References
- H. Lee, G.-I. Park, K.-H. Kang, J.-M. Hur, J.-G. Kim, D.-H. Ahn, Y.-Z. Cho, E.H. Kim, Pyroprocessing technology developments at KAERI, Nucl. Eng. Technol. 43 (2011) 317-328. https://doi.org/10.5516/NET.2011.43.4.317
- H.L. Chang, F.X. Gao, W.I. Ko, H.D. Kim, S.Y. Lee, Evaluation of sigma-MUF (material unaccounted for) for the conceptually designed Korea advanced pyroprocess facility, J. Korean Phys. Soc. 59 (2011) 1418. https://doi.org/10.3938/jkps.59.1418
- C.G. Bathke, B.B. Ebbinghaus, B.A. Collins, B.W. Sleaford, K.R. Hase, M. Robel, R.K. Wallace, K.S. Bradley, J.R. Ireland, G.D. Jarvinen, M.W. Johnson, A.W. Prichard, B. Smith, The Attractiveness of materials in advanced nuclear fuel cycles for various proliferation and theft scenarios, Nucl. Technol. 179 (2012) 5-30, https://doi.org/10.13182/NT10-203.
- P.C. Durst, R. Wallace, I. Therios, M.H. Ehinger, R. Bean, D.N. Kovacic, A. Dougan, K. Tolk, B. Boyer, Advanced Safeguards Approaches for New Reprocessing Facilities, 2007.
- N. Miura, H.O. Menlove, The Use of Curium Neutrons to Verify Plutonium in Spent Fuel and Reprocessing Wastes, LA-12774-MS, 1994.
- B. Han, H. Shin, H. Kim, Analysis of measurement uncertainty of material unaccounted for in the reference pyroprocessing facility, Nucl. Technol. 182 (2013).
- M. Gonzalez, L. Hansen, D. Rappleye, R. Cumberland, M.F. Simpson, Application of a one-dimensional transient electrorefiner model to predict partitioning of plutonium from curium in a pyrochemical spent fuel treatment process, Nucl. Technol. 192 (2015) 165-171, https://doi.org/10.13182/NT15-28.
- P.M. Rinard, H.O. Menlove, Application of Curium Measurements for Safeguarding at Reprocessing Plants, LA-13134-MS, 1996.
- J.G. Richard, M.L. Fensin, S.J. Tobin, M.T. Swinhoe, J. Baciak, H.O. Menlove, Characterization of the neutron source term and multiplicity of a spent fuel assembly in support of NDA safeguards of spent nuclear fuel, in: INMM 51st Annu. Meet., 2010.
- T.H. Lee, H.D. Kim, J.S. Yoon, S.Y. Lee, M. Swinhoe, H.O. Menlove, Preliminary calibration of the ACP safeguards neutron counter, Nucl. Instruments Methods Phys. Res. Sect. A Accel. Spectrometers, Detect. Assoc. Equip 580 (2007) 1423-1427, https://doi.org/10.1016/j.nima.2007.07.142.
- T.H. Lee, H.O. Menlove, S.Y. Lee, H.D. Kim, Development of the ACP safeguards neutron counter for PWR spent fuel rods, Nucl. Instruments Methods Phys. Res. Sect. A. 589 (2008) 57-65, https://doi.org/10.1016/j.nima.2008.02.054.
- T.H. Lee, H.D. Kim, Application of a self-multiplication correction method to a neutron coincidence counter and its calibration for spent fuel, IEEE Trans. Nucl. Sci. 56 (2009) 2791-2795, https://doi.org/10.1109/TNS.2009.2021427.
- T.H. Lee, Y.S. Kim, H.-S. Shin, H.-D. Kim, Hot-Test results of the advanced spent fuel conditioning process safeguards neutron counter for PWR spent fuel rods, Nucl. Technol. 176 (2011) 147-154, https://doi.org/10.13182/NT11-A12549.
- R.A. Borrelli, Use of curium spontaneous fission neutrons for safeguardability of remotely-handled nuclear facilities: fuel fabrication in pyroprocessing, Nucl. Eng. Des. 260 (2013) 64-77, https://doi.org/10.1016/j.nucengdes.2013.03.025.
