Neutron transport studies for the Ignitor neutron diagnostics

S. Rollet, P. Batistoni

Research output: Contribution to journalArticle

4 Citations (Scopus)

Abstract

As a preliminary step for the project of the neutron diagnostics in the Ignitor tokamak, the overall neutron field in the device has been calculated with the help of the MCNP code, which solves, with the Monte Carlo method, neutron and photon transport problems in arbitrary three-dimensional geometries. The poloidal distribution of the fluxes on the first wall and the related energy spectra have been calculated to estimate the backscattered contribution to signals at spectrometers and collimated detectors for measurements with spatial resolution in the plasma. The average fluxes on the top and the lateral cryostat surfaces and the local fluxes on the equatorial plane outside the cryostat wall are also calculated in order to determine the neutron counters characteristics and expected performances.
Original languageEnglish
Pages (from-to)4551 - 4553
Number of pages3
JournalReview of Scientific Instruments
Volume63
Issue number10
DOIs
Publication statusPublished - 1992
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Instrumentation
  • Physics and Astronomy (miscellaneous)

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