Refine your search:     
Report No.
 - 
Search Results: Records 1-2 displayed on this page of 2
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Development of CAD-to-MCNP model conversion system and its application to ITER

Sato, Satoshi; Iida, Hiromasa; Ochiai, Kentaro; Konno, Chikara; Nishitani, Takeo; Morota, Hidetsugu*; Nashif, H.*; Yamada, Masao*; Masuda, Fukuzo*; Tamamizu, Shigeyuki*; et al.

Nuclear Technology, 168(3), p.843 - 847, 2009/12

 Times Cited Count:7 Percentile:45.39(Nuclear Science & Technology)

It takes huge or unrealistic amounts of time to prepare accurate calculation inputs in shielding design for very large and complicated structure such as fusion reactors. For that reason, we have developed an automatic conversion system from three dimensional CAD drawing data into input data of the calculation geometry for a three dimensional Monte Carlo radiation transport calculation code MCNP, and applied it to an ITER benchmark model. This system consists of a void creation program (CrtVoid) for CAD drawing data and a conversion program (GEOMIT) from CAD drawing data to MCNP input data. CrtVoid creates void region data by subtracting solid region data from the whole region by Boolean operation. The void region data is very large and complicated geometry. The program divides the overall region to many small cubes, and the void region data can be created in each cube. GEOMIT generates surface data for MCNP data based on the CAD data with voids. These surface data are connected, and cell data for MCNP input data are generated. In generating cell data, additional surfaces are automatically created in the program, and undefined space and duplicate cells are removed. We applied this system to the ITER benchmark model. We successfully created void region data, and MCNP input data. We calculated neutron flux and nuclear heating. The calculation results agreed well with those with MCNP inputs generated from the same CAD data with other methods.

Oral presentation

Development of the CAD/MCNP automatic conversion code, GEOMIT, 1; CAD pre-processing tool, Development of the CrtVoid

Morota, Hidetsugu*; Yamada, Masao*; Nasif, H.*; Masuda, Fukuzo*; Iida, Hiromasa; Sato, Satoshi; Nishitani, Takeo; Tamamizu, Shigeyuki*; Karaki, Junichi*

no journal, , 

Development of CAD preprocessing tool "CrtVoid" is reported. The code extracts surface element information and re-arrange them as input data for CAD/MCNP automatic conversion cord "GEOMIT". Reports includes detail of the development and test results of confirmation of its functions.

2 (Records 1-2 displayed on this page)
  • 1