8-10 June 2016
Asia/Bangkok timezone

A model for predicting tritium flux from blanket mock-up in Tokamak fusion reactors

Jun 8, 2016, 11:00 AM
15m
Room J3

Room J3

Oral presentaion Nuclear and Radiation Physics session II

Speaker

Dr Siriyaporn Sangaroon (Department of Physics, Mahasarakham University, Mahasarakham, Thailand)

Description

The tritium is considered as one of main fuels for D-T nuclear fusion reactors, where it is planned to be produced from a blanket of reactors by using the interactions between 14.1 MeV neutrons from nuclear fusion reactions and lithium from the blankets. In this work, the simulations of the tritium production from mock-up breeding blanket due to interactions of neutrons and lithium in the blanket are carried out using the Monte Carlo N-Particle transport code (MCNP) version MCNPX. Four designs of mock-up breeding blanket, including a design with a pure natural lithium, a design with lithium titanate (Li2Ti03) based compound, a design with a compound based on a combination of a pure natural lithium and thorium, and a design with a compound based on a combination of lithium titanate and thorium. It is found that the production of tritium significantly increases with the inclusion of thorium, where an increase of tritium production with a factor of 2 can be achieved.

Primary author

Dr Siriyaporn Sangaroon (Department of Physics, Mahasarakham University, Mahasarakham, Thailand)

Co-authors

Ms Jiraporn Promping (Thailand Institute of Nuclear Technology (Public Organization), Bangkok, Thailand) Dr Roppon Picha (Thailand Institute of Nuclear Technology (Public Organization), Bangkok, Thailand) Dr Thawatchai Onjun (School of Manufacturing Systems and Mechanical Engineering, Sirindhorn International Institute of Technology, Thammasat University, Klongluang, Pathumthani, Thailand)

Presentation materials

There are no materials yet.