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DOE on track to deliver high-burnup SNF to Idaho by 2027
The Department of Energy said it anticipated delivering a research cask of high-burnup spent nuclear fuel from Dominion Energy’s North Anna nuclear power plant in Virginia to Idaho National Laboratory by fall 2027. The planned shipment is part of the High Burnup Dry Storage Research Project being conducted by the DOE with the Electric Power Research Institute.
As preparations continue, the DOE said it is working closely with federal agencies as well as tribal and state governments along potential transportation routes to ensure safety, transparency, and readiness every step of the way.
Watch the DOE’s latest video outlining the project here.
Om Prakash Joneja, Vijay R. Nargundkar, Tejen Kumar Basu
Fusion Science and Technology | Volume 12 | Number 1 | July 1987 | Pages 114-118
Technical Paper | Blanket Engineering | doi.org/10.13182/FST87-A25055
Articles are hosted by Taylor and Francis Online.
The experimentally measured value of 14-MeV neutron multiplication for 10-cm-thick lead in rectangular geometry agrees within 1% of the corresponding calculated value using the MORSE-E code with the Los Alamos National Laboratory 30-group cross-section set CLAW-IV, in P3 scattering approximation. This result is in direct contrast with Takahashi's measurements with lead spheres of 3-, 6-, 9-, and 12-cm radii, where the measured multiplication values are found to be ˜15% higher than the corresponding transport calculations performed using the ANISN and NITRAN codes with the ENDF/B-IV library. However, Monte Carlo calculations using the MORSE-E code with the CLAW-IV library, as well as those of Cheng et al, using the MCNP code with the ENDF/B-V library, agree very well with Takahashi's measurements. Thus, the real difference of leakage neutron multiplication in lead is not between the measurements and the calculations, as reported by Takahashi, but between Takahashi's and other calculations. It is found that by using lead as a neutron multiplier in practical fusion blankets, a 5 to 10% higher neutron multiplication can be obtained than with beryllium for identical configurations of the multiplier.