Monte Carlo verification of point kinetics for safety analysis of nuclear reactors

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Monte Carlo neutron transport methods can be used to verify the applicability of point kinetics for safety analysis of nuclear reactors. KENO-NR was used to obtain the transfer function of the Advanced Neutron Source reactor and the time delay between the core power production and the external detectors, a parameter of interest to the safety systems design. The good agreement between the Monte Carlo generated transfer function and the point kinetics transfer function validates that the uncommon ANS geometry does not preclude the use of point kinetics in the frequency range that was investigated. Various features of the power spectral ... continued below

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10 p.

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Valentine, T.E. & Mihalczo, J.T. June 1, 1995.

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Monte Carlo neutron transport methods can be used to verify the applicability of point kinetics for safety analysis of nuclear reactors. KENO-NR was used to obtain the transfer function of the Advanced Neutron Source reactor and the time delay between the core power production and the external detectors, a parameter of interest to the safety systems design. The good agreement between the Monte Carlo generated transfer function and the point kinetics transfer function validates that the uncommon ANS geometry does not preclude the use of point kinetics in the frequency range that was investigated. Various features of the power spectral densities also demonstrated the applicability of point kinetics. The time delay was obtained from the cross-power spectral density (CPSD) and is {approximately}15 ms. These analyses show that frequency analysis can be used experimentally to investigate the validity of the use of point kinetics models in critical experiments or zero power testing of reactors.

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10 p.

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INIS; OSTI as DE95012846

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  • 7. international symposium on nuclear reactor surveillance and diagnostics, Avignon (France), 19-23 Jun 1995

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  • Other: DE95012846
  • Report No.: CONF-9506121--1
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 73014
  • Archival Resource Key: ark:/67531/metadc712152

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Office of Scientific & Technical Information Technical Reports

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  • June 1, 1995

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  • Sept. 12, 2015, 6:31 a.m.

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  • Jan. 19, 2016, 8:21 p.m.

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Valentine, T.E. & Mihalczo, J.T. Monte Carlo verification of point kinetics for safety analysis of nuclear reactors, article, June 1, 1995; Tennessee. (digital.library.unt.edu/ark:/67531/metadc712152/: accessed November 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.