Evaluation of reactor kinetic parameters without the need for perturbation codes.

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The analysis of research reactor transients depends on the effective delayed neutron fraction (k{sub eff}), its family-dependent components ({beta}{sub eff,i}), the prompt neutron lifetime (l{sub p}), and the decay constants ({lambda}{sub i}) for each delayed neutron family. Beginning with ENDF/B-V data, methods are presented for accurately calculating these kinetic parameters within the framework of diffusion theory but without the need for a perturbation code. For heavy water systems these methods can be extended to include the delayed photoneutron component of {beta}{sub eff}. However, a separate calculation is needed to estimate the fractional loss of fission product gamma rays, energetic enough ... continued below

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15 p.

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Bretscher, M. M. January 14, 1998.

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The analysis of research reactor transients depends on the effective delayed neutron fraction (k{sub eff}), its family-dependent components ({beta}{sub eff,i}), the prompt neutron lifetime (l{sub p}), and the decay constants ({lambda}{sub i}) for each delayed neutron family. Beginning with ENDF/B-V data, methods are presented for accurately calculating these kinetic parameters within the framework of diffusion theory but without the need for a perturbation code. For heavy water systems these methods can be extended to include the delayed photoneutron component of {beta}{sub eff}. However, a separate calculation is needed to estimate the fractional loss of fission product gamma rays, energetic enough to dissociate the deuteron, from leakage, energy degradation and absorption in fuel and structural materials. These methods are illustrated for a light-water Oak Ridge Research Reactor (ORR) LEU core and for a heavy-water Georgia Tech Research Reactor (GTRR) HEU core where calculated and measured values of the prompt neutron decay constant ({beta}{sub eff}/l{sub p}) are compared.

Physical Description

15 p.

Notes

INIS; OSTI as DE00010571

Medium: P; Size: 15 pages

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  • International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Jackson Hole, WY (US), 10/05/1997--10/10/1997

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  • Report No.: ANL/TD/CP-95381
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 10571
  • Archival Resource Key: ark:/67531/metadc624146

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Office of Scientific & Technical Information Technical Reports

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Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • January 14, 1998

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  • June 16, 2015, 7:43 a.m.

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  • April 7, 2017, 2:58 p.m.

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Bretscher, M. M. Evaluation of reactor kinetic parameters without the need for perturbation codes., article, January 14, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc624146/: accessed December 11, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.