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참고문헌 (95건) : 자료제공( 네이버학술정보 )

참고문헌 목록에 대한 테이블로 번호, 참고문헌, 국회도서관 소장유무로 구성되어 있습니다.
번호 참고문헌 국회도서관 소장유무
1 Current status of spent fuels and the development of computer programs for the PWR spent fuel management in Korea 네이버 미소장
2 Nuclear Safety and Security Commission (NSSC), Annual Report, p.180 (2012). 미소장
3 M. A. McKinnon and V. A. DeLoach, "Spent nuclear fuel storage - Performance tests and demonstrations", Pacific Northwest Laboratory Report, PNL- -8451 (1993). 미소장
4 M. A. McKinnon and M. E. Cunningham, "Dry Storage Demonstration for High-Burnup Spent Nuclear Fuel-Feasibility Study", Pacific Northwest National Laboratory Report, PNNL-14390 (2003). 미소장
5 Thermal Creep of Irradiated Zircaloy Cladding 네이버 미소장
6 High Temperature Postirradiation Materials Performance of Spent Pressurized Water Reactor Fuel Rods under Dry Storage Conditions 네이버 미소장
7 Short-time creep and rupture tests on high burnup fuel rod cladding 네이버 미소장
8 Characteristics of Hydride Precipitation and Reorientation in Spent-Fuel Cladding 네이버 미소장
9 Hydride reorientation in Zircaloy-4 cladding 네이버 미소장
10 Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage 네이버 미소장
11 Mechanisms of hydrogen induced delayed cracking in hydride forming materials 네이버 미소장
12 Y. S. Kim, "Delayed hydride cracking of spent fuel rods in dry storage", Journal of nuclear materials, 378(1), pp. 30-34 (2008). 미소장
13 M. P. Puls, "Review of the thermodynamic basis for models of delayed hydride cracking rate in zirconium alloys", Journal of nuclear materials, 393(2), pp. 350-367 (2009). 미소장
14 Influences of cesium and cesium oxide on iodine stress corrosion cracking of Zircaloy-2 in out-of-pile and in-pile conditions 네이버 미소장
15 A. Tassoji, R. E. Einziger, and A. K. Miller, "Modeling of Zircaloy Stress-Corrosion Cracking: Texture Effects and Dry storage Spent Fuel Behavior", ASTM special technical publication, 824, pp. 595- 626 (1984). 미소장
16 M. A. McKinnon, R. E. Einziger, D. L. Baldwin, and S. G. Pitman, "Data Needs for Long-Term Dry Storage of LWR Fuel", Electric Power Research Institute Report, EPRI-TR-108757 (1998). 미소장
17 L. D. Blackburn, D. G. Farwick, S. R. Fields, L. A. James, and R. A. Moen, "Maximum Allowable Temeprature For Storage of Spent Nuclear Reactor Fuel", Handford Engineering Develoment Laboratory Report, HEDL-TME 78-37 (1978). 미소장
18 M. Peehs, F. Garzarolli, and W. Goll, "Assessment of Dry Storage Performance of Spent LWR Fuel Assemblies with Increasing Burnup", IAEASM- 352-39, pp. 313-324 (1984). 미소장
19 LWR Spent Fuel Storage Behaviour 네이버 미소장
20 B. A. Chin, M. A. Khan, and J. C. L. Tarn, "Deformation and Fracture Map Methdology for Predicting Cladding Behavior during Dry Storage", Pacific Northwest Laboratory Report, PNL-5998 (1986). 미소장
21 US NRC Spent Fuel Project Office, "Interim Staff Guidance-11, Revision 1" (2000). 미소장
22 Review of spent fuel integrity evaluation for dry storage 소장
23 J. Kessler and R. E. Einziger, "Technical Bases for Extended Dry Storage of Spent Nuclear Fuel", Electric Power Research Institute Report, EPRI- 1003416 (2002). 미소장
24 B. Hanson, H. Alsaed, C. Stockman, D. Enos, R. Meyer, and K. Sorenson, "Gap Analysis to Support Extended Storage of Used Nuclear Fuel Rev.0", Pacific Northwest National Laboratory Report, PNNL- 20509, p. 198 (2012). 미소장
25 US NRC Spent Fuel Project Office, "Interim Staff Guidance-11, Revision 3" (2003). 미소장
