1 |
Svensk Karnbranslehantering AB. Design Premises for a KBS-3V Repository Based on Results From the Safety Assessment SR-Can and Some Subsequent Analyses, SKB Technical Report, TR-09-22 (2009).
|
2 |
W.L. Huang, J.M. Longe, and D.R. Pevear, "An Experimentally Derived Kinetic Model for a Smectite-to-illite Conversion and its use as Geothermometer", Clays Clay Miner., 41(2), 162-177 (1993).
DOI
|
3 |
J. Lee, D. Cho, H. Choi, and J. Choi, "Concept of a Korean Reference Disposal System for Spent Fuels", J. Nucl. Sci. Technol., 44(12), 1565-1573 (2007).
DOI
|
4 |
I.Y. Kim, D.K. Cho, and H.J. Choi. Analysis on Characteristics of Reference SNF for KRS+ Design - I. PLUS7 SNF, Korea Atomic Energy Research Institute Report, KAERI/TR-7996/2019 (2019).
|
5 |
I.Y. Kim, D.K. Cho, and H.J. Choi. Analysis on Characteristics of Reference SNF for KRS+ design - II. KOFA SNF, Korea Atomic Energy Research Institute Report, KAERI/TR-8055/2020 (2020).
|
6 |
O. Karnland and M. Birgersson, "Montmorillonite Stability With Special Respect to KBS-3 Conditions", Swedish Nuclear Fuel and Waste Management Co., SKB Technical Report, TR-06-11 (2006).
|
7 |
L. Zhen, J. Rutqvist, J.T. Birkholzer, and H.H. Liu, "On the Impact of Temperatures up to 200℃ in Clay Repositories With Bentonite Engineer Barrier Systems: A Study With Coupled Thermal, Hydrological, Chemical, and Mechanical Modeling", Eng. Geol., 197, 278-295 (2015).
DOI
|
8 |
Posiva Oy. Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto - Design Basis 2012, Posiva Oy Technical Report, POSIVA 2012-03 (2012).
|
9 |
A. M. Pytte and R. C. Reynolds, "The Thermal Transformation of Smectite to Illite", in: Thermal History of Sedimentary Basins, N.D. Naeser and T.H. McCulloh, eds., 133-140, Springer, New York (1989).
|
10 |
Grimsel Test Site. "High Temperature Effects on Bentonite Buffers (HotBent) -Aims & Objectives." GTS Projects, GTS Phase VI, HotBENT. Accessed Aug. 26 2021. Available from: https://www.grimsel.com/gtsprojects/hotbent-high-temperature-effects-on-bentonite-buffers/hotbent-introduction.
|
11 |
T.J. Park, J.H. Ryu, Y.C. Choi, Cho, W.H. Cho, and J.K. Lee, "Buffer Retardation Experiment for Radionuclides Under the Elevated Temperature Conditions: Strategy and Methodology Development for the Korean Bentonite", Proc. of Korean Radioactive Waste Society Autumn Conference, 16(2), 203-204, Jeju (2018).
|
12 |
W.J. Cho and G. Y. Kim, "Reconsideration of Thermal Criteria for Korean Spent Fuel Repository", Ann. Nucl. Energy, 88, 73-82 (2016).
DOI
|
13 |
T.J. Park and D. Seoung, "Thermal Behavior of Groundwater-saturated Korean Buffer Under the Elevated Temperature Conditions: In-situ Synchrotron X-ray Powder Diffraction Study for the Montmorillonite in Korean Bentonite", Nucl. Eng. Technol., 53(5), 1511-1518 (2021).
DOI
|
14 |
K. Ikonen. Thermal Condition of Open KBS-3H Tunnel, Posiva Oy Report, POSIVA 2005-04 (2005).
|
15 |
Japan Nuclear Cycle Development Institute. H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan (Supporting Report 2) Repository Design and Engineering Technology, JNC Report, JNC TN1410 2000-003 (2000).
|
16 |
G.R. Simmons and P. Baumgartner. The Disposal of Canada's Nuclear Fuel Waste: Engineering for a Disposal Facility, Atomic Energy of Canada Limited Report, AECL-10715 (1994).
|
17 |
J. Cuadros and J. Linares, "Experimental Kinetic Study of the Smectite-to-illite Transformation", Geochem. Cosmochim. Acta, 60(3), 439-453 (1996).
DOI
|
18 |
R. Mosser-Ruck, M. Catherlineau, A. Baronnet, and A. Trouiller, "Hydrothermal Reactivity of K-smectite at 300℃ and 100 bar: Dissolution-crystallisation Process and non-expandable Dehydrated Smectite Formation", Clay Miner., 34(2), 275-290 (1999).
DOI
|
19 |
P. Wersin, L.H. Johnson, and I.G. McKinley, "Performance of the Bentonite Barrier at Temperatures Beyond 100℃: A Critical Review", Phys. Chem. Earth, 32(8-14), 780-788 (2007).
DOI
|
20 |
J.K. Lee, Y.K. Koh, J.S. Kwon, B.J Kim, J.H. Ryu, C.K. Park, T.J. Park, H.J. Seo, H.J. Ahn, S. Yoon, S.Y. Lee, J.H. Jeong, W.H. Cho, D.K. Cho, Y.C. Choi, and P. S. Hahn. Technology Development for the Performance Demonstration of the Spent Nuclear Fuel Disposal System - Evaluation of Geochemical Behavior of Radionuclides in Multiple Barriers, Korea Atomic Energy Research Institute Report, KAERI/RR-4631/2020 (2020).
|
21 |
S.K. Srivastava, P. Bala, B.K. Samantaray, and H. Haeuseler, "Microstructural Parameters and Layer Disorder Accompanying Dehydration Transformation in Na-montmorillonite", Z. Kristallogr. - Cryst. Mater., 215(4), 235-239 (2000).
DOI
|
22 |
Grimsel Test Site. December 2020. "GTS News Letter December 2020 Year 2, Vol. 4." GTS Newsletters. Accessed Aug. 26 2021. Available from: https://www.grimsel.com/images/newsletter/GTS%20Newsletter%2004%20-%20December%202020.pdf.
|
23 |
Posiva Oy. Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto - Performance Assessment 2012, Posiva Oy Technical Report, POSIVA 2012-04 (2012).
|