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CCC-0655 MRIPP 1.0.

MRIPP, Magnetic Resonance Images (MRI) Data for Calibration of In Vivo Radionuclides Deposit Measurements

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1. NAME OR DESIGNATION OF PROGRAM:  MRIPP 1.0.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
No item

Machines used:

No specified machine
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3. DESCRIPTION OF PROGRAM OR FUNCTION

MRIPP provides relative calibration factors for the in vivo measurement of internally deposited photon emitting radionuclides within the human body. The code includes a database of human anthropometric structures (phantoms) that were constructed from whole body Magnetic Resonance  Images. The database contains a large variety of human images with varying anatomical structure. Correction factors are obtained using  Monte Carlo transport of photons through the Voxel geometry of the phantom. Correction factors provided by MRIPP allow user of in vivo  measurement systems (e.g. whole body counters) to calibrate these systems with simple sources and obtain subject specific calibrations. Note that the capability to format MRI data for use with this system is not included; therefore, one must use the phantom data included in this package.
MRIPP provides a simple interface to perform Monte Carlo simulation of photon transport through the human body. MRIPP also provides anthropometric information (e.g. height, weight, etc.) for  individuals used to generate the phantom database.
A modified Voxel version of the Los Alamos National Laboratory MCNP4A code is used for the Monte Carlo simulation. The Voxel version Fortran patch to MCNP4 and MCNP4A (Monte Carlo N-Particle transport simulation) and the MCNP executable are included in this distribution, but the MCNP Fortran source is not included. It was distributed by RSICC as CCC-200 but is now obsoleted by the release  MCNP4B.
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4. METHOD OF SOLUTION

Magnetic Resonance Image data are used as input to a voxel version of MCNP. The voxel version of MCNP recognizes the presence of voxel data files (material.*) and performs photon transport using a fictitious cross section method. Calculations are  performed for a simple source geometry and for a MRI input file. The ratio of these to values for the same energy line provides a
correction factor for calibration.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Some materials may be composed of eight or fewer elements. Other materials may be composed of four of fewer elements. No more than 20 photon energies  may be defined. Simple sources may have only one layer of housing/shielding. Up to 10 transformation cards are allowed.
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6. TYPICAL RUNNING TIME

Execution of this software requires 1 to 10 hours for a million photon histories through a 12 to 16 million voxel phantom. Execution speed improves with higher energy photons.  Multiple photon energies will slow the execution slightly, however execution speed will largely depend on the lowest photon energy. Faster computers are already reducing these times.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
No status
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10. REFERENCES:
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11. MACHINE REQUIREMENTS

PC 386 (or later), 60 MHz, 80 Mbyte free disk space, 8 Mbyte RAM (16 MB preferred), and compatible printer.
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

DOS 5.0 or later. All other required software is provided with MRIPP. MRIPP was compiled in Borland C++ 4.0 under DOS 6 on a Pentium processor. The  voxel patch to MCNP was compiled with Lahey Fortran 5.01 on a 486. MRIPP can be run in a DOS window of Windows95.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
                Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:
                Lawrence Livermore National Laboratory, Livermore,
                California
                Experimental and Mathematical Physics Consultants,
                Gaithersburg, Maryland
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16. MATERIAL AVAILABLE
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: Monte Carlo method, dosimeters, photon interaction.