| Autor: |
T. Yamamoto, Yuichi Ogawa, T. Amano, K. Takemura, Nobuyuki Inoue, Y. Asaoka, K. Tokimatsu, Kunihiko Okano, Y. Murakami, K. Tomabechi, Tomoaki Yoshida, Ryoji Hiwatari |
| Rok vydání: |
1998 |
| Předmět: |
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| Zdroj: |
Scopus-Elsevier |
| ISSN: |
0920-3796 |
| DOI: |
10.1016/s0920-3796(98)00169-0 |
| Popis: |
We designed a volumetric neutron source for testing large-scale blanket components, based on a steady-state tokamak device with superconducting coils. It is found that a neutron flux of approximately 1.0 MW m −2 is available in the medium-size device ( R =4.5 m, a =1.0 m, κ =1.8, I p =5.6 MA) under the conditions of H ∼2 and β N ∼3 with a neutral beam injection (NBI) power of about 60 MW. We demonstrate the controllability of the current profiles required for high-beta plasma up to β N =3–3.8 with the combination of bootstrap current and NB-driven current ( E b =1.0 MeV). If an advanced performance scenario such as a reversed shear configuration is available, a neutron flux of 1.4 MW m −2 is achievable. We install the breeding blanket of Li–Pb only at outboard and upper regions, and find that a local tritium breeding ratio (TBR) of 1.5 is achievable and a net TBR of 0.8 could be available. The analysis of shielding materials at the inboard region shows that the proper combination of tungsten, steel and boric water yields a reduction of the nuclear irradiation of TF coil by a factor of approximately 10. |
| Databáze: |
OpenAIRE |
| Externí odkaz: |
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Full Text from ScienceDirect