Conversion Analyses for the VR-1 Reactor, part I and II.

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At the request of the Czech Technical University (CTU) in Prague, ANL has performed independent verification calculations using the MCNP Monte Carlo code for three core configurations of the VR-1 reactor: a current core configuration B1 with HEU (36%) IRT-3M fuel assemblies and planned core configurations C1 and C2 with LEU (19.7%) IRT-4M fuel assemblies. Details of these configurations were provided to ANL by CTU. For core configuration B1, criticality calculations were performed for two sets of control rod positions provided to ANL by CTU. Fore core configurations C1 and C2, criticality calculations were done for cases with all control ... continued below

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Hannan, N. A.; Matos, J. E.; Stillman, J. A.; Olson, A. P. & Garner, P.L. November 14, 2005.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 13 times . More information about this report can be viewed below.

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At the request of the Czech Technical University (CTU) in Prague, ANL has performed independent verification calculations using the MCNP Monte Carlo code for three core configurations of the VR-1 reactor: a current core configuration B1 with HEU (36%) IRT-3M fuel assemblies and planned core configurations C1 and C2 with LEU (19.7%) IRT-4M fuel assemblies. Details of these configurations were provided to ANL by CTU. For core configuration B1, criticality calculations were performed for two sets of control rod positions provided to ANL by CTU. Fore core configurations C1 and C2, criticality calculations were done for cases with all control rods at the top positions, all control rods at the bottom positions, and two critical states of the reactor for different control rod positions. In addition, sensitivity studies for variation of the {sup 235}U mass in each fuel assembly and variation of the fuel meat and cladding thicknesses in each of the fuel tubes were doe for the C1 core configuration. The reactivity worth of the individual control rods was calculated for the B1, C1, and C2 core configurations. Finally, the reactivity feedback coefficients, the prompt neutron lifetime, and the total effective delay neutron fraction were calculated for each of the three cores.

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  • Report No.: ANL-05/18
  • Grant Number: W-31-109-ENG-38
  • DOI: 10.2172/885491 | External Link
  • Office of Scientific & Technical Information Report Number: 885491
  • Archival Resource Key: ark:/67531/metadc876438

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  • November 14, 2005

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  • Sept. 21, 2016, 2:29 a.m.

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  • Feb. 17, 2017, 1:06 p.m.

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Hannan, N. A.; Matos, J. E.; Stillman, J. A.; Olson, A. P. & Garner, P.L. Conversion Analyses for the VR-1 Reactor, part I and II., report, November 14, 2005; United States. (digital.library.unt.edu/ark:/67531/metadc876438/: accessed September 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.