Recent progress in the fusion neutrons, 3; Nuclear analysis by automatic conversion of CAD data

Sato, Satoshi; Kondo, Keitaro

In the nuclear analysis of ITER, fusion DEMO reactor and IFMIF, etc., radiation transport calculations are conducted by using MCNP geometry data automatically created from 3-dimensional CAD data with CAD/MCNP conversion codes. In this review paper, we introduce the present status of the development on the CAD/MCNP conversion codes and examples of application. Also, we introduce how to visualize calculation results by MCNP.

Language	:	Japanese
Journal	:	Purazuma, Kaku Yugo Gakkai-Shi
Volume	:	92
Number	:	4
Pages	:	p.266 - 268
Publication Year/Month	:	2016/04
Meeting title	:
Held date	:
Location (city)	:
Location (country)	:
Patent information	:
PDF	:
Paper URL	:	http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2016_04/jspf2016_04-266.pdf
DOI for research data	:
Keywords	:	no keyword
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:

Accesses	:	- Accesses
Web of Science® Times Cited Count	:	Times Cited Count： If you would like to get the latest times cited, please access the Web of Science®. http://www.webofknowledge.com/wos
InCites™	:
Altmetrics	:

Registration No. : AA20150607
JAEA Abstracts No. : 44001142
Paper Submission No. : 17839

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.