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Batistoni, P.*; Angelone, M.*; Carconi, P.*; Fischer, U.*; Fleischer, K.*; Kondo, Keitaro; Klix, A.*; Kodeli, I.*; Leichtle, D.*; Petrizzi, L.*; et al.
Fusion Engineering and Design, 85(7-9), p.1675 - 1680, 2010/12
Times Cited Count：31 Percentile：88.56(Nuclear Science & Technology)The EU is developing two test blanket modules (TBM), the Helium Cooled Pebble Bed (HCPB) and the Helium Cooled Lithium Lead (HCLL), which will be tested in ITER. Here neutronics experiments with a mockup for HCLL TBM were carried out. Detail distributions of the tritium production rate inside the mockup were measured with various methods. A lithium diamond detector developed as a neutron monitor for fusion devices has also been used as a tritium detector. Activation reaction rates inside the mockup were also measured. These measured data agreed with calculation results buy using MCNP and FENDL-2.1 within 10%, which demonstrated that the prediction accuracy was high. Sensitivity and uncertainty analyses suggested that the uncertainty of the tritium production rate from the nuclear data uncertainty was small, usually below 2%.
Loughlin, M. J.*; Batistoni, P.*; Konno, Chikara; Fischer, U.*; Iida, Hiromasa; Petrizzi, L.*; Polunovskiy, E.*; Sawan, M.*; Wilson, P.*; Wu, Y.*
Fusion Science and Technology, 56(2), p.566 - 572, 2009/08
Times Cited Count：42 Percentile：92.56(Nuclear Science & Technology)It is envisaged that ITER should produce as much as 700 MW of fusion power. This equates to the production of 2.48
10
14MeV neutrons/s which will give an uncollided flux at the first wall of approximately 410
n/cm
/s and a total with the addition of the collided to some 10
n/cm/s. ITER is therefore a significant nuclear facility and it is essential that an efficient and coherent strategy for nuclear analysis is in place. This paper reviews the status of the methods applied to date and recommends the future strategy which ITER should adopt to address the continuing requirements and responsibilities. This is done by consideration of the application of radiation transport codes, the creation of suitable models, developments in information technology, and the management tools which will be required. Areas in which new codes and techniques need to be developed will be identified.
Matsukawa, Makoto; Kikuchi, Mitsuru; Fujii, Tsuneyuki; Fujita, Takaaki; Hayashi, Takao; Higashijima, Satoru; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Ide, Shunsuke; Ishida, Shinichi; et al.
Fusion Engineering and Design, 83(7-9), p.795 - 803, 2008/12
Times Cited Count：17 Percentile：72.86(Nuclear Science & Technology)no abstracts in English
Zani, L.*; Pizzuto, A.*; Semeraro, L.*; Ciazynski, D.*; Cucchiaro, A.*; Decool, P.*; della Corte, A.*; Di Zenobio, A.*; Dolgetta, N.*; Duchateau, J. L.*; et al.
IEEE Transactions on Applied Superconductivity, 18(2), p.216 - 219, 2008/06
Times Cited Count：4 Percentile：30.89(Engineering, Electrical & Electronic)The upgrade of JT-60U to JT-60 Super Advanced (JT-60SA), a fully superconducting tokamak, will be performed in the framework of the Broader Approach (BA) agreement between Europe (EU) and Japan. In particular, the Toroidal Field (TF) system, which includes 18 coils, is foreseen to be procured by France, Italy and Germany. This work covers activities from design and manufacturing to shipping to Japan. The present paper is mainly devoted to the analyses that lead to the conductor design and to the technical specifications of the joints for the JT-60SA TF coils. The conductor geometry is described, which is derived from Cable-In-Conduit concept and adapted to the actual JT-60SA tokamak operating conditions, principally the ITER-like scenario. The reported simulations and calculations are particularly dealing with the stability analysis and the power deposition during normal and off-normal conditions (AC losses, nuclear heating). The final conductor solution was selected through a trade-off between scientific approach and industrial technical orientation. Besides, the TF system connections layout is shown, derived from the industrially assessed twin-box concept, together with the associated thermo-hydraulic calculations ensuring a proper temperature margin.
Iida, Hiromasa; Petrizzi, L.*; Khripunov, V.*; Federici, G.*; Polunovskiy, E.*
Fusion Engineering and Design, 75(1-4), p.133 - 139, 2005/11
The design of the ITER machine was presented in 2001. A nuclear analysis has been performed on ITER by means of the most detailed models and the best assessed nuclear data and codes. As the construction phase of ITER is approaching, the design of the main components has been optimized/finalized and several minor design changes/optimizations have been made, which required refined calculations to confirm that nuclear design requirements are met. Some of the proposed design changes have been made to mitigate critical radiation shielding problems. This paper reviews some of the most recent neutronic work with emphasis on critical nuclear responses in the TF coil inboard legs and vacuum vessel related to design modifications made to the blanket modules and vacuum vessel.
