MicroShield® | 辐射剂量计算软件

MicroShield®是一款辐射剂量计算软件，它广泛应用于屏蔽体设计与屏蔽外参考点剂量率计算等方面。 该软件有16种源项模型并自带一个含12种屏蔽材料的材料库以及一个含大量放射性核素的核素库，用户还可以根据工程需要自行添加屏蔽材料，这些功能使用户在建模时有更广泛的选择范围。

MicroShield®除了重视建模、核素参量输入等功能外，其最终结果是以Microsoft Office®方式输出，方便用户对计算结果进行后续应用。

【英文介绍】

MicroShield® is a comprehensive photon/gamma ray shielding and dose assessment program that is widely used for designing shields, estimating source strength from radiation measurements, minimizing exposure to people, and teaching shielding principles.

MicroShield® is useful to health physicists, waste managers, design engineers, and radiological engineers and only requires a basic knowledge of radiation and shielding principles.

MicroShield® is fully interactive and utilizes extensive input error checking. Integrated tools provide graphing of results, material and source file creation, source inference with decay (dose-to-Ci calculations accounting for decay and daughter buildup), projection of exposure rate versus time as a result of decay, access to material and nuclide data, and decay heat calculations.

MicroShield® Version 10 includes the addition of the International Commission on Radiological Protection (ICRP) Publication 116 absorbed dose rates as well as:

·         Inclusion of the historical ANSI/ANS-6.1.1-1977 gamma dose conversion factors

·         Microsoft Windows® 8 compatibility as well as Windows 7, Vista® and XP®

·         Ability to export results using any version Microsoft Office®

·         Improved French and German versions of the main software interface

·                   Customized Reports

MICROSHIELD’S® FEATURES INCLUDE:

·         Full Microsoft Windows® 8/8.1 (32 bit and 64 bit), Windows® 7 (32 bit and 64 bit), Vista® and XP®compatibility.

·         Ability to export results into Microsoft Office® applications.

·         Ability to utilize international numerical formats (decimal commas, etc.).

·         Current industry standard dose conversion factors including ICRP-116, ICRP-74, ICRP-51 as well as ANSI/ANS-6.1.1.

·         Sixteen geometries that accommodate offset dose points and as many as ten standard shields plus source self-shielding and cylinder cladding.

·         The geometry display for entry is re-scaled as dimensions are entered. Dimensional data are accepted in meters, centimeters, feet, or inches.

·         Library data (radionuclides, attenuation, buildup, and dose conversion) reflect standard data from industry standard radiation libraries ICRP-38 and ICRP-107 as well as ANSI/ANS standards and RSICC publications.

·         Buildup and uncollided results are both automatically and simultaneously calculated.

·         Sources may be created and saved and moved among cases (either as nuclides or energies) and as concentrations or totals.  Several photon grouping methods are provided including custom (user defined) grouping methods.

·         Source decay can be calculated with daughter products generated using the same algorithms as found in the RadDecay® software

GEOMETRY – SOURCE CONFIGURATIONS INCLUDED:

·         Point

·         Line

·         Disk

·         Rectangular Area – Vertical

·         Rectangular Area – Horizontal

·         Sphere

·         Cylinder Volume – Side Shields

·         Cylinder Volume – End Shields

·         Cylinder Surface – Internal Dose Point

·         Cylinder Surface – External Dose Point

·         Annular Cylinder – Internal Dose Point

·         Annular Cylinder – External Dose Point

·         Rectangular Volume

·         Truncated Cone

·         Infinite Plane

·         Infinite Slab

MICROSHIELD 10 NEW FEATURES:

ICRP Publication 116

ICRP Publication 116 (Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures, Annals of ICRP Volume 40(2-5), 2010) provides fluence to dose conversion coefficients for both effective dose and organ absorbed doses for various types of external exposures, consistent with the 2007 Recommendations of the ICRP. These coefficients were calculated using the official ICRP/ICRU computational phantoms representing the Reference Adult Male and Reference Adult Female, in conjunction with Monte Carlo codes simulating the transport of radiation within the human body such as EGSnrc, FLUKA, GEANT4, MCNPX, and PHITS.

The incident radiations and energy ranges considered were external beams of mono-energetic photons of 10 keV to 10 GeV. For the simulations, idealized whole-body irradiation geometries were considered. These included unidirectional broad parallel beams along the antero-posterior, postero-anterior, left lateral and right lateral axes, and 360° rotational directions around the phantoms’ longitudinal axis. Fully isotropic irradiation of the phantoms was also considered.

ANSI/ANS-6.1.1-1977: Neutron and Gamma-Ray Fluence-To-Dose Factors

MicroShield® is now includes the reference gamma dose conversion factors from ANSI/ANS-6.1.1-1977: Neutron and Gamma-Ray Fluence-To-Dose Factors to support calculations for NUREG-1617, “Standard Review Plan for Transportation Packages for Spent Nuclear Fuel”.

Complete Exporting of Results

You can now save all general results as a Microsoft Word®, Microsoft Excel®, HTML, or text files. MicroShield® now supports any version of Microsoft Office®. Results that are saved as any of the first three file types are formatted and color coded for easy readability.

Microsoft Windows® 8/8.1 Native Compatibility

MicroShield® is now fully compatible with the following operating systems: Microsoft XP®, Microsoft Vista®, Microsoft Windows® 7 (32 bit and 64 bit), and Microsoft Windows® 8/8.1 (32 bit and 64 bit).

Improved Language Translations

The MicroShield® software is available in English, French, and German languages with recent updates to the French and German language translations. The majority of menus, captions, messages, and report results will display in the language of the installed version.

Enhanced Reports and Options

The user now has the option of having the Case Summary Report or Dose Equivalent Report as the default reporting style. In addition, exposure dose and fluence rates as well as the ANSI/ANS-6.1.1-1977, ICRP-51, ICRP-74, and ICRP-116 results can now be customized on the Dose Equivalent Report.

Requirements:

·         Microsoft Windows® 8.1/8/7/Vista/XP

·         Microsoft® Internet Explorer® Version 7 and above

·         For exporting results to Microsoft Excel® and Word®, Microsoft Office® is required.