26 U.S. Nuclear Regulatory Commission (NRC), "Standard review plan for dry cask storage systems", Nuclear Regulatory Commission Report, NUREG-1536, revision 1 (2010). 미소장
27 K. Kamimura, "Integrity criteria of spent fuel for dry storage in Japan", International Seminar on Spent Fuel Storage (ISSF), Tokyo, Japan (2010). 미소장
28 EPRI, "Spent Fuel Transportation Applications: Longitudinal Tearing Resulting from Transportation Accidents—A Probabilistic Treatment", Electric Power Research Institute Report, EPRI-1013448 (2006). 미소장
29 A STUDY ON THE INITIAL CHARACTERISTICS OF DOMESTIC SPENT NUCLEAR FUELS FOR LONG TERM DRY STORAGE 소장
30 The effect of hydride on the corrosion of Zircaloy-4 in aqueous LiOH solution 네이버 미소장
31 S. Müller and L. Lanzani, "Corrosion of zirconium alloys in concentrated lithium hydroxide solutions", Journal of nuclear materials, 439, pp. 251-257 (2013). 미소장
32 A study on the effects of dissolved hydrogen on zirconium alloys corrosion 네이버 미소장
33 M. P. Short, D. Hussey, B. K. Kendrick, T. M. Besmann, C. R. Stanek, and S. Yip, "Multiphysics modeling of porous CRUD deposits in nuclear reactors", Journal of nuclear materials, 443(1-3), pp. 579-587 (2013). 미소장
34 G. A. Berna, C. E. Beyer, K. L. Davis, and D. D. Lanning, "FRAPCON-3: A Computer Code for the Calculation of Steady-state, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup", NUREG/CR-6534, PNNL-11513 (1997). 미소장
35 Hydrogen Pickup and Redistribution in Alpha-Annealed Zircaloy-4 네이버 미소장
36 R. E. Einziger, H. C. Tsai, M. C. Billone, and B. A. Hilton, Examination of Spent PWR Fuel Rods After 15 Years in Dry Storage (2002). 미소장
37 H. Tsai and M. C. Billone, "Characterization of High-Burnup PWR and BWR Rods", Nuclear Safe ty Research Conference, October 28-30, 2002, Washington D.C., 2002. 미소장
38 Review of Halden reactor project high burnup fuel data that can be used in safety analyses 네이버 미소장
39 K. J. Geelhood, W. G. Luscher, and C. E. Beyer, "FRAPCON-3.4: A Computer Code for the Calculation of Steady-State Thermal-Mechanical behavior of Oxide Fuel Rods for High Burnup", NUREG/ CR-7022, PNNL-19418, 1 (2011). 미소장
40 S. M. Bowman and L. C. Leal, "ORIGEN-ARP: Automatic Rapid Process for Spent Fuel Depletion, Decay, and Source Term Analysis", NUREG/CR- 0200, Revision 6, 1 (2000). 미소장
41 Y. Rashid and R. Dunham, "Creep Modeling and Analysis Methodlology for Spent Fuel in Dry Storage", Electric Power Research Institute Report, EPRI-1003135 (2001). 미소장
42 R. E. Einziger, H. Tsai, M. C. Billone, and B. A. Hilton, "Examination of Spent PWR Fuel Rods after 15 Years in Dry Storage", Argonne National Laboratory Report, ANL-03/17 (2003). 미소장
43 C. W. Enderlin, D. R. Rector, J. M. Cuta, R. E. Dodge, and T. E. Michener, "COBRA-SFS: A thermal- hydraulic analysis code for spent fuel storage and transportation casks", Pacific Northwest National Laboratory Report, PNL-10782 (1995). 미소장
44 X. Heng, G. Zuying, and Z. Zhiwei, "A numerical investigation of natural convection heat transfer in horizontal spent-fuel storage cask", Nuclear Engineering and Design, 213, pp. 59-65 (2002). 미소장
45 R. A. Brewster, E. Baglietto, E. Volpenhein, and C. S. Bajwa, "CFD Analyses of the TN-24P PWR Spent Fuel Storage Cask", ASME 2012 Pressure Vessels and Piping Conference, 3, pp. 17-25 (2012). 미소장
46 Thermal-fluid flow analysis and demonstration test of a spent fuel storage system 네이버 미소장
