1. JENDL-4.0: A New Library for Nuclear Science and Engineering
2. Development of comprehensive and versatile framework for reactor analysis, MARBLE
3. Okumura K., Kugo T., et al, “SRAC2006: A Comprehensive Neutronics Calculation Code System”, JAEA-Data/Code 2007–004 (2007)
4. Okumura K., “MOSRA-SRAC; Lattice calculation module of the modular code system for nuclear reactor analyses MOSRA”, JAEA-Data/Code, 2015–015 (2015)
5. Nagaya Y., Okumura K., et al, “MVP/GMVP II: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods”, JAERI-1348 (2004)