Browse > Article
http://dx.doi.org/10.7733/jnfcwt.2022.018

Review of Instant Release Fractions of Long-lived Radionuclides in CANDU and PWR Spent Nuclear Fuels Under the Geological Disposal Conditions  

Choi, Heui Joo (Korea Atomic Energy Research Institute)
Koo, Yang-Hyun (Korea Atomic Energy Research Institute)
Cho, Dong-Keun (Korea Atomic Energy Research Institute)
Publication Information
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) / v.20, no.2, 2022 , pp. 231-241 More about this Journal
Abstract
Several countries, including Korea, are considering the direct disposal of spent nuclear fuels. The radiological safety assessment results published after a geological repository closure indicate that the instant release is the main radiation source rather than the congruent release. Three Safety Case reports recently published were reviewed and the IRF values of seven long-lived radionuclides, including relevant experimental results, were compared. According to the literature review, the IRF values of both the CANDU and low burnup PWR spent fuel have been experimentally measured and used reasonably. In particular, the IRF values of volatile long-lived nuclides, such as 129I and 135Cs, were estimated from the FGR value. Because experimental leaching data regarding high burnup spent nuclear fuels are extremely scarce, a mathematical modelling approach proposed by Johnson and McGinnes was successfully applied to the domestic high burnup PWR spent nuclear fuel to derive the IRF values of iodine and cesium. The best estimate of the IRF was 5.5% at a discharge burnup of 55 GWd tHM-1.
Keywords
Disposal; Spent nuclear fuel; Instant release fraction; Fission gas release; High burnup;
Citations & Related Records
연도 인용수 순위
  • Reference
1 L. Johnson, I. Gunther-Leopold, J.K. Waldis, H.P. Linder, J. Low, D. Cui, E. Ekeroth, K. Spahiu, and L. Z. Evins, "Rapid Aqueous Release of Fission Products From High Burn-up LWR Fuel: Experimental Results and Correlations With Fission gas Release", J. Nucl. Mater., 420(1-3), 54-62 (2012).   DOI
2 Svensk Karnbranslehantering AB. Long-term Safety for the Final Repository for Spent Nuclear Fuel at Forsmark, SKB Technical Report, TR-11-01 (2011).
3 Y.M. Lee and Y. Hwang, "A GoldSim Model for the Safety Assessment of an HLW Repository", Prog. Nucl. Energy, 51(6-7), 746-759 (2009).   DOI
4 Posiva Oy. Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto-Models and Data for the Repository System 2012, Posiva Oy Report, POSIVA 2013-01 (2013).
5 L.O. Werme, L.H. Johnson, V.M. Oversby, F. King, K. Spahiu, B. Grambow, and D. W. Shoesmith. Spent Fuel Performance Under Repository Conditions: A Model for Use in SR-Can, Svensk Karnbranslehantering AB Technical Report, TR-04-19 (2004).
6 K. Lassmann, C.T. Walker, J. van der Laar, and F. Lindstrom, "Modelling the High Burnup UO2 Structure in LWR Fuel", J. Nucl. Mater., 226(1-2), 1-8 (1995).   DOI
7 S. Stroes-Gascoyne, L.H. Johnson, and D.M. Sellinger, "The Relationship Between Gap Inventories of Stable Xenon, 137Cs, and 129I in Used CANDU Fuel", Nucl. Technol., 77(3), 320-330 (1987).   DOI
8 L. Johnson, C. Poinssot, C. Ferry, and P. Lovera. Estimates of the Instant Release Fraction for UO2 and MOX Fuel at t=0, National Cooperative for the Disposal of Radioactive Waste Technical Report, NAGRA NTB 04-08 (2004).
9 J.C. Tait, R.J.J. Cornett, L.A. Chant, J. Jirovec, J. Mc-Connell, and D.L. Wilkin, "Determination of Cl Impurities and 36Cl Instant Release From Used CANDU Fuels", Materials Research Society Symp. Proc., vol.465, 503-510, MRS, Massachusetts (1997).
10 L.H. Johnson and D.F. McGinnes. Partitioning of Radionuclides in Swiss Power Reactor Fuels, National Cooperative for the Disposal of Radioactive Waste Technical Report, NAGRA NTB 02-07 (2002).
