1. ASME Boiler and Pressure Vessel Code Sec. III., Div.1, 2001. Rules for Construction of Nuclear Facility Components-Class 1 Components, 2001 ed.
2. Fowler, T.B., Vondy, D.R., Cunningham, 1971. Nuclear Reactor Core Analysis Code CITATION, ORNL-TM-2496. Oak Ridge National Laboratory.
3. Fujimoto, N., Yamashita, K., 1999. Improvement of Core Calculation Model of High Temperature Engineering Test Reactor, JAERI-Research 99-059. Japan Atomic Energy Research Institute (in Japanese).
4. Fujimoto, N., Nakano, M., Nojiri, N., Takeuchi, S., Fujisaki, K., Yamashita, K., 1999. First criticality prediction of the HTTR by 1/M interposition method. In: Proceedings of the Sixth Asian Symposium on Research Reactors, Oarai Research Establishment, Japan, March 29–31, pp. 328–333.
5. Imgrund, M.C., 1992. ANSYS® Verification Manual. Swanson Analysis Systems, Inc.