Author:
Koohi-Fayegh R.,Abad Miri Hakim,Green S.,Scott M.C.
Subject
Nuclear Energy and Engineering
Reference18 articles.
1. Briesmeister, J.F. (Ed.), 1986. MCNP — A General Monte Carlo Code for Neutron and Photon Transport. LA-7396 - M, Los Alamos National Laboratory.
2. Beryllium as the plasma-facing material in fusion energy systems — experiments, evaluation and comparison with alternative materials;Conn;Fusion Engineering and Design,1997
3. Field, G.M., Beynon, T.D., Grupelaar, H., 1991. Modelling inelastic emission cross sections for 9Be(n, 2n). In: Qaim, S.M. (Ed.), Proceedings of the International Conference on Nuclear Data for Science and Technology. Springer–Verlag.
4. FENDL data testing for beryllium, lead, iron and copper;Fischer;Fusion Engineering & Design,1995
5. Measuring the neutron yield from T(d,n)4He;Gaiser;Nuclear Instruments and Methods,1980
Cited by
3 articles.
订阅此论文施引文献
订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献