sushil K. Bhatnagar
Nuclear Technology | Volume 120 | Number 3 | December 1997 | Pages 224-230
Technical Paper | Radiation Protection | doi.org/10.13182/NT97-A35413
Articles are hosted by Taylor and Francis Online.
Penetration shielding design for primary and secondary shield walls in a nuclear power plant proceeds in several iterative cycles. These cycles are needed to refine the conceptual designs for numerous, often conflicting, requirements. These requirements include the following: worker occupancy, in-service inspections, ventilation, pressure and temperature transient controls, equipment qualification, etc. Because the determination of neutron and gamma radiation levels in the containment building of a nuclear power plant requires a three-dimensional calculation, which is both very complicated and expensive, simplified but conservative procedures are needed to provide that input for various other analyses. Once an optimized design is developed, it can be confirmed by either a full three-dimensional analysis or acceptable combinations of discrete ordinates and Monte Carlo methods. The isotropic analog method and its enhancement are presented to provide such an alternative. Included are the methodology, its justification, confirmation, limitations, and suggestions for additional development. This method has already been used for the shielding design of two nuclear power plants and shown to be conservative by a factor of between 2 and 5.