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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
William P. Kelleher, J. Wiley Davidson, Gary R. Thayer, Donald J. Dudziak
Fusion Science and Technology | Volume 17 | Number 3 | May 1990 | Pages 466-475
Technical Note | Shielding | doi.org/10.13182/FST90-A29221
Articles are hosted by Taylor and Francis Online.
A radiation shielding analysis was performed on the Confinement Physics Research Facility (CPRF) under construction at Los Alamos National Laboratory. A reversed-field pinch device, the ZTH, was examined in an effort to obtain an estimate of the spatial distribution of the dose seen by both personnel and electronic components. In the Monte Carlo transport analysis, the MCNP code was used to estimate the neutron and gamma-ray doses and differential flux (in energy) spectra at ten locations within the CPRF. The complex geometry of the ZTH dictated that the problem be solved in a two-step process: First, a cylindrical surface source enclosing the ZTH was computed, and then this source was used as the radiation source for the CPRF building calculations. Using a source strength of 1015 neutrons, identical calculations were performed for both deuterium-deuterium and deuterium-tritium fusion plasmas.