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
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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Latest News
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
K. S. Smith
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 451-458
Technical Paper | doi.org/10.13182/NSE82-A20286
Articles are hosted by Taylor and Francis Online.
An investigation of first-order perturbation (FOP) methods for computing sample worths has been performed. It is demonstrated that conventional cell homogenization methods introduce errors into FOP reactivity calculations because the intracell structure of adjoint fluxes is neglected. These errors are such that the conventional FOP reactivity expression is not accurate to first order, even in the limit of infinitesimal perturbations. A method for avoiding such approximations is introduced and applied to the calculation of small sample worths in plate-type fast reactor critical assemblies. It is demonstrated that errors introduced by real flux weighting of cross sections are such that homogenized FOP reactivity calculations overestimate fissile material worths in several critical assemblies by 5 to 10%. It is shown that these errors arise because of the heterogeneous nature of plate-type critical assemblies, and when appropriate reactivity calculations (which account for spatial heterogeneity of adjoint fluxes) are performed, a significant fraction of the long-standing central worth discrepancy is eliminated.