Z. Ghani A. Turner S. Mangham J. Naish M. Lis L. Packer M. Loughlin
Extensive neutronics and 3-D activation simulations were carried out to assess the levels of radiation throughout the ITER tokamak complex. The simulated radiation sources included DT fusion neutrons exiting the cryostat and gamma rays arising from the activation of cooling water, activated pipe chases and cask transfers. Resultant biological dos…
Preprint PublishedA. Turner R. Pampin M.J. Loughlin Z. Ghani G. Hurst A. Lo Bue S. Mangham A. Puiu S. Zheng
The In-Vessel Viewing System (IVVS) units proposed for ITER are deployed to perform in-vessel examination. During plasma operations, the IVVS is located beyond the vacuum vessel, with shielding blocks envisaged to protect components from neutron damage and reduce shutdown dose rate (SDR) levels. Analyses were conducted to determine the effectivenes…
PublishedS. Zheng R. Pampin S. Lilley B. C. Na M. J. Loughlin N. P. Taylor V. Barabash
The scope, methodology, and preliminary results are presented of a series of neutron transport and activation analyses aimed at updating the ITER radioactive inventory assessment and assisting the waste management planning. Calculations are performed using stateof-the-art three-dimensional models, codes, and data libraries and thereby overcoming ea…
PublishedR. Pampin M.J. Loughlin M.J. Walsh
Systematic analysis of the radiation fields throughout the ITER core LIDAR diagnostic system were performed to support the design optimisation and assessment process, aiming at achieving the required performance in terms of reliability, occupational safety and interface with neighboring systems. Neutron, photon, nuclear heat and material activation…
PublishedM. J. Walsh M. Beurskens P. G. Carolan M. Gilbert M. Loughlin Et Al
The maximum temperature expected in ITER is in the region of 40 keV and the minimum average density of approximately 310 19 m -3 is also expected. The proven capability, convenience, and port occupancy of the LIDAR Thomson scattering approach, demonstrated on JET, makes it an excellent candidate for ITER. Nonetheless, there are formidable design ch…
PublishedK. G. McClements
A full orbit code is used to compute collisionless losses of fusion particles from three proposed burning plasma tokamaks: the International Tokamak Experimental Reactor ITER; a spherical tokamak power plant (STPP) [T. C. Hender, A. Bond, J. Edwards, P. J. Karditsas, K. G. McClements, J. Mustoe, D. V. Sherwood, G. M. Voss, and H. R. Wilson, Fusion …
Published