Preliminary issues associated with the next generation nuclear plant intermediate heat exchanger design
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[1] Eduardo Gallego,et al. Transactions of the American Nuclear Society , 2009 .
[2] Weiju Ren,et al. A Review Paper on Aging Effects in Alloy 617 for Gen IV Nuclear Reactor Applications , 2009 .
[3] E. Lara‐Curzio,et al. Creep Strength and Microstructure of AL20-25+Nb Alloy Sheets and Foils for Advanced Microturbine Recuperators , 2007 .
[4] John P. Shingledecker,et al. Overview of Creep Strength and Oxidation of Heat-Resistant Alloy Sheets and Foils for Compact Heat Exchangers , 2006 .
[5] R. L. Pierres,et al. Heat Exchangers for the Next Generation of Nuclear Reactors , 2006 .
[6] E. A. Harvego,et al. Evaluation of Next Generation Nuclear Power Plant (NGNP) Intermediate Heat Exchanger (IHX) Operating Conditions , 2006 .
[7] P. Lett,et al. High temperature corrosion of structural materials under gas‐cooled reactor helium , 2006 .
[8] Weiju Ren,et al. Assessment of Existing Alloy 617 Data for Gen IV Materials Handbook , 2005 .
[9] T. M. Lillo,et al. Engineering Analysis of Intermediate Loop and Process Heat Exchanger Requirements to Include Configuration Analysis and Materials Needs , 2005 .
[10] D. Wilson,et al. Thermal-Hydraulic Analyses of Heat Transfer Fluid Requirements and Characteristics for Coupling A Hydrogen Production Plant to a High-Temperature Nuclear Reactor , 2005 .
[11] W. Ren. Development of a Controlled Material Specification for Alloy 617 for Nuclear Applications , 2005 .
[12] R. Swindeman,et al. Microstructure Characterization of Advanced Boiler Materials for Ultra Supercritical Coal Power Plants , 2004, Advances in Materials Technology for Fossil Power Plants: Proceedings from the Fourth International Conference.
[13] R. Swindeman,et al. Creep strength of High-Temperature Alloys for Ultrasupercritical Steam Boilers , 2004, Advances in Materials Technology for Fossil Power Plants: Proceedings from the Fourth International Conference.
[14] Anton Moisseytsev,et al. Passive load follow analysis of the STAR-LM and STAR-H2 systems. , 2004 .
[15] D. Allen,et al. Creep rupture and ductility of as-manufactured and service-aged nickel alloy IN617 materials and welds , 2004 .
[16] B. Ilschner,et al. The thermal fatigue behavior of the combustor alloys In 617 and HAYNES 230 before and after welding , 1999 .
[17] C. E. Jordan,et al. Thermal stability of high temperature structural alloys , 1999 .
[18] G. D. Smith,et al. Performance of Inconel Alloy 617 in Actual and Simulated Gas Turbine Environments , 1995 .
[19] Robert J. Klova,et al. Upgrading a Power Turbine Stator for Greater Creep Life, Incorporating a Material Change to Haynes 230 , 1993 .
[20] H. M. Tawancy. High temperature creep behaviour of an Ni-Cr-W-B alloy , 1992, Journal of Materials Science.
[21] S. Hsu. The effects of fatigue, hold time and creep on crack growth in high temperature environments—NiCrCo alloy , 1991 .
[22] D. Klarstrom,et al. The LCF Behavior of Several Solid Solution Strengthened Alloys Used in Gas Turbine Engines , 1990 .
[23] L. W. Graham. Corrosion of metallic materials in HTR-helium environments , 1990 .
[24] B. Huchtemann. The effect of alloy chemistry on creep behaviour in a helium environment with low oxygen partial pressure , 1989 .
[25] H. McCoy,et al. Mechanical properties of Inconel 617 and 618 , 1985 .
[26] C. R. Brinkman,et al. High-temperature time-dependent fatigue behaviour of several engineering structural alloys , 1985 .
[27] P. J. Ennis,et al. Effect of carburizing service environments on the mechanical properties of high-temperature alloys , 1984 .
[28] K. Lee. Creep Rupture Properties of Hastelloy-X and lncoloy-800H in a Simulated HTGR Helium Environment Containing High Levels of Moisture , 1984 .
