Community Research and Development Information Service - CORDIS

Abstract

Neutron transport calculations have been performed using the Monte Carlo particle trajectory sampling method (the MCNP code) in order to determine the neutron fluences and energy distributions at different locations in the JET tokamak. The primary purpose of these calculations was to calibrate the activation measurements used in the determination of the absolute fusion neutron yield from the JET plasma. The authors present here the calculated neutron activation response coefficients for three different materials used in the neutron yield determinations for plasmas producing 2.5 and 14 MeV neutrons. The accuracy of the calibration derived from the neutron transport calculation was tested by comparing the present results for the total 2.5 MeV neutron yield with those obtained with calibrated fission chambers; overall agreement at the pm15% level was demonstrated.

Additional information

Authors: PILLON M, JET JOINT UNDERTAKING, ABINGDON, UK;JARVIS O N, JET JOINT UNDERTAKING, ABINGDON, UK;KAELLNE J, JET JOINT UNDERTAKING, ABINGDON, UK;MARTONE M JET JOINT UNDERTAKING, ABINGDON, UK, JET JOINT UNDERTAKING, ABINGDON, UK
Bibliographic Reference: REPORT JET-P(88)10, 1988, AVAILABILITY: JET, ABINGDON, UK
Record Number: 1989126096600 / Last updated on: 1989-05-01
Category: PUBLICATION
Available languages: en