Browse > Article
http://dx.doi.org/10.7733/jnfcwt.2019.17.3.279

Recent Progress in Waste Treatment Technology for Pyroprocessing at KAERI  

Park, Geun-Il (Korea Atomic Energy Research Institute)
Jeon, Min Ku (Korea Atomic Energy Research Institute)
Choi, Jung-Hoon (Korea Atomic Energy Research Institute)
Lee, Ki-Rak (Korea Atomic Energy Research Institute)
Han, Seung Youb (Korea Atomic Energy Research Institute)
Kim, In Tae (Korea Atomic Energy Research Institute)
Cho, Yung-Zun (Korea Atomic Energy Research Institute)
Park, Hwan-Seo (Korea Atomic Energy Research Institute)
Publication Information
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) / v.17, no.3, 2019 , pp. 279-298 More about this Journal
Abstract
This study comprehensively addresses recent progress at KAERI in waste treatment technology to cope with waste produced by pyroprocessing, which is used to effectively manage spent fuel. The goal of pyroprocessing waste treatment is to reduce final waste volume, fabricate durable waste forms suitable for disposal, and ensure safe packaging and storage. KAERI employs grouping of fission products recovered from process streams and immobilizes them in separate waste forms, resulting in product recycling and waste volume minimization. Novel aspects of KAERI approach include high temperature treatment of spent oxide fuel for the fabrication of feed materials for the oxide reduction process, and fission product concentration or separation from LiCl or LiCl-KCl salt streams for salt recycling and higher fission-product loading in the final waste form. Based on laboratory-scale tests, an engineering-scale process test is in progress to obtain information on the performance of scale-up processes at KAERI.
Keywords
Spent PWR Fuel; Pyroprocessing; Filter waste; Salt waste; Metal waste;
Citations & Related Records
연도 인용수 순위
  • Reference
1 J.H. Choi, I.H. Cho, H.C. Eun, H.S. Park, Y. Z. CHO, K.R Lee, G.I. Park, S.H. Kim, C.H. Shin, and J.K. Kim, "Fabrication and Physical Properties of Lanthanide Oxide Glass Waste Form for the Immobilization of Lanthanide Oxide Wastes Generated from yrochemical Process", J. Radioanal. Nucl. Chem., 299, 1731-1738 (2014).   DOI
2 K.H. Kang, C.H. Lee, M.K. Jeon, and G.I. Park. Treatment Technology of Hull Wastes, Korea Atomic Energy Research Institute Report, KAERI/TR-5288/2013 (2013).
3 D.M. Strachan, J.V. Crum, M.R. Zumhoff, C.C. Bovaird, C.F. Windisch, Jr., and B.J. Riley, "Epsilon Metal Summary Report Fiscal Year 2011", FCRD-WAST-2011-000389, Pacific Northwest National Laboratory, Richland, WA. (2011).
4 M.F. Simpson, "Development of Spent Nuclear Fuel Pyroprocessing Technology at Idaho National Laboratory", INL/EXT-12-25124, Idaho National Laboratory, Idaho Falls, ID. (2011).
5 J.J. Park, J.W. Lee, and G.I. Park. Development of Advanced Voloxidation Process for Treatment of Spent Fuel, Korea Atomic Energy Research Institute Report, KAERI/ RR-3212/2009, Korea (2010).
6 J.J. Park, J.M. Shin, J.H. Yang, Y.H. Baek, J.W. Yoo, and G.I. Park. Fly-ash Granule Filter for Trapping Gaseous Cesium, Korea Atomic Energy Research Institute Report, KAERI/TR-5277/2013, Korea (2013).
7 J.H. Yang, J.Y.Yoon, J.H. Lee, S.M. Hong, and Y.Z. Cho, "Trapping Characteristics of Cesium Iodide by Aluminosilicate Filter", KRS 2017 Autumn Meeting : Korean Radioactive Waste Society, October 18-20, Changwon, Korea (2017)
8 J.H. Yang, J.Y. Yoon, J.H. Ju, and Y.Z. Cho, "A Kaolinite-based Filter to Capture Gaseous Cesium Compounds in Off-gas Released during the Pyroprocessing Head-end Process", Annals of Nucl. Energy, 103, 29-35 (2017).   DOI
9 B.S. Choi, G.I. Park, J.H. Kim, S.K. Ryu, and J.W. Lee, "Adsorption Equilibrium and Dynamics of Methyl Iodide in a Silver Ion-exchanged Zeolite Column at High Temperatures", J. Radioanal. Nucl. Chem., 7(2), 91-193 (2001).
10 D.R. Haefner and, T.J. Tranter, "Methods of Gas Phase Capture of Iodine from Fuel Reprocessing Off-gas : A Literature Survey", INL/EXT-07-12299, Idaho National Laboratory, Idaho Falls, ID. (2007).
