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NRC approves TerraPower construction permit
Today, the Nuclear Regulatory Commission announced that it has approved TerraPower’s construction permit application for Kemmerer Unit 1, the company’s first deployment of Natrium, its flagship sodium fast reactor.
This approval is a significant milestone on three fronts. For TerraPower, it represents another step forward in demonstrating its technology. For the Department of Energy, it reflects progress (despite delays) for the Advanced Reactor Demonstration Program (ARDP). For the NRC, it is the first approval granted to a commercial reactor in nearly a decade—and the first approval of a commercial non–light water reactor in more than 40 years.
Hesham R. Nasif, Fukuzo Masuda, Hidetsugu Morota, Hitomasa Iida, Satoshi Sato, Chikara Konno
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 89-102
Technical Paper | Radiation Protection | doi.org/10.13182/NT12-A14521
Articles are hosted by Taylor and Francis Online.
GEOMIT is a computer-aided design (CAD)/MCNP conversion interface code. It was developed to automatically generate Monte Carlo geometrical data from CAD data due to the difference in the representation scheme. GEOMIT is capable of importing as well as exporting different CAD formats. GEOMIT has the capability to produce solid cells as well as void cells without using the complement operator. While loading the CAD shapes (solids), each shape is assigned a material number and density according to its color on the original CAD data. A shape fixing process has been applied to cure the errors in the CAD data. Vertex location correctness is evaluated first, and then a removal of free edges and removal of small faces processes. A binary space portioning tree technique is used to automatically split complicated solids into simpler cells to avoid excessively complicated cells to allow MCNP to run faster. MCNP surfaces are subjected to an automatic reduction before creating the model. CAD data of the ITER benchmark model have been converted successfully to MCNP geometrical input. MCNP input model validations have been carried out by checking lost particles and comparing volumes calculated by MCNP to those of the original CAD data. Different test cases have been evaluated for ITER, including blanket first wall heat loading calculations, surface fluxes, and volume fluxes at different divertor regions as well as toroidal field coil heating.