Neutronic safety parameters and transient analyses for Poland's MARIA research reactor.

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Reactor kinetic parameters, reactivity feedback coefficients, and control rod reactivity worths have been calculated for the MARIA Research Reactor (Swierk, Poland) for M6-type fuel assemblies with {sup 235}U enrichments of 80% and 19.7%. Kinetic parameters were evaluated for family-dependent effective delayed neutron fractions, decay constants, and prompt neutron lifetimes and neutron generation times. Reactivity feedback coefficients were determined for fuel Doppler coefficients, coolant (H{sub 2}O) void and temperature coefficients, and for in-core and ex-core beryllium temperature coefficients. Total and differential control rod worths and safety rod worths were calculated for each fuel type. These parameters were used to calculate generic ... continued below

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16 p.

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Bretscher, M. M.; Hanan, N. A.; Matos, J. E.; Andrzejewski, K. & Kulikowska, T. September 27, 1999.

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Reactor kinetic parameters, reactivity feedback coefficients, and control rod reactivity worths have been calculated for the MARIA Research Reactor (Swierk, Poland) for M6-type fuel assemblies with {sup 235}U enrichments of 80% and 19.7%. Kinetic parameters were evaluated for family-dependent effective delayed neutron fractions, decay constants, and prompt neutron lifetimes and neutron generation times. Reactivity feedback coefficients were determined for fuel Doppler coefficients, coolant (H{sub 2}O) void and temperature coefficients, and for in-core and ex-core beryllium temperature coefficients. Total and differential control rod worths and safety rod worths were calculated for each fuel type. These parameters were used to calculate generic transients for fast and slow reactivity insertions with both HEU and LEU fuels. The analyses show that the HEU and LEU cores have very similar responses to these transients.

Physical Description

16 p.

Notes

INIS; OSTI as DE00750510

Medium: P; Size: 16 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-100104
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 750510
  • Archival Resource Key: ark:/67531/metadc709721

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Office of Scientific & Technical Information Technical Reports

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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, 3:22 p.m.

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Bretscher, M. M.; Hanan, N. A.; Matos, J. E.; Andrzejewski, K. & Kulikowska, T. Neutronic safety parameters and transient analyses for Poland's MARIA research reactor., article, September 27, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc709721/: accessed May 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.