- M.L. Fensin, S.J. Tobin, N.P. Sandoval, M.T. Swinhoe, S.J. Thompson, A Monte Carlo linked depletion spent fuel library for assessing varied nondestructive assay techniques for nuclear safeguards, in: Adv. Nucl. Fuel Manag. IV, 2009. LaGrange Park, IL, USA.
- M.A. Wincek, K.B. Stewart, G.F. Piepel, Statistical Methods for Evaluating Sequential Material Balance Data, NUREG/CR-0683, PNL-2920, 1979.
- J. Leppanen, SERPENT - a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code, 2015, pp. 1-164 papers3://publication/uuid/2623C65B-C2F6-4095-8781-0298F0-93FDF.
- J.J. Duderstadt, L.J. Hamilton, Nuclear Reactor Analysis, JOHN WILEY & SONS, 2012.
- C.Y. Lee, C.H. Shin, W.K. In, Pressure drop in dual-cooled annular and cylindrical solid fuel assemblies for pressurized water reactor, Nucl. Eng. Des. 250 (2012) 287-293. https://doi.org/10.1016/j.nucengdes.2012.05.039
- H. Yu, Low-Boron OPR1000 Core Based on the BigT Burnable Absorber, KAIST, 2014.
- H. Yu, M.S. Yahya, Y. Kim, A reduced-boron OPR1000 core based on the BigT burnable absorber, Nucl. Eng. Technol. 48 (2016) 318-329, https://doi.org/10.1016/j.net.2015.12.010.
- M.A. Williamson, J.L. Willit, Pyroprocessing flowsheets for recycling used nuclear fuel, Nucl. Eng. Technol. 43 (2011) 329-334, https://doi.org/10.5516/NET.2011.43.4.329.
- IAEA, Status of the Treatment of Irradiated LWR Fuel, IAEA-Tecdoc-333, 1985.
- Y. Kim, K. Kim, J. Jung, B. Park, J. Yoon, H. Lee, Design of remotely operated voloxidizer for hot-cell application, in: IEEE Int. Symp. Assem. Manuf., Suwon, Korea, 2009, pp. 393-397.
- Y.H. Kim, H.J. Lee, J.K. Lee, J.H. Jung, B.S. Park, J.S. Yoon, S.W. Park, Engineering design of a high-capacity vol-oxidizer for handling UO2 pellets of tens of kilogram, J. Nucl. Sci. Technol. 45 (2008) 617-624. https://doi.org/10.3327/jnst.45.617
- S. Jeon, J. Lee, J. Lee, S. Kang, K. Lee, Y. Cho, D. Ahn, K. Song, Fabrication of UO2 porous pellets on a scale of 30 kg-U/batch at the PRIDE facility, Adv. Mater. Sci. Eng. 2015 (2015).
- J. Hayya, D. Armstrong, N. Gressis, A note on the ratio of two normally distributed variables, Manage. Sci. 21 (1975) 1338-1341, https://doi.org/10.1287/mnsc.21.11.1338.
- N. Ensslin, W.C. Harker, M.S. Krick, D.G. Langner, M.M. Pickrell, J.E. Stewart, Application Guide to Neutron Multiplicity Counting, LA-13422-M, 1998.
- A. Glaser, M. Miller, Estimating plutonium production at Israel's Dimona reactor, Aerosp. Eng. (n.d.) 1-10.
- J.H. Yoo, C.S. Seo, E.H. Kim, H.S. Lee, A conceptual study of pyroprocessing for recovering actinides from spent oxide fuels, Nucl. Eng. Technol. 40 (2008) 581-592. https://doi.org/10.5516/NET.2008.40.7.581
- S.K. Kim, W.I. Ko, S.R. Youn, R. Gao, Cost analysis of a commercial pyroprocess facility on the basis of a conceptual design in Korea, Ann. Nucl. Energy 80 (2015) 28-39, https://doi.org/10.1016/j.anucene.2015.01.011.
- IAEA (International Atomic Energy Agency), IAEA Safeguards Glossary 2001 Edition, International Atomic Energy Agency, 2001.
Cited by
- Evaluation of nuclear material accountability by the probability of detection for loss of Pu (LOPu) scenarios in pyroprocessing vol.51, pp.1, 2018, https://doi.org/10.1016/j.net.2018.08.015
- Review of Candidate Techniques for Material Accountancy Measurements in Electrochemical Separations Facilities vol.206, pp.12, 2018, https://doi.org/10.1080/00295450.2020.1724728