Note on the development, benchmarking and validation of the APT neutronics engineering code

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Tritium production modeling can be used to gain cost savings and schedule improvements. However, at present much of the predictive uncertainty is in the modeling of neutron generation and transport, and tritium production in the target. These uncertainties require engineering design margins, primarily contingencies that increase the facility cost. Much of the uncertainty associated with the codes, in the (20--30)% uncertainty range, is thought to be due to multiple scattering (leakage) of high energy neutrons and possibly protons in the radial directions of range thick targets of less than (20--30) cm diameter. It is estimated that a well carried out ... continued below

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4 p.

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Ward, T.E.; Todosow, M.; Hanson, A.; Snead, C.L.; Slaughter, D. & Dietrich, F. III December 31, 1996.

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Description

Tritium production modeling can be used to gain cost savings and schedule improvements. However, at present much of the predictive uncertainty is in the modeling of neutron generation and transport, and tritium production in the target. These uncertainties require engineering design margins, primarily contingencies that increase the facility cost. Much of the uncertainty associated with the codes, in the (20--30)% uncertainty range, is thought to be due to multiple scattering (leakage) of high energy neutrons and possibly protons in the radial directions of range thick targets of less than (20--30) cm diameter. It is estimated that a well carried out neutronics measurement program coupled with high-energy transport code development could reduce the predictive engineering neutronics code uncertainty to the few percent level for all local or global geometries of use in the APT engineering design. This level of precision would then be comparable to the neutronics core physics codes employed in nuclear reactor design engineering. Following the improved engineering neutronics code development the overall engineering design contingencies for APT could then be reduced from the present (50--65)% level down to the more acceptable (25--30)% level.

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4 p.

Notes

INIS; OSTI as DE98000991

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  • Symposium on the Savannah River Accelerator project and complementary spallation neutron sources, Columbia, SC (United States), 14-15 May 1996

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  • Other: DE98000991
  • Report No.: BNL--64651
  • Report No.: CONF-9605223--
  • Grant Number: AC02-76CH00016
  • Office of Scientific & Technical Information Report Number: 548712
  • Archival Resource Key: ark:/67531/metadc693933

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  • December 31, 1996

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  • Aug. 14, 2015, 8:43 a.m.

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  • Nov. 24, 2015, 5:47 p.m.

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Ward, T.E.; Todosow, M.; Hanson, A.; Snead, C.L.; Slaughter, D. & Dietrich, F. III. Note on the development, benchmarking and validation of the APT neutronics engineering code, article, December 31, 1996; Upton, New York. (digital.library.unt.edu/ark:/67531/metadc693933/: accessed September 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.