[29] R. Cook,et al. Creep rupture behavior of candidate materials for nuclear process heat applications , 1984 .
[30] R. H. Cook. Creep Properties of lnconel-617 in Air and Helium at 800 to 1000°C , 1984 .
[31] H. Schuster,et al. Investigations on the fatigue behavior of high-temperature alloys for high-temperature gas-cooled reactor components , 1984 .
[32] T. Kondo,et al. Creep and rupture behavior of a special grade Hastelloy-X in simulated HTGR helium , 1984 .
[33] T. Kondo,et al. Low-Cycle Fatigue of Heat-Resistant Alloys in High-Temperature Gas-Cooled Reactor Helium , 1984 .
[34] T. Shikama,et al. Creep rupture properties of superalloys developed for nuclear steelmaking , 1984 .
[35] E. Bodmann,et al. Fracture Mechanics Investigations on High-Temperature Gas-Cooled Reactor Materials , 1984 .
[36] P. Ennis,et al. Tensile and impact properties of candidate alloys for high-temperature gas-cooled reactor applications , 1984 .
[37] J. Sannier,et al. Behavior of Metallic Materials Between 550 and 870°C in High-Temperature Gas-Cooled Reactor Helium Under Pressures of 2 and 50 bar , 1984 .
[38] B. Ilschner,et al. Creep behavior of materials for high-temperature reactor application , 1984 .
[39] T. Nakanishi,et al. Creep Properties of Hastelloy-X in Impure Helium Environments , 1984 .
[40] H. Bates. The Corrosion Behavior of High-Temperature Alloys During Exposure for Times up to 10 000 h in Prototype Nuclear Process Helium at 700 to 900°C , 1984 .
[41] H. Nickel,et al. Creep and Relaxation Behavior of lnconel-617 , 1984 .
[42] H. Nickel,et al. Precipitation Behavior of Ni-Cr-22 Fe-18 Mo (Hastelloy-X) and Ni-Cr-22 Co-12 Mo (Inconel-617) After Isothermal Aging , 1984 .
[43] E. Bodmann,et al. Status of design code work in Germany concerning materials and structural aspects for the heat exchanger components of advanced HTR's , 1983 .
[44] M. Booker,et al. Influence of temperature, environment, and thermal aging on the continuous cycle fatigue behavior of Hastelloy X and Inconel 617 , 1982 .
[45] G. Lai,et al. Interaction of metals with primary coolant impurities: comparison of steam-cycle and advanced HTGRs , 1981 .
[46] Akira Ohtomo,et al. Morphological changes of carbides during creep and their effects on the creep properties of inconel 617 at 1000 °C , 1980 .
[47] J. Chow,et al. Correlation of high- and low-cycle fatigue data for Incoloy-800H. [70 to 1400/sup 0/F, stress-strain] , 1976 .
[48] W. Mankins,et al. Microstructure and phase stability of INCONEL alloy 617 , 1974, Metallurgical and Materials Transactions B.
[49] R. Taylor,et al. Creep and relaxation , 1964 .
[50] A. London,et al. Compact heat exchangers , 1960 .
[51] David A. Petti,et al. The Next Generation Nuclear Plant , 2009 .
[52] W. Ren,et al. A Review of Aging Effects in Alloy 617 for Gen IV Nuclear Reactor Applications , 2006 .
[53] U. S. Doe. A Technology Roadmap for Generation IV Nuclear Energy Systems , 2002 .
[54] Colin F. McDonald,et al. Compact buffer zone plate-fin IHX—The key component for high-temperature nuclear process heat realization with advanced MHR , 1996 .
[55] J. Nilsson,et al. Influence of temperature and microstructure on creep-fatigue of Alloy 800H , 1988 .
[56] Elihu F. Bradley,et al. Superalloys: a technical guide , 1988 .
[57] D. Roberts. Design codes and lifetime prediction aspects for Alloy 800 for nuclear and non-nuclear applications , 1978 .
[58] L. Epel,et al. Creep and fatigue properties of Incoloy 800H in a high-temperature gas-cooled reactor (HTGR) helium environment , 1978 .
[59] G. Reynolds,et al. Effects of thermal aging on the microstructure and mechanical properties of a commercial Ni-Cr-Co-Mo alloy (inconel 617) , 1976 .