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RIC panel discusses pathway to fusion commercialization
Fusion leaders at the Nuclear Regulatory Commission’s annual Regulatory Information Conference discussed the path forward for regulating the burgeoning fusion industry. The speakers discussed government and private industry initiatives in the United States and United Kingdom, with a focus on efforts shaping the near-term deployment of commercial fusion machines.
A recurring theme was the need to explain the difference between fission and fusion. Representatives from the Department of Energy and Type One Energy highlighted this as an important distinction for regulators, as it will allow fusion to undergo its own independent maturation process for developing standards and regulations in the same way that fission has. Lea Perlas, Fusion Program director at the Virginia Department of Health, said that confusion between fission and fusion has been a common cause for misplaced concerns among community members surrounding Commonwealth Fusion Systems’ proposed fusion plant site near Richmond, Va.
R. T. Santoro, J. M. Barnes
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 367-372
Neutronics and Shielding | doi.org/10.13182/FST83-A22892
Articles are hosted by Taylor and Francis Online.
Neutron and gamma-ray energy spectra resulting from the interactions of ∼14 MeV neutrons in laminated slabs of stainless steel type-304 and borated polyethylene have been calculated using the Monte Carlo code MCNP. The calculated spectra are compared with measured data as a function of slab thickness and material composition and as a function of detector location behind the slabs. Comparisons of the differential energy spectra are made for neutrons with energies above 850 keV and for gamma rays with energies above 750 keV. The measured neutron spectra and those calculated using Monte Carlo methods agree within 5% to 50% depending on the slab thickness and composition and neutron energy. The agreement between the measured and calculated gamma-ray energy spectra are also within this range. The MCNP data are also in favorable agreement with attenuated data calculated previously by discrete ordinates transport methods and the Monte Carlo code SAMCE.
