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Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
Sergei Zimin
Fusion Science and Technology | Volume 24 | Number 2 | September 1993 | Pages 168-179
Technical Paper | Shielding | doi.org/10.13182/FST93-A30223
Articles are hosted by Taylor and Francis Online.
An extensive analysis of the sensitivity of the fast neutron flux in the superconductor, the dose to the electrical insulator, and the number of displacements per atom in the copper stabilizer to variations of the neutron cross sections for the International Thermonuclear Experimental Reactor (ITER)/OTR inboard region (first wall/blanket/shield/vacuum vessel) was carried out. All of the nuclides with a significant concentration in the ITER/OTR inboard region were investigated, namely, iron, chromium, nickel, lead, oxygen, hydrogen, boron, copper, 6Li, and 7Li. The integrated total sensitivities of iron, lead, hydrogen, and oxygen were compared with the results for the OTR and Next European Torus (NET) sensitivity analyses. The integrated total sensitivity of both the fast neutron flux and the dose to variation of lead cross sections for the ITER/OTR was much higher than that for the OTR, namely, 3.5 and 1.2, respectively. The difference in the integrated total sensitivities of the inboard toroidal field coil responses to a one standard deviation variation of the iron, hydrogen, and oxygen neutron cross sections was <30%. The most important energy regions and the types of neutron cross sections for shield calculations were identified. The uncertainty of the neutron cross sections in the important energy regions needs to be decreased to <10% to decrease the uncertainty of the calculated neutron dose and fast flux behind the ITER/OTR inboard shield to <15 to 30%.