11 W.R.A. Goossens, G.G. Eichholz, and D.W. Tedder. 1991. "Treatment of Gaseous Effluents at Nuclear Facilities", Harwood Academic Publishers, The University of California 118-119 (1991).
12 P. Taylor, "A Review of Methods for Immobilizing Iodine-129 Arising from a Nuclear Fuel Recycle Plant, with Emphasis on Waste-form Chemistry", Atomic Energy of Canada Limited, AECL-10163, Pinawa, MB. (1990).
13 Y. Yokomori, K. Asazuki, N. Kamiya, Y. Yano, K. Alamatsu, T. Toda, A. Aruga, Y. Kaneo, S. Matsuoka, and S. Matsumoto, "Final Storage of Radioactive Cesium by Pollucite Hydrothermal Synthesis", Sci. Rep., 4, 4195-4201 (2014).
14 J.H. Yang, A. Han, J.Y. Yoon, H.S. Park, and Y.Z. Cho, "A New Route to the Stable Capture and Final Immobilization of Radioactive Cesium", J. Hazard. Mater., 339, 73-81 (2017).   DOI
15 J.H. Yang, H.S. Park, and Y.Z. Cho, "Silver Phosphate Glasses for Immobilization of Radioactive Iodine", Annals of Nucl. Energy, 110, 208-214 (2017).   DOI
16 Y. Z. Cho, B. G. Ahn, H. C. Eun, J. S. Jung, and H. S. Lee, "Melt Crystallization Process Treatment of LiCl Salt Waste Generated from Electrolytic Reduction Process of Spent Oxide Fuel", Energy Procedia, 7, 525-531 (2011).   DOI
17 M.K. Jeon, C.H. Lee, C.J. Park, J.H. Choi, I.H. Cho, K.H. Kang, H.S. Park, and G.I. Park, "Effect of Burnup on the Radioactivation Behavior of Cladding Hull Materials Studied using the ORIGEN-S Code", J. Radioanal. Nucl. Chem., 298(3), 1629-1633 (2103).   DOI
18 Y. Z. Cho, G. I. Park, H. S. Lee, I. T. Kim, and D. S. Han, "Concentration of Cesium and Strontium Elements Involved in a LiCl Waste Salt by a Melt Crystallization Process", Nucl. Technol., 171, 325-330 (2010).   DOI
19 J. H. Choi, Y. Z. Cho, T. K. Lee, H. C. Eun, J. H. Kim, I. T. Kim, G. I. Park, and J. K. Kang, "Inclusion Behavior of Cs, Sr, and Ba Impurities in LiCl Crystal Formed by Layer Melt Crystallization: Combined First-principles Calculation and Experimental Study", J. Cryst. Growth, 371, 84-90 (2013).   DOI
20 M.K. Jeon, C.J. Park, C.H. Lee, K.H. Kang, and G.I. Park, "Simulation of Radioactivation and Chlorination Reaction Behavior for Zircaloy-4 and Zirlo Cladding Hull Wastes", J. Radioanal. Nucl. Chem., 292(3), 1221-1228 (2012).   DOI
21 M.K. Jeon, K.H. Kang, C.M. Heo, J.H. Yang, C.H. Lee, and G.I. Park, "Effect of Oxidation Conditions on Chlorination Reaction of Zircaloy-4 Hulls", J. Nucl. Mater., 424(1-3),153-157 (2012).   DOI
22 T. Inoue, "Actinide Recycling by Pyro-process with Metal Fuel FBR for Future Nuclear Fuel Cycle System", Prog. in Nucl. Energy, 40, 547-554 (2002).   DOI
23 C.H. Lee, K.H. Kang, M.K. Jeon, C.M. Heo, and Y.L. Lee, "Electrorefining of Zirconium from Zircaloy-4 Cladding Hulls in LiCl-KCl Molten Salts", J. the Electrochem. Soc., 159(8), D463-468 (2012).   DOI
24 S.Y. Han, S.A. Jang, and H.S. Park, "Microstructure and Corrosion Properties on Zr-Cr-NM Alloy Metallic Waste Form for Long Term Disposal", KRS 2017 Spring Meeting : Korean Radioactive Waste Society, May 24-26, Busan, Korea (2017).
25 J. H. Choi, T. K. Lee, K. R. Lee, S. Y. Han, Y. Z. Cho, N. Y. Kim, S. A. Jang, H. S. Park, and J. M. Hur, "Melt-crystallization Monitoring System for the Purification of 10 kg- scale LiCl Salt Waste", Nucl. Eng. Des., 326, 1 (2018).   DOI
26 H.S. Lee, G.I. Park, K.H. Kang, J.M. Hur, J.K. Kim, D.H. Ahn, Y.Z. Cho, and E.H.Kim, "Pyroprocessing Technology Development at KAERI", Nucl. Eng. Technol., 43(4), 317-328 (2011).   DOI
27 H.S. Lee, G.I. Park, J.W. Lee, K.H. Kang, J.M. Hur, J.K. Kim, S.W. Paek, I.T. Kim, and I.J. Cho, "Current Status of Pyroprocessing Development at KAERI", Sci. Technol. Nucl. Install., 2013, 1-11 (2013).
