6. Simnad MT (1981) The U-ZrHx alloy: its properties and use in TRIGA fuel. Nucl Eng Des
64:4033–4422
7. Konashi K, Itoh K, Kido T, Kosaka Y, Seino S (2013) Development of hydride neutron
absorber for fast reactor: irradiation experiment on hydride neutron absorber in BOR-60. In:
Proceedings of ICAPP 2013, Jeju Island, April 14–18, 2013, paper FF232
8. Olander D, Konashi K, Yamawaki M (2012) 3.12 Uranium-zirconium hydride fuel. In:
Comprehensive nuclear materials, Elsevier, pp 314–357
9. Nagaya Y, Mori T, Okumura K, Nakagawa M (2005) MVP/GMVP version 2: general purpose
Monte Carlo Codes for neutron and photon transport calculations based on continuous energy
and multigroup methods. JAERI 1348
10. Okumura K, Nakagawa M, Kaneko K (1997) Development of burn-up calculation code system
MVP-BURN based on continuous energy Monte Carlo method and its validation (M&C and
SNA 97), vol 1. Saratoga Springs
178
K. Konashi and T. Yokoyama
64:4033–4422
7. Konashi K, Itoh K, Kido T, Kosaka Y, Seino S (2013) Development of hydride neutron
absorber for fast reactor: irradiation experiment on hydride neutron absorber in BOR-60. In:
Proceedings of ICAPP 2013, Jeju Island, April 14–18, 2013, paper FF232
8. Olander D, Konashi K, Yamawaki M (2012) 3.12 Uranium-zirconium hydride fuel. In:
Comprehensive nuclear materials, Elsevier, pp 314–357
9. Nagaya Y, Mori T, Okumura K, Nakagawa M (2005) MVP/GMVP version 2: general purpose
Monte Carlo Codes for neutron and photon transport calculations based on continuous energy
and multigroup methods. JAERI 1348
10. Okumura K, Nakagawa M, Kaneko K (1997) Development of burn-up calculation code system
MVP-BURN based on continuous energy Monte Carlo method and its validation (M&C and
SNA 97), vol 1. Saratoga Springs
178
K. Konashi and T. Yokoyama