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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
BWXT announces nuclear manufacturing plant expansion
BWX Technologies announced today plans to expand and add advanced manufacturing equipment to its manufacturing plant in Cambridge, Ontario, Canada.
A $36.3 million USD ($50M CAD) expansion will increase the plant’s size by 25 percent—to 280,000 square feet—and another $21.7 million USD ($30M CAD) will be spent on new equipment to increase and accelerate its output of large nuclear components. The investment will increase capacity and create more than 200 long-term jobs for skilled workers, engineers, and support staff, according to the company.
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.