Neutronic safety and transient analyses for potential LEU conversion of the IR-8 research reactor.

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Kinetic parameters, isothermal reactivity feedback coefficients and three transients for the IR-8 research reactor cores loaded with either HEU(90%), HEU(36%), or LEU (19.75%) fuel assemblies (FA) were calculated using three dimensional diffusion theory flux solutions, RELAP5/MOD3.2 and PARET. The prompt neutron generation time and effective delayed neutron fractions were calculated for fresh and beginning-of-equilibrium-cycle cores. Isothermal reactivity feedback coefficients were calculated for changes in coolant density, coolant temperature and fuel temperature in fresh and equilibrium cores. These kinetic parameters and reactivity coefficients were used in transient analysis models to predict power histories, and peak fuel, clad and coolant temperatures. The ... continued below

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17 p.

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Deen, J. R.; Hanan, N. A.; Smith, R. S.; Matos, J. E.; Egorenkov, P. M. & Nasonov, V. A. September 27, 1999.

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Kinetic parameters, isothermal reactivity feedback coefficients and three transients for the IR-8 research reactor cores loaded with either HEU(90%), HEU(36%), or LEU (19.75%) fuel assemblies (FA) were calculated using three dimensional diffusion theory flux solutions, RELAP5/MOD3.2 and PARET. The prompt neutron generation time and effective delayed neutron fractions were calculated for fresh and beginning-of-equilibrium-cycle cores. Isothermal reactivity feedback coefficients were calculated for changes in coolant density, coolant temperature and fuel temperature in fresh and equilibrium cores. These kinetic parameters and reactivity coefficients were used in transient analysis models to predict power histories, and peak fuel, clad and coolant temperatures. The transients modeled were a rapid and slow loss-of-flow, a slow reactivity insertion, and a fast reactivity insertion.

Physical Description

17 p.

Notes

INIS; OSTI as DE00750512

Medium: P; Size: 17 pages

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  • 1999 International Meeting on Reduced Enrichment for Research and Test Reactors, Budapest (HU), 10/03/1999--10/08/1999

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  • Report No.: ANL/TD/CP-100107
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 750512
  • Archival Resource Key: ark:/67531/metadc704683

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  • September 27, 1999

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  • Sept. 12, 2015, 6:31 a.m.

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  • April 7, 2017, 3:36 p.m.

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Deen, J. R.; Hanan, N. A.; Smith, R. S.; Matos, J. E.; Egorenkov, P. M. & Nasonov, V. A. Neutronic safety and transient analyses for potential LEU conversion of the IR-8 research reactor., article, September 27, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc704683/: accessed November 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.