Utilization of new 150-MeV neutron and proton evaluations in MCNP

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MCNP{trademark} and LAHET{trademark} are two of the codes included in the LARAMIE (Los Alamos Radiation Modeling Interactive Environment) code system. Both MCNP and LAHET are three-dimensional continuous-energy Monte Carlo radiation transport codes. The capabilities of MCNP and LAHET are currently being merged into one code for the Accelerator Production of Tritium (APT) program at Los Alamos National Laboratory. Concurrently, a significant effort is underway to improve the accuracy of the physics in the merged code. In particular, full nuclear-data evaluations (in ENDF6 format) for many materials of importance to APT are being produced for incident neutrons and protons up to ... continued below

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5 p.

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Little, R.C.; Frankle, S.C.; Hughes, H.G. III & Prael, R.E. October 1, 1997.

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MCNP{trademark} and LAHET{trademark} are two of the codes included in the LARAMIE (Los Alamos Radiation Modeling Interactive Environment) code system. Both MCNP and LAHET are three-dimensional continuous-energy Monte Carlo radiation transport codes. The capabilities of MCNP and LAHET are currently being merged into one code for the Accelerator Production of Tritium (APT) program at Los Alamos National Laboratory. Concurrently, a significant effort is underway to improve the accuracy of the physics in the merged code. In particular, full nuclear-data evaluations (in ENDF6 format) for many materials of importance to APT are being produced for incident neutrons and protons up to an energy of 150-MeV. After processing, cross-section tables based on these new evaluations will be available for use fin the merged code. In order to utilize these new cross-section tables, significant enhancements are required for the merged code. Neutron cross-section tables for MCNP currently specify emission data for neutrons and photons only; the new evaluations also include complete neutron-induced data for protons, deuterons, tritons, and alphas. In addition, no provision in either MCNP or LAHET currently exists for the use of incident charged-particle tables other than for electrons. To accommodate the new neutron-induced data, it was first necessary to expand the format definition of an MCNP neutron cross-section table. The authors have prepared a 150-MeV neutron cross-section library in this expanded format for 15 nuclides. Modifications to MCNP have been implemented so that this expanded neutron library can be utilized.

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5 p.

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INIS; OSTI as DE97008194

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  • International conference on nuclear data for science and technology, Trieste (Italy), 19-24 May 1997

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  • Other: DE97008194
  • Report No.: LA-UR--97-1825
  • Report No.: CONF-970524--8
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 532548
  • Archival Resource Key: ark:/67531/metadc690912

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  • October 1, 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • Feb. 26, 2016, 9:39 p.m.

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Little, R.C.; Frankle, S.C.; Hughes, H.G. III & Prael, R.E. Utilization of new 150-MeV neutron and proton evaluations in MCNP, article, October 1, 1997; New Mexico. (digital.library.unt.edu/ark:/67531/metadc690912/: accessed August 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.