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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
Walter J. Eich, Mark L. Williams,Chun-Mou Peng
Nuclear Science and Engineering | Volume 90 | Number 2 | June 1985 | Pages 127-139
Technical Paper | doi.org/10.13182/NSE85-A17671
Articles are hosted by Taylor and Francis Online.
Analysis of critical experiments for cross-section evaluation has been conducted on the basis of one-dimensional four-group diffusion theory calculations that explicitly model the homogenized core and reflector in the radial plane. Such analyses require a reflector representation that models the leakage process as accurately as feasible. The development and testing of few-group ENDF/B-V based light water reflector constants for use in diffusion theory derived to reproduce leakage and other reaction rates from reference multifast group transport calculations are described. This work has been extended to parameterize similar higher order transport calculations with two- or four-group constants valid for application to typical pressurized water reactor baffle/reflector configurations as represented in coarse mesh diffusion (PDQ) representations.