1 |
D.R. Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements, Technical Information Center, U.S. Department Energy. (1976)
|
2 |
H.C. Suk, et.al., ELESTRES.M11K Program Users' Manual and Description, KAERI/TR-320/92, Korea Atomic Energy Research Institute, (1992)
|
3 |
K.S. Sim, et.al., Modification of ELESTRES Code with New Database of Flux Depression across the Pellet Radius, KAERI/TR-485/94, Korea Atomic Energy Research Institute, (1994)
|
4 |
D. Vose, Quantitative Risk Analysis: A Guide Monte Carlo Simulation Method, John Wiley & Sons, New York, (1996)
|
5 |
I.E. Oldaker and M. Gacesa, Fuel Design Manual for CANDU 6 Reactor, DM-XX-37000-001, AECL, Canada (1989)
|
6 |
K.H. Kang, et al., 'The Thermal Conductivity of Simulated DUPIC Fuel,' J. Nucl. Sci. Tech., Suppl, 3, 776 (2002)
|
7 |
M.S. Yang, et al., 'Characteristics of DUPIC Fabrication Technology,' Proc. Int. Conf. Future Nuclear Systems: Challenge towards Second Nuclear Era with Advanced Fuel Cycles. Gobal' 97, p.535, 1997,Yokohama, Japan
|
8 |
C.J. Park, et al., 'Development of an Optimization Method for Fuel Design Parameters Using Sampling Techniques,' Proc. Korean Nuclear Society, Kyung-ju, Korea (2003).(CD-Rom)
|
9 |
K.C. Song, et al., Irradiation Tests and Performance Evaluation of DUPIC Fuel, KAERI/RR- 2236/2001, MOST, Korea (2001)
|
10 |
A. Saltelli, et.al., Sensitivity Analysis, John Wiley & Sons Ltd., (2000)
|
11 |
H.S. Park, et al.,' The DUPIC Fuel Cycle Alternatives: Status & Perspective,' Proceedings of the 10th PBNC, 1996, Kobe, Japan
|
12 |
Generation 4 Roadmap - Report of the Fuel Cycle Crosscut Group, DOE, FCCG Summary Rpt FR02-00, November 1, (2001)
|