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CCC-0046 OGRE.

OGRE, Monte-Carlo System for Gamma Transport Problems

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1. NAME OR DESIGNATION OF PROGRAM:  OGRE.
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2. COMPUTERS
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Program name Package id Status Status date
OGRE CCC-0046/01 Tested 01-NOV-1966

Machines used:

Package ID Orig. computer Test computer
CCC-0046/01 IBM 360 series IBM 360 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

The OGRE programme system was designed to calculate, by Monte Carlo methods, any quantity related  to gamma-ray transport. The system is represented by two examples -  OGRE-P1 and OGRE-G. The OGRE-P1 programme is a simple prototype which calculates dose rate on one side of a slab due to a plane source on the other side. The OGRE-G programme, a prototype of a programme utilizing a general-geometry routine, calculates dose rate at arbitrary points. A very general source description in OGRE-G may be employed by reading a tape prepared by the user.
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4. METHOD OF SOLUTION

Case histories of gamma rays in the prescribed geometry are generated and analyzed to produce averages of any desired quantity which, in the case of the prototypes, are gamma-ray dose rates. The system is designed to achieve generality by ease of  modification. No importance sampling is built into the prototypes, a very general geometry subroutine permits the treatment of complicated geometries. This is essentially the same routine used in the O5R neutron transport system. Boundaries may be either planes or quadratic surfaces, arbitrarily oriented and intersecting in arbitrary fashion.
Cross section data is prepared by the auxiliary master cross section programme XSECT which may be used to originate, update, or edit the  master cross section tape. The master cross section tape is utilized in the OGRE programmes to produce detailed tables of macroscopic cross sections which are used during the Monte Carlo calculations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maximum cross-section array information may be estimated by a given formula for a specific problem.
The number of regions must be less than or equal to 50.
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6. TYPICAL RUNNING TIME

Running time varies with the type of problem. Estimated running time for the sample problems

XSECT, 2 minutes, 10 seconds. P1, 2 minutes, 20 seconds.
OGRE-G 2 minutes on the IBM 7090.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED AND AUXILIARY PROGRAMS

OGRE-P1 - transmission through laminated slab - sample calculation.
OGRE-G - calculation of dose rate at arbitrary points in an arbitrary geometry.
XSECT - cross section handling programme and library.
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9. STATUS
Package ID Status date Status
CCC-0046/01 01-NOV-1966 Tested at NEADB
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10. REFERENCES
CCC-0046/01, included references:
- S.K. Penny, D.K. Trubey, and M.B. Emmett:
"OGRE, A Monte Carlo system for Gamma-Ray Transport
Studies, Including an Example (OGRE-P1) for Transmission
Through Laminated Slabs"
ORNL-3805 (April 1966)
- U.Shunsuke
"Description of OGRE-GS"
May 1974
-D.K. Trubey and M.B. Emmett
"OGRE-G, An OGRE System Monte Carlo Code for the Calculation
of Gamma-Ray Dose Rate at Arbitrary Points in an Arbitrary
Geometry"
ORNL-TM-1212 (January 1966)
- Data Sheets, OGRE G and OGRE-P1
- D.K. Trubey
"PRINT-SIG, An OGRE Routine to Print Gamma-Ray Total Cross
Sections and Energy Desposition Coefficients"
ORNL-TM-3048 (October 1968)
- D.K. Trubey and H.E Francis
"OGRE MASTAPE - Photon Interaction Cross Section Library
and Data Handling Code"
ORNL-TM-3046 (July 1969)
- D.K.Trubey, S.K. Penny, M.B. Emmett
"OGRE-P2, A Monte Carlo Program for Computing Gamma-Ray
Leakage from Laminated Slabs with a Distributed Source"
ORNL-TM-237 (August 1962).
- D.K. Trubey and J.R. Stockton
"OGRE Cross Section Package for Using Photon Interaction
Data in ENDF/B Format"
ORNL-TM-2757 (October 1969)
- E. Nitteberg
"The OGRE System for CDC 3600"
(December 1966)
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11. MACHINE REQUIREMENTS

Standard equipment is used on either computer. Three tape units are needed on the IBM 7090 and the CDC-1604 computers, and two units are needed for the IBM 360, plus the on-line card reader.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0046/01 FORTRAN-IV
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13. SOFTWARE REQUIREMENTS: OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

         Neutron Physics Division
         Oak Ridge National Laboratory
         Oak Ridge, Tennessee, U. S. A.
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16. MATERIAL AVAILABLE
CCC-0046/01
File name File description Records
CCC0046_01.001 MASTAPE SOURCE 148
CCC0046_01.002 MASTAPE DATA %LIBRARY< 1304
CCC0046_01.003 MASTAPE OUTPUT 4134
CCC0046_01.004 OGRE P1 SOURCE & DATA 692
CCC0046_01.005 OGRE P1 OUTPUT 12
CCC0046_01.006 OGRE G SOURCE & DATA 1952
CCC0046_01.007 OGRE G OUTPUT 11
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17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: Monte Carlo method, cross sections, dose rates, gamma radiation, slabs, transport theory.