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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
S. K. Bhattacharyya, J. A. Morman, R. G. Bucher, D. M. Smith, W. R. Robinson, E. F. Bennett
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 197-218
Technical Paper | Reactor | doi.org/10.13182/NT80-A32524
Articles are hosted by Taylor and Francis Online.
A possible accident scenario in a gas-cooled fast reactor (GCFR) is the leakage of secondary steam into the core. A full-scale experimental study of the physics effects of such an accidental condition has been performed on the zero power reactor (ZPR)-9 critical facility at Argonne National Laboratory. Polyethylene foam strips were used to simulate steam for these measurements. The basic neutronics parameters, namely, neutron spectrum, spectral indexes, reactivity worths, 238U Doppler effect, and B4C control rod worths, were measured in the steam-flooded GCFR critical assembly and also in the corresponding dry, reference GCFR assembly. The results of these measurements clearly show the spectrum softening effects on steam entry. For the analysis of the experiments, ENDF/B-IV-based data were used with two-dimensional diffusion theory methods. It was concluded that the values of the primary safety parameters increased upon steam entry relative to the reference dry case. Such an increase would mitigate the effects of accidental steam entry in a GCFR.