11 Y.H. Koo, B.H. Lee, J.S. Cheon, D.S. Sohn, "Pore Pressure and Swelling in the Rim Region of LWR High Burnup UO2 Fuel", J. Nucl. Mater., 295(2-3), 213-220 (2001).   DOI
12 E. Nordstrom. Fission Gas Release Data for Ringhals PWRs, Svensk Karnbranslehantering AB Technical Report, TR-09-26 (2009).
13 G. Vesterlund and L.V. Corsetti, "Recent ABB Fuel Design and Performance Experience", Proc. of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance, 62-70, ANS, Florida (1994).
14 Y.H. Koo, B.H. Lee, J.Y. Oh, and K.W. Song, "Conservative Width of High-Burnup Structure in Light Water Reactor UO2 Fuel as a Function of Pellet Average Burnup", Nucl. Technol., 164(3), 337-347 (2008).   DOI
15 S. Stroes-Gascoyne, "Measurements of Instant-Release Source Terms for 137Cs, 90Sr, 99Tc, 129I and 14C in Used CANDU Fuels", J. Nucl. Mater., 238(2-3), 264-277 (1996).   DOI
16 L.H. Johnson and J.C. Tait. Release of Segregated Nuclides From Spent Fuel, Svensk Karnbranslehantering AB. Technical Report, TR-97-18 (1997).
17 H. Kleykamp, "The Chemical State of the Fission Products in Oxide Fuels", J. Nucl. Mater., 131(2-3), 221-246 (1985).   DOI
18 D. Serrano-Purroy, F. Clarens, E. Gonzalez-Robles, J.P. Glatz, D.H. Wegen, J. de Pablo, I. Casas, J. Gimenez, and A. Martinez-Esparza, "Instant Release Fraction and Matrix Release of High Burn-up UO2 Spent Nuclear Fuel: Effect of High Burn-up Structure and Leaching Solution Composition", J. Nucl. Mater., 427(1-3), 249-258 (2012).   DOI
19 M. Gobien, F. Garisto, E. Kremer, and C. Medri. Sixth Case Study: Reference Data and Codes, Nuclear Waste Management Organization Report, NWMO-TR-2016-10 (2016).
20 Svensk Karnbranslehantering AB. Data Report for the Safety Assessment SR-Site, SKB Technical Report, TR-10-52 (2010).
21 F. Garisto and P. Gierszewski. Technetium-99: Review of Properties Relevant to a Canadian Geological Repository, Ontario Power Generation Report, 06819-REP-01200-10081-R00 (2002).
22 J. Lee, I. Kim, H. Ju, H. Choi, and D. Cho, "Proposal of an Improved Concept Design of the Deep Geological Disposal System of Spent Nuclear Fuel in Korea", J. Nucl. Fuel Cycle Waste Technol., 18(S), 1-19 (2020).
23 C.N. Wilson. Results From NNWSI Series 2 Bare Fuel Dissolution Tests, Pacific Northwest Laboratory Report, PNL-7169 (1990).
24 J.L. Cormenzana. Probabilistic Sensitivity Analysis for the 'Initial Defect in the Canister' Reference Model, Posiva Working Report, 2013-25 (2013).
25 P. Lovera, C. Ferry, C. Poinssot, and L. Johnson. Synthesis Report on the Relevant Diffusion Coefficients of Fission Products and Helium in Spent Nuclear Fuels, Commissariat a l'energie atomique Report, CEAR-6039 (2003).
26 W.J. Gray, "Inventories of Iodine-129 and Cesium-137 in the Gaps and Grain Boundaries of LWR Spent Fuels", Materials Research Society Symp. Proc., vol.556, 487-494, MRS, PA (1999).
27 S. Stroes-Gascoyne, J.C. Tait, R.J. Porth, J.L. McConnell, and W.J. Lincoln, "Release of 14C From the Gap and Grain-Boundary Regions of Used CANDU Fuels to Aqueous Solutions", Waste Manage., 14(5), 385-392 (1994).   DOI
28 Nuclear Waste Management Organization. Postclosure Safety Assessment of a Used Fuel Repository in Crystalline Rock, NWMO Report, NWMO-TR-2017-02 (2017).
29 L. Johnson, C. Ferry, C. Poinssot, and P. Lovera, "Spent Fuel Radionuclide Source-term Model for Assessing Spent Fuel Performance in Geological Disposal. Part I: Assessment of the Instant Release Fraction", J. Nucl. Mater., 346(1), 56-65 (2005).   DOI