Actions for Conversion Analyses for the VR-1 Reactor, part I and II [electronic resource].

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Conversion Analyses for the VR-1 Reactor, part I and II [electronic resource].

Published
Argonne, Ill. : Argonne National Laboratory, 2005.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators
Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
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 ²³⁵U 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.
Report Numbers
E 1.99:anl-05/18
anl-05/18
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Note
Published through SciTech Connect.
11/14/2005.
"anl-05/18"
Stillman, J. A.; Olson, A. P.; Matos, J. E.; Garner, P.L.; Hannan, N. A.
Funding Information
W-31-109-ENG-38
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