A FORTRAN SOURCE-ENERGY INTEGRATION PROGRAM FOR THE NGM CODE OUTPUT,

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Abstract:

This report describes a digital computer program written for the GE 225 Computer 16K core storage and 6 magnetic tape drives in the Tape FORTRAN language. It differs from the original program See AD-645 929 in that a complete detector is read into the computer memory at one time which allows a faster and more efficient program. The program integrates the LASL NGM radiation transport code differential flux output with respect to the source-energy variable weighted by a user-supplied function. The resultant output is the flux at the detectors due to the user-supplied source-energy spectrum. The method of performing the weighted source-energy integration operation and the use of checks to minimize error are given through the use of a flow diagram with complementary textual description and FORTRAN source-deck listing. The method of program operation and proper response to error signals are also described. Author

Author(s):
Beverly, William B. ; Lacetera, Joseph
Author Organization(s):
ARMY NUCLEAR DEFENSE LAB EDGEWOOD ARSENAL MD
Pagination:
0031

Security Markings

DOCUMENT & CONTEXTUAL SUMMARY

Distribution:
Approved For Public Release

RECORD

Collection: TR
Identifying Numbers
Report Number(s):
NDL-TM-43
 Subject Terms
Communities of Interest:
Energy and Power Technologies
Descriptor(s):
(*NUCLEAR EXPLOSIONS, NUCLEAR RADIATION), (*NEUTRON CAPTURE GAMMA RAYS, MONTE CARLO METHOD), (*COMPUTER PROGRAMS, *NEUTRON TRANSPORT THEORY), TRANSPORT PROPERTIES, DIGITAL COMPUTERS, NEUTRONS, GAMMA RAYS, AIRBURST, SHOCK WAVES, DIGITAL RECORDING SYSTEMS, FLOW CHARTING, SUBROUTINES, DETECTORS
Field(s)/Group(s):
Computer Programming and Software, Computer Hardware, Nuclear Radiation Shielding, Protection and Safety
Keyword(s):
FORTRAN, GE 225 COMPUTERS
Report Date:
1968 Jun 01