Neutron transport calculations in support of neutron diagnostics at JET

M.J. Loughlin, N. Watkins, L. Bertalot, B. Esposito, A.L. Roquemore

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Abstract

At JET the primary diagnostic for monitoring the neutron emission is a set of fission chambers. These are calibrated using the neutron activation technique. A second independent measurement of the neutron yield can be obtained from the neutron profile monitor. Both measurements depend on neutron transport calculations and at JET this has been done using the neutron transport code MCNP. The introduction of tritium into JET plasmas provided an opportunity to check the modeling by comparing the activation of different materials. The calculation of the neutron spectrum at a re-entrant irradiation position was found to be consistent with measurements and an accuracy of <7% in the neutron yield measurement was obtained. Neutron transport calculations of the effective collimator correction and attenuation for the profile monitor are also described. © 1999 American Institute of Physics.
Original languageEnglish
Pages (from-to)1126 - 1129
Number of pages4
JournalReview of Scientific Instruments
Volume70
Issue number1 II
Publication statusPublished - Jan 1999
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Instrumentation

Cite this

Loughlin, M. J., Watkins, N., Bertalot, L., Esposito, B., & Roquemore, A. L. (1999). Neutron transport calculations in support of neutron diagnostics at JET. Review of Scientific Instruments, 70(1 II), 1126 - 1129.