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

Presentation/Publication Type

Initialising ...


Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...


Initialising ...


Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Development of CAD-MCNP interface program GEOMIT and its applicability for ITER neutronics design calculations

Nasif, H. R.*; Masuda, Fukuzo*; Morota, Hidetsugu*; Iida, Hiromasa*; Sato, Satoshi; Konno, Chikara

Nuclear Technology, 180(1), p.89 - 102, 2012/10

 Times Cited Count:3 Percentile:27.39(Nuclear Science & Technology)

GEOMIT is the CAD/MCNP conversion interface code. It is developed to automatically generate Monte Carlo geometrical data from CAD data due to the difference in the representation scheme. GEOMIT is capable of importing different CAD format as well as exporting different CAD format. GEOMIT has a capability to produce solid cells as well as void cells without using complement operator. While loading the CAD shapes (Solids), each shape is assigning material number and density according to its color on the original CAD data. Shape fixing process is been applied to cure the errors in the CAD data. Vertices location correctness is evaluated first, then a removal of free edges and removal of small faces processes. Binary Space Portioning (BSP) tree technique is used to automatically split complicated solids into simpler cells to avoid excessive complicated cells for MCNP to run faster. MCNP surfaces are subjected to an automatic reduction before creating the model. CAD data of International Thermonuclear Experimental Reactor (ITER) benchmark model has 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 the ITER, include Blanket first wall heat loading calculations, surface fluxes and volume fluxes at different divertor regions as well as TF coils heating.

Oral presentation

Current status of JASMIN: Japanese-American study of muon interactions and neutron detection

Nakashima, Hiroshi; Mokhov, N.*; Iwamoto, Yosuke; Matsuda, Norihiro; Kasugai, Yoshimi; Sakamoto, Yukio; Leveling, A.*; Boehnlein, D.*; Vaziri, K.*; Sanami, Toshiya*; et al.

no journal, , 

Several multi-purpose high-energy radiation transport codes are used in many research fields such as high-energy physics as well as accelerator facility shielding designs. The codes are benchmarked against experimental data on a regular basis. To promote this to a higher level and to a hardly explored field of neutron radiation induced by energetic muons, a JASMIN collaboration (Japanese-American Study of Muon Interaction and Neutron detection), has been created with several Laboratories and Universities of Japan and U.S.A. The collaboration has performed a series of experiments at the Pbar target station and NuMI facility at Fermi National Accelerator Laboratory, using irradiation of targets with 120 GeV protons for antiproton and neutrino production. This paper reviews recent activities and results.

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