Monte Carlo analysis of the effects of a blanket-shield penetration on the performance of a tokamak fusion reactor [electronic resource].
- Washington, D.C : United States. Energy Research and Development Administration, 1977.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 19 : digital, PDF file
- Additional Creators:
- Oak Ridge National Laboratory
United States. Energy Research and Development Administration
United States. Department of Energy. Office of Scientific and Technical Information
- Adjoint Monte Carlo calculations have been carried out using the three-dimensional radiation transport code, MORSE, to estimate the nuclear heating and radiation damage in the toroidal field (TF) coils adjacent to a 28 x 68 cm/sup 2/ rectangular neutral beam injector duct that passes through the blanket and shield of a D-T burning Tokamak reactor. The plasma region, blanket, shield, and TF coils were represented in cylindrical geometry using the same dimensions and compositions as those of the Experimental Power Reactor. The radiation transport was accomplished using coupled 35-group neutron, 21-group gamma-ray cross sections obtained by collapsing the DLC-37 cross-section library. Nuclear heating and radiation damage rates were estimated using the latest available nuclear response functions. The presence of the neutral beam injector duct leads to increases in the nuclear heating rates in the TF coils ranging from a factor of 3 to a factor of 196 depending on the location. Increases in the radiation damage also result in the TF coils. The atomic displacement rates increase from factors of 2 to 138 and the hydrogen and helium gas production rates increase from factors of 11 to 7600 and from 15 to 9700, respectively.
- Published through SciTech Connect.
Santoro, R. T.; Tang, J. S.; Alsmiller, Jr., R. G.; Barnes, J. M.
- Funding Information:
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