A Monte Carlo model system for core analysis and epithermal neutron beam design at the Washington State University Radiation Center

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The Monte Carlo Model System (MCMS) for the Washington State University (WSU) Radiation Center provides a means through which core criticality and power distributions can be calculated, as well as providing a method for neutron and photon transport necessary for BNCT epithermal neutron beam design. The computational code used in this Model System is MCNP4A. The geometric capability of this Monte Carlo code allows the WSU system to be modeled very accurately. A working knowledge of the MCNP4A neutron transport code increases the flexibility of the Model System and is recommended, however, the eigenvalue/power density problems can be run with ... continued below

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81 p.

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Burns, T.D. Jr. May 1, 1996.

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Description

The Monte Carlo Model System (MCMS) for the Washington State University (WSU) Radiation Center provides a means through which core criticality and power distributions can be calculated, as well as providing a method for neutron and photon transport necessary for BNCT epithermal neutron beam design. The computational code used in this Model System is MCNP4A. The geometric capability of this Monte Carlo code allows the WSU system to be modeled very accurately. A working knowledge of the MCNP4A neutron transport code increases the flexibility of the Model System and is recommended, however, the eigenvalue/power density problems can be run with little direct knowledge of MCNP4A. Neutron and photon particle transport require more experience with the MCNP4A code. The Model System consists of two coupled subsystems; the Core Analysis and Source Plane Generator Model (CASP), and the BeamPort Shell Particle Transport Model (BSPT). The CASP Model incorporates the S({alpha}, {beta}) thermal treatment, and is run as a criticality problem yielding, the system eigenvalue (k{sub eff}), the core power distribution, and an implicit surface source for subsequent particle transport in the BSPT Model. The BSPT Model uses the source plane generated by a CASP run to transport particles through the thermal column beamport. The user can create filter arrangements in the beamport and then calculate characteristics necessary for assessing the BNCT potential of the given filter want. Examples of the characteristics to be calculated are: neutron fluxes, neutron currents, fast neutron KERMAs and gamma KERMAs. The MCMS is a useful tool for the WSU system. Those unfamiliar with the MCNP4A code can use the MCMS transparently for core analysis, while more experienced users will find the particle transport capabilities very powerful for BNCT filter design.

Physical Description

81 p.

Notes

INIS; OSTI as DE96010608

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  • Other Information: PBD: May 1996

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  • Other: DE96010608
  • Report No.: INEL--95/0458
  • Grant Number: AC07-94ID13223
  • DOI: 10.2172/236231 | External Link
  • Office of Scientific & Technical Information Report Number: 236231
  • Archival Resource Key: ark:/67531/metadc671364

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Creation Date

  • May 1, 1996

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • Dec. 18, 2015, 4 p.m.

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Burns, T.D. Jr. A Monte Carlo model system for core analysis and epithermal neutron beam design at the Washington State University Radiation Center, report, May 1, 1996; United States. (digital.library.unt.edu/ark:/67531/metadc671364/: accessed December 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.