47 Thermal analysis of a spent fuel cask in different transport conditions 네이버 미소장
48 CFD-assisted scaling methodology and thermal-hydraulic experiment for a single spent fuel assembly 네이버 미소장
49 Full-scope simulation of a dry storage cask using computational fluid 네이버 미소장
50 K. Kamimura, N. Kohno, K. Itoh, Y. Tsukuda, T. Yasuda, M. Aomi, K. Murai, H. Fujii, and Y. Senda, "Thermal creep tests of BWR and PWR spent fuel cladding", IAEA-CN-102/27, pp. 375-385 (2003). 미소장
51 Low-Temperature Rupture Behavior of Zircaloy-Clad Pressurized Water Reactor Spent Fuel Rods Under Dry Storage Conditions 네이버 미소장
52 Spent LWR fuel dry storage in large transport and storage casks after extended burnup 네이버 미소장
53 K. Ito, K. Kamimura, and Y. Tsukuda, "Evaluation of Irradiation Effect on Spent Fuel Cladding Creep Properties", Proceedings of the 2004 International meeting on LWR fuel performance, pp. 440-451 (2004). 미소장
54 Y. R. Rashid, D. J. Sunderland, and R. O. Montgomery, "Creep as the Limiting Mechanism for Spent Fuel Dry Storage", Electric Power Research Institute Report, EPRI-1001207 (2000). 미소장
55 Stress-reorientation of hydrides and hydride embrittlement of Zr–2.5 wt% Nb pressure tube alloy 네이버 미소장
56 S. I. Hong and K. W. Lee, "Stress-induced reori entation of hydrides and mechanical properties of Zircaloy-4 cladding tubes", Journal of nuclear materials, 340, pp. 203-208 (2005). 미소장
57 M. C. Billone, T. A. Burtseva, and R. E. Einziger, "Ductile-to-brittle transition temperature for highburnup cladding alloys exposed to simulated dryingstorage conditions", Journal of nuclear materials, 433(1-3), pp. 431-448 (2013). 미소장
58 Effect of radial hydrides on the axial and hoop mechanical properties of Zircaloy-4 cladding 네이버 미소장
59 K. Kese, "Hydride re-orientation in zircaloy and its effect on the tensile properties", Swedish Nuclear Power Inspectorate, (SKI) Report 98:32 (1998). 미소장
60 H. M. Chung, "Understanding Hydride- and Hydrogen- related Processes in High-burnup Cladding in Spent-fuel Storage and Accident Situations", Proceedings of the 2004 International meeting on LWR fuel performance, pp. 470-479 (2004). 미소장
61 Impact of Irradiation Defects Annealing on Long-Term Thermal Creep of Irradiated Zircaloy-4 Cladding Tube 네이버 미소장
62 Radial-hydride Embrittlement of High-burnup Zircaloy-4 Fuel Cladding 네이버 미소장
63 T. Oohama, M. Okunishi, Y. Senda, K. Murakami, and M. Sugano, "Study on Hydride Re-Orientation Properties in Zircaloy-4 Cladding Tube", Nuclear reactor thermal hydraulics, operations and safety, 2004, p. N6P117 (2004). 미소장
64 Statistical Analysis of Hydride Reorientation Properties in Irradiated Zircaloy-2 네이버 미소장
65 Stress Reorientation of Hydrides in Recrystallized Zircaloy-2 Sheet 네이버 미소장
66 Effect of thermal cycling on the stress orientation of hydride in zircaloy 네이버 미소장
67 The effects of misfit and external stresses on terminal solid solubility in hydride-forming metals 네이버 미소장
68 Hydrogen in Zircaloy-4: effects of the neutron irradiation on the hydride formation 네이버 미소장
69 Precipitation and dissolution peaks of hydride in Zr–2.5Nb during quasistatic thermal cycles 네이버 미소장
70 Terminal solid solubility of hydrogen in Zr-alloy pressure tube materials 네이버 미소장
71 The Long-Range Migration of Hydrogen Through Zircaloy in Response to Tensile and Compressive Stress Gradients 네이버 미소장
72 C. J. Simpson and C. E. Ells, "Delayed hydrogen embrittlement in Zr-2.5wt % Nb", Journal of nuclear materials, 52(2), pp. 289-295 (1974). 미소장
