1 |
IAEA Safety Standards Series (Safety Guide NS-G-4.3), 2008a, "Core Management and Fuel Handling for Research Reactors", IAEA Safety Standards Series for protecting people and the environment, International Atomic Energy Agency, Vienna.
|
2 |
IAEA Safety Standards Series (Safety Guide NS-G-4.4), 2008b, "Operational Limits and Conditions and Operating Procedures for Research Reactors", IAEA Safety Standards Series for protecting people and the environment, International Atomic Energy Agency, Vienna.
|
3 |
IAEA Technical Document (IAEA TECDOC-643), 1992, "Research reactor core conversion guidebook", IAEA TECDOC-643, International Atomic Energy Ageny ,Vienna.
|
4 |
W IMSD4 code Manual, 1991. Winfrith Improved Multigroup Scheme Code system. Radiation safety Information Computational Center, Oak Ridge National Laboratory, Oak Ridge.
|
5 |
C ITATION code Manual, 1999, Nuclear Reactor core Analysis Code System, Radiation safety Information computational center, Oak Ridge National Laboratory, Oak Ridge.
|
6 |
IAEA Technical Report (455), 2007, "Utilization Related Design Features of Research reactors: A Compendium", Series No. 455, International Atomic Energy Agency, Vienna.
|
7 |
D. Bodansky, Nuclear Energy: Principles, Practices, and Prospects (Springer, 2004).
|
8 |
R.C. BANNERMAN, "Control Rod Interaction Models for Use in 2D and 3D Reactor Geometries", AEEW- R-1409, Winfrith UKAEA, England, (1985).
|
9 |
IAEA Technical Document (IAEA TECDOC-233), 1980, "Research reactor core conversion from the use the of highly enriched uranium to the use of low enriched uranium fuels", IAEA TECDOC-233, Inter national Atomic Energy Agency, Vienna.
|