References
- Nuclear Power Generation Department, Safety Evaluation for a Startup Operation without Neutron Source of Kori Unit 1, Korea Electric Power Company, LTD, 1998.
- J.S. Chung, I.T. Woo, The Nuclear Design Report for Ulchin Nuclear Power Plant Unit 3 Cycle 7, Korea Nuclear Fuel Company, 2005. KNF-U3C7-05026 Rev.0.
- W. Bojduj, Source Range Detector Response during Boron Dilution Accident at Shutdown, American Nuclear Society: 2010 Annual Meeting, San Diego (CA), 2010, pp. 517-518.
- Y.A. Chao, H.Q. Lam, J.D. Gibbons, M.D. Heibel, M. Kauchi, The Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical Reactivity Measurement, American Nuclear Society: 2004 Annual Meeting, Washington, D.C., 2004, pp. 728-730.
- C.A. Ford, Modeling a Source Range Channel Response during a PWR Core Onload Sequence, American Nuclear Society: 2010 Annual Meeting, San Diego (CA), 2010, pp. 639-641.
- United States Nuclear Regulatory Commission, Information Notice No. 93-32: Non-conservative Inputs for Boron Dilution Event Analysis, IN-93-32, 1993.
- United States Nuclear Regulatory Commission, Generic Letter No. 85-05: Inadvertent Boron Dilution Events, GL-85-05, 1985.
- S. Goluoglu, L.M. Petrie Jr., M.E. Dunn, D.F. Hollenbach, B.T. Rearden, Monte Carlo criticality methods and analysis capabilities in SCALE, Nucl. Technol. 174 (2010) 214-235.
- S.M. Bowman, SCALE 6: comprehensive nuclear safety analysis code system, Nucl. Technol. 174 (2010) 126-148.
- D.E. Peplow, Monte Carlo shielding analysis capabilities with MAVRIC, Nucl. Technol. 174 (2010) 289-313.
- H. Nifenecker, S. David, J.M. Loiseaux, O. Meplan, Basics of accelerator driven subcritical reactors, Nucl. Instr. Meth. Phys. Res. A 463 (2001) 428-467. https://doi.org/10.1016/S0168-9002(01)00160-7
- P. Seltborg, Source efficiency and high-energy neutronics in accelerator-driven systems, Ph.D. Thesis, Department of Nuclear and Reactor Physics Royal Institute of Technology Stockholm, Sweden, 2005.
- G.I. Bell, S. Glasstone, Nuclear Reactor Theory, Van Nostrand Reinhold Company, New York, 1970.
- K.O. Ott, R.J. Neuhold, Nuclear Reactor Dynamics, American Nuclear Society, Le Grange Park (IL), 1985.
- Y. Kim, W.S. Park, C.K. Park, Characterization of a source importance function in an accelerator-driven system, Nucl. Sci. Eng. 144 (2003) 227-241. https://doi.org/10.13182/NSE03-A2356
- J.G. Ahn, N.Z. Cho, J.E. Kuh, Generation of spatial weighting functions for ex-core detectors by adjoint transport calculation, Nucl. Technol. 103 (1993) 114-121. https://doi.org/10.13182/NT93-A34834
- Scale: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, 2011. ORNL/TM-2005/39, Version 6.1. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-785.
- S.M. Bowman, O.W. Hermann, M.C. Brady, SCALE-4 Analysis of Pressurized Water Reactor Critical, Oak Ridge National Laboratory, Oak Ridge (TN), ORNL/TM-12294/V2, 1995.
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