73 IAEA, "Delayed hydride cracking in zirconium alloys in pressure tube nuclear reactors", International Atomic Energy Agengy Report, IAEA-TECDOC- 1410 (2004). 미소장
74 F. R. Ambler, "Effect of Direction of Approach to Temperature on the Delayed Hydrogen Cracking Behabior of Cold-Worked Zr-2.5Nb", ASTM special technical publication, 824, pp. 653-674 (1984). 미소장
75 On the consequences of hydrogen supersaturation effects in Zr alloys to hydrogen ingress and delayed hydride cracking 네이버 미소장
76 S. Q. Shi, G. K. Shek, and M. P. Puls, "Hydrogen concentration limit and critical temperatures for delayed hydride cracking in zirconium alloys", Journal of nuclear materials, 218(2), pp. 189-201 (1995). 미소장
77 Preface 네이버 미소장
78 Y. S. Kim, "Author’s 2nd reply to comments on author’s reply to “Review of the thermodynamic basis for models of delayed hydride cracking rate in zirconium alloys”, M.P. Puls in J. Nucl. Mater. 393 (2009) 350–367", Journal of nuclear materials, 399(2-3), pp. 259-265 (2010). 미소장
79 The influence of multiaxial states of stress on the hydrogen embrittlement of zirconium alloy sheet 네이버 미소장
80 G. W. Parry and W. Evans, "Occurrence of ductile hydrides in zircaloy-2", Nucleonics, 22, p. 117 (1964). 미소장
81 W. M. Mueller, J. P. Blackledge, G. G. Libowitz, and U. S. A. E. Commission, Metal hydrides: Academic Press (1968). 미소장
82 Fracture toughness of zirconium hydride and its influence on the crack resistance of zirconium alloys 네이버 미소장
83 M. C. Billone and Y. Liu, "Perspectives on DBTT for High-Burnup Fuel Cladding", ESCP Meeting, St. Petersburg, FL , May 6 (2013). 미소장
84 Effect of strain hardening on the lateral compression of tubes between rigid plates 네이버 미소장
85 Reproducing hoop stress–strain behavior for tubular material using lateral compression test 네이버 미소장
86 L. G. Bell and R. G. Duncan, "Hydride reorientation in Zr-2.5%Nb; How it is Affected by Stress, Temperature and Heat Treatment", Atomic Energy of Canada Limited Report, AECL-5110 (1975). 미소장
87 A. C. Wallace, G. K. Shek, and O. E. Lepik, "Effects of Hydride Morphology on Zr-2.5Nb Fracture Toughness", ASTM special technical publication, 1023, pp. 66-88 (1989). 미소장
88 ASTM B811-02, "Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding" (2007). 미소장
89 Crack growth in the through-thickness direction of hydrided thin-wall Zircaloy sheet 네이버 미소장
90 S. K. Yagnik, R. C. Kuo, Y. R. Rashid, A. J. Machiels, and R. L. Yang, "Effect of Hydrides on the Mechanical Properties of Zircaloy-4", Proceedings of the 2004 International meeting on LWR fuel performance, pp. 191-199 (2004). 미소장
91 L. A. Simpson and C. K. Chow, "Effect of Metallurgical Variables and Temperature on the Fracture Toughness of Zirconium Alloy Pressure Tube", ASTM special technical publication, 939, pp. 579- 596 (1987). 미소장
92 P. H. Davies and C. P. Stearns, "Fracture toughness testing of Zircaloy-2 pressure tube material with radial hydrides using direct-current potential drop", ASTM special technical publication, 905, pp. 379- 400 (1986). 미소장
93 U.S. Nuclear Regulatory Commission (NRC), "Standard Review Plan for Dry Cask Storage Systems", Nuclear Regulatory Commission Report, NUREG-1536 (1997). 미소장
94 US NRC Spent Fuel Project Office, "Interim Staff Guidance-11, Revision 2" (2002). 미소장
95 (The) effects of creep and hydride on spent fuel integrity during interim dry storage 소장

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