참고문헌
- Nuclear Safety and Security Commission, Nuclear safety information center. http://nsic.nssc.go.kr.
- H. Lee, G.I. Park, J.W. Lee, et al., Current status of pyroprocessing development at KAERI, Sci. Technol. Nucl. Install. 2013 (2013) 343492.
- J.P. Ackerman, Chemical basis for pyrochemical reprocessing of nuclear fuel, I&EC Res. 30 (1991) 141-145.
- J.J. Laidler, J.E. Battles, W.E. Miller, J.P. Ackerman, E.L. Carls, Development of pyroprocessing technology, Prog. Nucl. Energy 31 (1997) 131-140. https://doi.org/10.1016/0149-1970(96)00007-8
- S.X. Li, S.D. Herrmann, K.M. Goff, M.F. Simpson, R.W. Benedict, Actinide recovery experiments with bench-scale liquid cadmium cathode in real fission product-laden molten salt, Nucl. Technol. 165 (2009) 190-199.
- M.F. Simpson, Developments of Spent Nuclear Fuel Pyroprocessing Technology at Idaho National Laboratory, Idaho Natl. Lab., 2012, pp. 1-21. INL/EXT-12-25124.
- International Atomic Energy Agency, The Structure and Content of Agreements between the Agency and States Required in Connection with the Treaty on the Non-proliferation of Nuclear Weapons, INFCIRC/153, 1972 (Corrected).
- P.C. Durst, I. Therios, R. Bean, A. Dougan, B.D. Boyer, R. Wallace, M. Ehinger, D. Kovacic, L. Tolk, Advanced Safeguards Approaches for New Reprocessing Facilities, Pacific Northwest Natl. Lab., 2007. PNNL-16674.
- H. Seo, B.H. Won, S.K. Ahn, S.K. Lee, S.H. Park, G.I. Park, S.H. Menlove, Optimization of hybrid-type instrumentation for Pu accountancy of U/TRU ingot in pyroprocessing, Appl. Radiat. Isot. 108 (2016) 16-23. https://doi.org/10.1016/j.apradiso.2015.11.109
- H. Seo, S.K. Lee, S.J. An, S.H. Park, J.H. Ku, H.O. Menlove, C.D. Rael, A.M. LaFleur, M.C. Browne, Development of prototype induced-fission-based Pu accountancy instrument for safeguards applications, Appl. Radiat. Isot. 115 (2016) 67-73. https://doi.org/10.1016/j.apradiso.2016.06.011
- H.O. Menlove, S.H. Menlove, C.D. Rael, The development of a new, neutron, time correlated, interrogation method for measurement of 235U content in LWR fuel assemblies, Nucl. Instrum. Methods 701 (2013) 72-79.
- J.S. Beaumont, T.H. Lee, M. Mayorov, C. Tintori, F. Rogo, B. Angelucci, M. Corbo, A fast-neutron coincidence collar using liquid scintillators for fresh fuel verification, J. Radioanal. Nucl. Chem. 314 (2017) 803-812.
- H.O. Menlove, A. Belian, W. Geist, C. Rael, A new method to measure the U- 235 content in fresh LWR fuel assemblies via fast-neutron passive selfinterrogation, Nucl. Instrum. Methods 877 (2018) 238-245.
- S.J. Tobin, H.O. Menlove, M.T. Swinhoe, M.A. Schear, Next Generation Safeguards Initiative research to determine the Pu mass in spent fuel assemblies: purpose, approach, constraints, implementation, and calibration, Nucl. Instrum. Methods 652 (2011) 73-75.
- J. Eigenbrodt, Spent fuel measurements: passive neutron albedo reactivity (PNAR) and photon signatures, Ph.D. Dissertation, in: Nuclear Engineering, Texas A&M University, College Station, TX, 2016.
- D. Henzlova, H.O. Menlove, C.D. Rael, H.R. Trellue, S.J. Tobin, S.H. Park, J.M. Oh, S.K. Lee, S.K. Ahn, I.C. Kwon, H.D. Kim, Californium interrogation prompt neutron (CIPN) instrument for non-destructive assay of spent nuclear fuelddesign concept and experimental demonstration, Nucl. Instrum. Methods 806 (2016) 43-54.
- A.M. Lafleur, W.S. Charlton, H.O. Menlove, M.T. Swinhoe, A.R. Lebrun, Development of self-interrogation neutron resonance Densitometry to improve detection of possible diversions for PWR spent fuel assemblies, Nucl. Technol. 181 (2013) 354-370.
- A.C. Kaplan, V. Henzl, H.O. Menlove, M.T. Swinhoe, A.P. Belian, M. Flaska, S.A. Pozzi, Determination of spent nuclear fuel assembly multiplication with the differential die-away self-interrogation instrument, Nucl. Instrum. Methods 757 (2014) 20-27.
- T. Martinik, V. Henzl, S. Grape, P. Jansson, M.T. Swinhoe, A.V. Goodsell, S.T. Tobin, Design of a prototype differential die-away instrument proposed for Swedish spent nuclear fuel characterization, Nucl. Instrum. Methods 821 (2016) 55-65.
- S.T. Tobin, P. Jansson, Nondestructive Assay Options for Spent Fuel Encapsulation, Swedish Nuclear Fuel and Waste Management Co., 2013. TR-13-30.
- D.B. Pelowitz (Ed.), MCNP6 User's Manual Version 1.0, Los Alamos Natl. Lab., 2013. LA-CP-13-00634.
- A.M. LaFleur, S.K. Ahn, H.O. Menlove, M.C. Browne, H.D. Kim, Characterization and performance evaluation of a new passive neutron albedo reactivity counter for safeguards measurements, Radiat. Meas. 61 (2014) 83-93. https://doi.org/10.1016/j.radmeas.2013.12.012
- Victrex plc. http://www.victrex.com.
- I.C. Gauld, S.M. Bowman, J.E. Horwedel, ORIGEN-ARP: Automatic Rapid Processing for Spent Fuel Depletion, Decay, and Source Term Analysis, Oak Ridge Natl. Lab., 2014. ORNL/NUREG/CSD-2/V1/R7.H.