28 G.I. Park, H.S. Park, K.H. Kang, J.M. Shin, and J.C. Lee. Development of Pyroprocess Waste Treatment Technology, Korea Atomic Energy Research Institute Report, KAERI/ RR-3887/2014 (2015).
29 B. Westphal, J.J. Park, J.M. Shin, and G.I. Park, "Selective Trapping of Volatile Fission Products with an Off-gas Treatment System", Sep. Sci. Technol., 43(9-10), 2695-2708 (2008).   DOI
30 M.K. Jeon, K.H. Kang, G.I. Park, and Y.S. Lee, "Chlorination Reaction Behavior of Zircaloy-4 Hulls : Experimental and Theoretical Approaches", J. Radioanal. Nucl. Chem., 292, 513-517 (2012).   DOI
31 K.R. Lee, B.J. Riley, H.S. Park, J-H Choi, S.Y. Han, J.M. Hur, J.A. Petterson, Z. Zhu, D.K. Schreiber, K. Kruska, and M.J. Olszta, "Investigation of Physical and Chemical Properties for Upgraded SAP ($SiO_2-Al_2O_3-P_2O_5$) Waste Form to Immobilize Radioactive Waste Salt", J. Nucl. Mater., 515, 382-391 (2019).   DOI
32 J.M. Shin, J.J. Park, K.C. Song, and J.H. Kim, "Trapping Behavior of Gaseous Cesium by Fly Ash Filters", Appl. Radiat. Isotopes, 67(7-8), 1534-1539 (2009).   DOI
33 J.H. Yang, J.M. Shin, J.J. Park, G.I. Park, and M.S. Yim, "Novel Synthesis of Bismuth-based Adsorbents for the Removal of $^{129}I$ in Off-gas", J. Nucl. Mater., 457, 1-9 (2015).   DOI
34 J.H. Yang, H.S. Park, and Y.Z. Cho, "Immobilization of Cs-trapping Ceramic Filters within Glass-ceramic Waste Forms", Annals of Nucl. Energy, 110, 1121-1126 (2017).   DOI
35 K.R. Lee, H.S. Park, I.H. Cho, J.H. Choi, H.C. Eun, T.K. Lee, S.Y. Han, and D.H. Ahn, "De-chlorination and Solidification of Radioactive LiCl Waste Salt by Using $SiO_2-Al_2O_3-P_2O_5$ (SAP) Inorganic Composite including $B_2O_3$ Component", Korean. J. Chem. Eng., 34, 2390-2396 (2017).   DOI
36 H.C. Eun, J.H. Choi, N.Y. Kim, T.K. Lee, S.Y. Han, S.A. Jang, T.J. Km, H.S. Park, and .H. Ahn, "A Study of Separation and Solidification of Group II Nuclides in Waste Salt Delivered from the Pyrochemical Process of Used Nuclear Fuel", J. Nucl. Mater., 491, 149-153 (2017).   DOI
37 H.S. Park, I.T. Kim, Y.Z. Cho, H.C. Eun, and H.S. Lee, "Stabilization/Solidification of Radioactive Salt Waste by Using $xSiO_2-yAl_2O_3-zP_2O_5$ (SAP) Material at Molten Salt State", Environ. Sci. Technol., 42, 9357-9362 (2008).   DOI
38 Y. Z. Cho, T.K. Lee, H.C. Eun, J.H. Choi, I.T. Kim, and G.I. Park, "Purification of Used Eutetci (LiCl-KCl) Salt Electrolyte from Pyrprocessing", J. Nucl. Mater., 439, 47-54 (2013).
39 H.C. Eun, J.H. Choi, N.Y. Kim, S.Y. Han, K.R. Lee, H.S. Park, and D.H. Ahn, "A Study on the Treatment of Waste Electrolytes from the Pyrochemical Process of Used Nuclear Fuel", NUTHOS-11 : The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety, October 9-13, Gyeongju, Korea, 1-8 (2016).
40 I.H. Cho, H.S. Park, K.R. Lee, J.H. Choi, I.T. Kim, J.M. Hur, and Y.S. Lee, "Treatment of Radioactive Waste Salt by Using Synthetic Silica-based Phosphate Composite for De-chlorination and Solidification", J. Nucl. Mater., 493, 388-397 (2017).   DOI
41 K.R. Lee, H.S. Park, I.H. Cho, J.H. Choi, H.C. Eun, T.K. Lee, S.Y. Han, and D.H. Ahn, "Dechlorination and Solidification of Radioactive LiCl Waste Salt by Using $SiO_2-Al_2O_3-P_2O_5$ (SAP) Inorganic Composite including $B_2O_3$ Component", Korean. J. Chem. Eng., 34, 2390-2396 (2017).   DOI