Monte Carlo program for calculating neutron detection efficiencies in plastic scintillator
A FORTRAN IV Monte Carlo program to calculate the neutron detection efficiency of plastic scintillators of rectangular or cylindrical geometry as a function of neutron energy and light collection threshold has been written and tested. The existing cross-section data for neutron-carbon interactions have been adjusted to give a good fit to existing measurements of efficiency. This document contains a complete description of the physics input and method of approach, together with detailed instructions for use of the program. A listing of the source code, the data deck, and output of a sample calculation are appended.
- Research Organization:
- Ohio State Univ. Research Foundation, Columbus (USA)
- OSTI ID:
- 7179467
- Report Number(s):
- COO-1545-92
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
440101* -- Radiation Instrumentation-- General Detectors or Monitors & Radiometric Instruments
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
COMPUTER CALCULATIONS
COMPUTER CODES
EFFICIENCY
ENERGY DEPENDENCE
FORTRAN
MEASURING INSTRUMENTS
MONTE CARLO METHOD
NEUTRON DETECTION
PLASTIC SCINTILLATION DETECTORS
PROGRAMMING LANGUAGES
RADIATION DETECTION
RADIATION DETECTORS
SCINTILLATION COUNTERS
SOLID SCINTILLATION DETECTORS
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
COMPUTER CALCULATIONS
COMPUTER CODES
EFFICIENCY
ENERGY DEPENDENCE
FORTRAN
MEASURING INSTRUMENTS
MONTE CARLO METHOD
NEUTRON DETECTION
PLASTIC SCINTILLATION DETECTORS
PROGRAMMING LANGUAGES
RADIATION DETECTION
RADIATION DETECTORS
SCINTILLATION COUNTERS
SOLID SCINTILLATION DETECTORS