Application of Monte Carlo codes to neutron dosimetry [electronic resource].
- Published
- Livermore, Calif : Lawrence Livermore National Laboratory, 1982.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 22 : digital, PDF file
- Additional Creators
- Lawrence Livermore National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- In neutron dosimetry, calculations enable one to predict the response of a proposed dosimeter before effort is expended to design and fabricate the neutron instrument or dosimeter. The nature of these calculations requires the use of computer programs that implement mathematical models representing the transport of radiation through attenuating media. Numerical, and in some cases analytical, solutions of these models can be obtained by one of several calculational techniques. All of these techniques are either approximate solutions to the well-known Boltzmann equation or are based on kernels obtained from solutions to the equation. The Boltzmann equation is a precise mathematical description of neutron behavior in terms of position, energy, direction, and time. The solution of the transport equation represents the average value of the particle flux density. Integral forms of the transport equation are generally regarded as the formal basis for the Monte Carlo method, the results of which can in principle be made to approach the exact solution. This paper focuses on the Monte Carlo technique.
- Report Numbers
- E 1.99:ucrl-87745
E 1.99: conf-820668-2
conf-820668-2
ucrl-87745 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
06/15/1982.
"ucrl-87745"
" conf-820668-2"
"DE82017635"
9. DOE workshop on personnel neutron dosimetry, Las Vegas, NV, USA, 24 Jun 1982.
Prevo, C.T. - Funding Information
- W-7405-ENG-48
View MARC record | catkey: 14793121