References
- Aizawa, O. , et al., 1980. Nucl. Technol. 48 (1980), p. 150.
- Matsumoto, T. , et al., 1989. Pigment Cell Res. 2 (1989), p. 240.
- Takami, M. , et al., 1986. Bull. At. Energy Res. Lab., Musashi Inst. Technol. MITR-862 (1986), p. 152, [in Japanese].
- Aizawa, O. , 1994. “Reactor Physics and Reactor Computation” . 1994. p. 215, Ben-Gurion Univ. of Negev Press.
- 1986. Briesmeister, J. F. , ed. LA-7396-M . 1986, MCNP-A general Monte Carlo code for neutron and photon transport, Rev. 2.
- Jeraj, R. , et al., 1997. Nucl. Technol. 120 (1997), p. 179.
- Horiuchi, N. , et al., 1993. Proc. 10th European TRIGA User's Conf. (1993), pp. 7–24.
- MCNPDAT, 1994. MCNP, version 4, Standard neutron cross section data library based in part on ENDF/B-V , RSIC-DLC-105 (1994).
- Howerton, R. J. , et al., 1975. "The LLL evaluated nuclear data library (ENDL)". In: UCRL-50400 . Vol. 15. 1975, part A.
- Lamarsh, J. R. , 1976. “Introduction to Nuclear Reactor Theory” . Addison-Wesley Publ; 1976.