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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Tien-Ko Wang, F. M. Clikeman, K. O. Ott
Nuclear Science and Engineering | Volume 93 | Number 3 | July 1986 | Pages 262-272
Technical Paper | doi.org/10.13182/NSE86-A17755
Articles are hosted by Taylor and Francis Online.
Experimental and computational studies of the gamma-ray energy deposition rate in the Fast Breeder Blanket Facility (FBBF) were performed with thermoluminescent dosimeters (TLDs). Various corrections including the TLD neutron sensitivities and the f factors (general cavity-ionization theory) were applied to the TLD measurements. Comparisons were made with results of three computer codes — 1DX, 2DB, and ANISN — and two nuclear libraries — LIB-IV and EPR. Both neutron and gamma-ray calculations were performed. The previously reported deviations between the gamma-ray energy deposition calculated-toexperiment (C/E) ratios for lead and for stainless steel were resolved. It is believed that the remaining C/E discrepancy comes primarily from the inaccuracies in the neutronics part of the calculations, because similar dropoffs are also reported in the FBBF reaction rate C/E comparisons. Detailed analysis of the deviation between transport (Sn) and diffusion calculations in the FBBF were performed. It was found that the deviation is built up in the blanket region and is largely independent of the curvature of the “independent” source region. Comparisons between Sn and diffusion calculations (on a one-dimensional basis) for neutron fluxes and reaction rates indicated that the use of transport calculations should reduce the discrepancies of C/E comparisons.