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Topaz video enhance ai 2.6.012/27/2023 ![]() ![]() This faithful utilization of sophisticated ENDF/B evaluations allows more precise MCNP calculations for several classes of coupled neutron-photon problems The new method makes use of all partial photon-production reaction data provided by ENDF/B evaluators including photon-production cross sections as well as energy and angular distributions of secondary photons. Neutron-induced photon production in MCNPĪn improved method of neutron-induced photon production has been incorporated into the Monte Carlo transport code MCNP. Modifications to MCNP have been implemented so that this expanded neutron library can be utilized The authors have prepared a 150-MeV neutron cross-section library in this expanded format for 15 nuclides. ![]() To accommodate the new neutron-induced data, it was first necessary to expand the format definition of an MCNP neutron cross-section table. In addition, no provision in either MCNP or LAHET currently exists for the use of incident charged-particle tables other than for electrons. 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 order to utilize these new cross-section tables, significant enhancements are required for the merged code. After processing, cross-section tables based on these new evaluations will be available for use fin 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. Concurrently, a significant effort is underway to improve the accuracy of the physics in the merged code. 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. Both MCNP and LAHET are three-dimensional continuous-energy Monte Carlo radiation transport codes. MCNP trademark and LAHET trademark are two of the codes included in the LARAMIE (Los Alamos Radiation Modeling Interactive Environment) code system. Utilization of new 150-MeV neutron and proton evaluations in MCNP Analyses reveal that MCNP calculates thermal neutron spectra fairly accurately, while it apparently over-estimates epithermal neutron spectra (of approximate 1/E distribution) as compared with the measurements. Kotegawa, Hiroshi Sasamoto, Nobuo Tanaka, Shun-ichiīoth ''measured radioactive inventory due to neutron activation in the shield concrete of JPDR'' and ''measured intermediate and low energy neutron spectra penetrating through a graphite sphere'' are analyzed using a continuous energy model Monte Carlo code MCNP so as to estimate calculational accuracy of the code for neutron transport in thermal and epithermal energy regions. International Nuclear Information System (INIS) ![]() Accuracy estimation for intermediate and low energy neutron transport calculation with Monte Carlo code MCNP ![]()
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