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Design and Techniques for Fusion Blanket Neutronics Experiments Using an Accelerator-Based Deuterium-Tritium Neutron Source

Y. Oyama, C. Konno, Y. Ikeda, F. Maekawa, H. Maekawa, S. Yamaguchi, K. Tsuda, T. Nakamura, M. A. Abdou, E. F. Bennett, R. F. Mattas, K. G. Porges, M. Z. Youssef

Fusion Science and Technology / Volume 28 / Number 1 / August 1995 / Pages 56-73

Technical Paper / Fusion Neutronics Integral Experiments — Part I / Blanket Engineering / dx.doi.org/10.13182/FST95-A30401

The experiments performed in the Japan Atomic Energy Research Institute/U.S. Department of Energy collaborative program on fusion blanket neutronics are designed with consideration of geometrical and material configurations. The general guide that is used to design the engineering-oriented neutronics experiment, which uses an accelerator-based 14-MeV neutron source, is discussed and compared with neutronics characteristics of the reactor models. Preparation of the experimental assembly, blanket materials, and the neutron source is described. A variety of techniques for measuring the nuclear parameters such as the tritium production rate are developed or introduced through the collaboration as a basis of the neutronics experiments. The features of these techniques are discussed with the experimental error and compared with each other.