Refine your search:     
Report No.
 - 
Search Results: Records 1-6 displayed on this page of 6
  • 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 the real-time plasma shape movie broadcasting system for JT-60SA

Sueoka, Michiharu; Sakamoto, Kensaku; Shigemori, Yuji*

Heisei-22-Nendo Kumamoto Daigaku Sogo Gijutsu Kenkyukai Hokokushu (CD-ROM), 6 Pages, 2011/03

no abstracts in English

JAEA Reports

DOSE-Analyzer; A Computer program with graphical user interface to analyze absorbed dose inside a body of mouse and human upon external neutron exposure

Satoh, Daiki; Takahashi, Fumiaki; Shigemori, Yuji*; Sakamoto, Kensaku

JAEA-Data/Code 2010-004, 28 Pages, 2010/06

JAEA-Data-Code-2010-004.pdf:1.58MB

DOSE-Analyzer is a computer program to retrieve the dose information from a database and generate a graph through a user-friendly graphical interface. The database is constructed for absorbed dose, fluence, and energy distribution inside a body of mouse and human exposed upon external neutrons, which is calculated by our developed Monte-Carlo simulation method using voxel-type phantom and particle transport code PHITS. The input configuration such as irradiation geometry, subject, and energy is set by GUI. The results are tabulated at particle types, i.e. electron, proton, deuteron, triton, and alpha particle, and target organs on a data sheet of Microsoft Office Excel. Simple analysis to compare the output values for two subjects is also performed on DOSE-Analyzer. This report is a user manual of DOSE-Analyzer.

JAEA Reports

Development of Radiation Dose Assessment System for Radiation Accident (RADARAC)

Takahashi, Fumiaki; Shigemori, Yuji*; Seki, Akiyuki

JAEA-Data/Code 2009-008, 127 Pages, 2009/07

JAEA-Data-Code-2009-008.pdf:10.5MB

A radiation transport calculation can derive dose distribution in a heavily exposed person for the medical treatment at the case of an accident. Since the accident cannot be prospected, many complicated procedures are needed to make the input file soon after the accident and to inform radiation dose based upon the output files with much information concerning the calculation. Thus, ($underline{Ra}$)diation ($underline{D}$)ose ($underline{A}$)ssessment system for ($underline{R}$)adiation ($underline{Ac}$)cident (RADARAC) was developed to derive effectively radiation dose by the MCNPX or the MCNP code. RADARAC consists of RADARAC_INPUT and RADARAC_DOSE. A user can interactively set up necessary resources to make input files with three programs in RADARAC_INPUT. The results of radiation doses are indicated with tables, graphs and figures depicting dose distribution by RADARAC_DOSE. It is confirmed that RADARAC can make input files with a few thousand lines and indicate more than 20,000 data dose within a few minutes.

Journal Articles

Dose assessment system for a heavily exposed person in radiation facility

Takahashi, Fumiaki; Shigemori, Yuji*; Seki, Akiyuki

Hozengaku, 8(1), p.56 - 61, 2009/04

Failure of safety management system can bring about a heavily exposed person in maintenance of a radiation facility, though such a case is very rare. A method using radiation transport code has advantages in an assessment of dose distribution inside a human body. Complicated procedures, however, are needed to prepare an input-file and to derive radiation dose based upon descriptions of an output-file in a numerical analysis using a radiation transport code. Thus, a system was developed to set up necessary information for an input file and to give radiation dose from an output file by a dialogue method using graphical user interfaces. Dose assessment can be effectively carried out for a radiological accident with this system.

Journal Articles

Accurate dose assessment system for an exposed person utilising radiation transport calculation codes in emergency response to a radiological accident

Takahashi, Fumiaki; Shigemori, Yuji*; Seki, Akiyuki

Radiation Protection Dosimetry, 133(1), p.35 - 43, 2009/01

 Times Cited Count:1 Percentile:10.23(Environmental Sciences)

A system has been developed to assess radiation dose distribution inside a body of exposed persons in a radiological accident by utilizing radiation transport calculation codes - MCNP and MCNPX. The system mainly consists of two parts, pre-processor and post-processor of the radiation transport calculation. Programs for the pre-processor are used to set up a "problem-dependent" input file, which defines the accident condition and dosimetric quantities to be estimated. The developed program for the post-processor part can effectively indicate dose information based upon the output file of the code. All of the programs in the dosimetry system can be executed with a generally used personal computer and accurately give the dose profile to an exposed person in a radiological accident without complicated procedures. An experiment using a physical phantom was carried out to verify the availability of the dosimetry system with the developed programs in a $$gamma$$-ray irradiation field. The dosimetry system with the developed programs can appropriately assess dose distribution inside or on the human body, if the user exactly define the source and human models and their geometric relationship.

Oral presentation

Development of precise dose analysis system in a radiation accident, 2

Takahashi, Fumiaki; Shigemori, Yuji*; Seki, Akiyuki

no journal, , 

no abstracts in English

6 (Records 1-6 displayed on this page)
  • 1