Reference
- Shirai, K., Itoh, C., Arai, T. and Saegusa, T. Integrity of Cast-Iron Cask Against Free Drop Test— Verification of Brittle Fracture Design Criterion. Int. J. Radioact. Mater. Transp. 4(1), 5–13 (1993).
- Katoh, Y., Hattori, S., Itoh, C., Shirai, K., Ozalci, S. and Katoh, O. Storage Cask Drop Test on Reinforced Concrete Slab. In: Proc. Int. Symp. on The Packaging and Transportation of Radioactive Materials, PATRAM '92, Yokohama. pp. 1721–1732 (1992).
- IAEA. Regulations for the Safety Transport of Radioactive Material Safety Series No. 6 (Vienna: International Atomic Energy Agency) (1985).
- Arai, T., Saegusa, T., Yagawa, G., Urabe, N. and Nickell, R. E. Determination of Lower-Bound Fracture Toughness for Hepvy-Section Ductile Cast Iron (DCI) and Estimation by Small Specimen Tests. In: Fracture Mechanics: 24th Symposium, ASTM STP 1207, (American Society for Testing and Materials) (to be published).
- Urabe, N. and Furuta, K. Is Ductile Cast Iron Ductile at —40°C? In: Proc. Int. Symp. on The Packaging and Transportation of Radioactive Materials, PATRAM '92, Yokohama. pp. 1189–1196 (1992).
- Urabe, N. and Harada Y. Fracture Toughness of Heavy Section Ductile Castings and Safety Assurance Method of DCI Casks. In: Proc. Int. Symp. on The Packaging and Transportation of Radioactive Materials, PATRAM '89, Washington, DC. CONF-890631 pp. 743–752 (1989).
- Irwin, G. R. Fracture Model Transition for a Crack Traversing a Plate. J. Basic Eng. 82, 417–425 (1960).
- Anderson, T. L. and Dodds Jr, R. H. Specimen Size Requirements for Fracture Toughness Testing in the Transition Region. J. Test. Eval. 19, 123–134 (1991).
- JSPS Test Standard (Draft). Evaluation of Elastic-Plastic Fracture Toughness Testing Procedure in the Transition Region. Japan Society for Promotion of Science (1992).
- Urabe, N. Statistical Studies on Fracture Toughness of Steels. In: Statistical Research on Fatigue and Fracture. Eds T. Tanaka, S. Nishijima and M. Ichikawa (The Society of Materials Science, Japan) pp. 105–123 (1987).
- Saegusa, T., Itoh, C., Shimamura, K. and Urabe, N. Application of IAEA TECDOC 717 to Packagings and Comparison with Reactor Vessel. In: Proc. 2nd Technical Seminar on Brittle Fracture Safety Assessment of Ductile Iron Containers for Shipping and Storage of Radioactive Materials (to be published).