CALIBRATION OF NEUTRON YIELD ACTIVATION MEASUREMENTS AT JET USING MCNP AND FURNACE NEUTRON TRANSPORT CODES
Neutron transport calculations have been performed using fluence ray tracing (FURNACE code) and Monte Carlo particle trajectory sampling methods (MCNP code) in order to determine the neutron fluence and energy distributions at different locations in the JET tokamak. These calculations were used to calibrate the activation measurements used in the determination of the absolute fusion neutron yields from the JET plasma. We present here the neutron activation response coefficients calculated for three different materials. Comparison of the MCNP and FURNACE results helps identify the sources of error in these neutron transport calculations. The accuracy of these calculations was tested by comparing the total 2.5 MeV neutron yields derived from the activation measurements with those obtained with calibrated fission chambers; agreement at the pm15% level was demonstrated.
Bibliographic Reference: REPORT JET-P(88)08, 1988, AVAILABILITY: JET, ABINGDON, UK
Record Number: 1989126098200 / Last updated on: 1989-05-01
Available languages: en