Structural Materials for Heavy Liquid Metal Cooled Fast Reactors

The compatibility of structural materials, such as steels with lead and lead-bismuth eutectic, poses a critical challenge in the development of heavy liquid metal (HLM) cooled fast reactors. Factors such as the high temperatures, fast neutron flux and irradiation exposure and corrosiveness provide a...

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Detalles Bibliográficos
Clasificación:Libro Electrónico
Autor principal: IAEA
Formato: Electrónico eBook
Idioma:Inglés
Publicado: Vienna : International Atomic Energy Agency, 2021.
Temas:
Liquid metal cooled reactors.
Nuclear reactors > Materials.
Réacteurs à réfrigérant liquide métallique.
Réacteurs nucléaires > Matériaux.
Acceso en línea:Texto completo

MARC

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245 1 0 |a Structural Materials for Heavy Liquid Metal Cooled Fast Reactors  |h [electronic resource]. 
260 |a Vienna :  |b International Atomic Energy Agency,  |c 2021. 
300 |a 1 online resource (242 p.) 
500 |a Description based upon print version of record. 
505 0 |a Intro -- 1. Introduction -- 1.1. Background -- 1.2. Objective -- 1.3. Scope -- 1.4. Structure -- 2. Summary of Meeting Sessions -- 2.1. Session I: HLM Compatibility with Structural Materials: Phenomena, Modelling and Operational Experience -- 2.2. Session II: Corrosion Mitigation Measures: Coating, New Structural Materials, Environmental Conditioning -- 2.3. Session III: Qualification Programmes of Structural Materials for HLM Fast Reactors -- 3. Summary of Group Discussions -- 3.1. Group Discussion i: Outstanding Research Challenges 
505 8 |a 3.2. Group Discusion II: New Materials and Coating Techniques -- 3.3. Group discussion III: Industrialization -- 4. Conclusions -- ABBREVIATIONS -- PAPERS PRESENTED AT THE MEETING -- SESSION I: HLM COMPATIBILITY WITH STRUCTURAL MATERIALS: PHENOMENA, MODELLING AND OPERATIONAL EXPERIENCE -- KINETICS AND MECHANISM OF CRACK INITIATION OF LIQUID METAL EMBRITTLEMENT -- 1. INTRODUCTION -- 2. EXPERIMENTAL -- 2.1. Materials -- 2.2. Specimens -- 2.3. Test technique -- 2.4. Environment -- 2.5. Post-test evaluation -- 3. RESULTS I -- SENSITIVITY TO LME/EAC CRACKING IN HLM -- 3.1. T91 & liquid LBE 
505 8 |a 3.2. T91 & liquid Pb -- 4. RESULTS II -- CONDITIONS FOR LME/EAC CRACKING IN HLM: INITIATION -- 4.1. T91 & liquid LBE -- 4.2. T91 & liquid Pb -- 4.3. Initiation of LME/EAC of T91 in HLM -- summary -- 4.4. 15-15Ti in liquid LBE -- 4.5. 15-15Ti in liquid Pb -- 5. RESULTS III -- CONDITIONS FOR LME/EAC CRACKING IN HLM: KINETICS -- 5.1. Fracture resistance of T91 in liquid LBE -- 5.2. Crack Growth Rate of T91 in HLM -- 6. Discussion -- 7. Conclusions -- RATEN ICN STATUS ON MECHANICAL PROPERTIES INVESTIGATION OF 316L GENERATION iv CANDIDATE MATERIAL -- 1. INTRODUCTION -- 2. EXPERIMENTAL METHOD 
505 8 |a 3. RESULTS AND DISCUSSION -- 4. PLANNED WORKS -- 5. CONCLUSIONS -- SIMULATIONS OF SOME STRUCTURAL MATERIALS BEHAVIOR UNDER NEUTRON IRRADIATION -- 1. INTRODUCTION -- 2. REACTOR CONFIGURATION AND COMPUTATIONAL TOOLS -- 3. RESULTS AND DISCUSSION -- 3.1. Molybdenum Alloys -- 3.2. Vanadium Alloys -- 4. CONCLUSIONS -- VACANCY TYPE DEFECTS BEHAVIOR IN MATERIALS FORESEEN FOR LIQUID METAL COOLED FAST REACTORS -- RESEARCH OF CORROSION BEHAVIOR OF STEAM GENERATOR TUBES FOR LEAD-COOLED POWER UNIT -- 1. INTRODUCTION -- 2. CORROSION RESISTANCE IN LIQUID LEAD 
505 8 |a 3. CORROSION RESISTANCE IN WATER AND SUPERHEATED STEAM -- 4. INTERGRANULAR CORROSION RESISTANCE -- 5. THE MAIN RESULTS AND CONCLUSIONS -- TENSILE TESTING OF SUB-SIZED T91 STEEL SPECIMENS IN LIQUID LEAD -- 1. INTRODUCTION -- 2. THE LILLA FACILITY AND TEST SECTIONS -- 2.1. The description of the LILLA facility -- 2.2. The description of the test sections -- 3. SSRT TESTS OF T91 IN ARGON AND LIQUID LEAD -- 3.1. Material and test conditions -- 3.2. Tests in argon and liquid lead -- 4. CONCLUSIONS 
500 |a SESSION II: CORROSION MITIGATION MEASURES: COATING, NEW STRUCTURAL MATERIALS, ENVIRONMENTAL CONDITIONING 
520 |a The compatibility of structural materials, such as steels with lead and lead-bismuth eutectic, poses a critical challenge in the development of heavy liquid metal (HLM) cooled fast reactors. Factors such as the high temperatures, fast neutron flux and irradiation exposure and corrosiveness provide a severe environment for the materials in these advanced reactor systems. The compatibility of liquid coolant with structural materials is critical for the developme. 
590 |a ProQuest Ebook Central  |b Ebook Central Academic Complete 
650 0 |a Liquid metal cooled reactors. 
650 0 |a Nuclear reactors  |x Materials. 
650 6 |a Réacteurs à réfrigérant liquide métallique. 
650 6 |a Réacteurs nucléaires  |x Matériaux. 
776 0 8 |i Print version:  |a IAEA  |t Structural Materials for Heavy Liquid Metal Cooled Fast Reactors  |d Vienna : International Atomic Energy Agency,c2021  |z 9789201288219 
856 4 0 |u https://ebookcentral.uam.elogim.com/lib/uam-ebooks/detail.action?docID=30589728  |z Texto completo 
938 |a ProQuest Ebook Central  |b EBLB  |n EBL30589728 
994 |a 92  |b IZTAP 

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