1. Development of a Fast Breeder Reactor Fuel Bundle-Duct Interaction Analysis Code—BAMBOO: Analysis Model and Validation by the Out-of-Pile Compression Test
2. Ohshima, H. and Ninokata, H. “Thermal-hydraulic analysis of fast reactor fuel subassembly with porous blockages,”. Proc. 4th Int. Semin. on Subchannel Analysis (ISSCA-4). Tokyo. pp.323–333.
3. Development of a Fast Breeder Reactor Fuel Bundle Deformation Analysis Code - BAMBOO: Development of a Pin Dispersion Model and Verification by the Out-of-Pile Compression Test
4. Seran, J. L., Touron, H., Maillard, A., Dubuisson, P., Hugot, J. P., Le Boulbin, E., Blanchard, P. and Pelletier, M. 1990.The Swelling Behavior of Titanium Stabilized Austenitic Steels Used as Structural Materials of Fissile Subassemblies in Phenix739–752. ASTM STP1046
5. Seran, J. L., Levy, V., Dubuisson, P., Gilbon, D., Maillard, A., Fissolo, A., Touron, H., Cauvin, R., Chalony, A. and Le Boulbin, E. 1992.Behavior under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phenix Fuel Subassembly1209–1233. ASTM STP1125