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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Nolan E. Hertel, R. H. Johnsons, Bernard W. Wehring, John J. Dorning
Fusion Science and Technology | Volume 9 | Number 2 | March 1986 | Pages 345-361
Technical Paper | Blanket Engineering | doi.org/10.13182/FST86-A24721
Articles are hosted by Taylor and Francis Online.
Integral experiments have been performed using a homogeneous iron spherical shell to test neutron cross-section data. Neutron leakage spectra from the shell were measured using 252Cf-fission and (deuterium-tritium) D-T-fusion neutron sources and an NE-213 spectrometry system. An associated particle detector was used to monitor the absolute D-T neutron source strength as well as any accompanying deuterium-deuterium neutron contamination. The leakage spectra were calculated using the continuous-energy Monte Carlo code VIM and the discrete ordinates Sn code ANISN employing ENDF/B-IV. For neutron energies between 1 and 5 MeV, the calculations underpredicted the leakage spectrum by factors of 1.4 to 2 for the californium neutron source and of 2 to 3 for the D-T neutron source. The large discrepancies are attributed to inadequate representation of cross-section resonance structure (namely, minima); inadequate representation of the angular and secondary energy distributions for continuum inelastic scattering and (n,2n) reactions also contribute to these discrepancies.