Coated Particle Fuels for High‐Temperature Reactors

材料科学 碳化硅 陶瓷 粒子(生态学) 复合材料 核工程 海洋学 地质学 工程类
作者
M.J. Kania,H. Nabielek,Hubertus Nickel
出处
期刊:Materials Science and Technology [Maney Publishing]
卷期号:: 1-183 被引量:15
标识
DOI:10.1002/9783527603978.mst0449
摘要

The article contains sections titled: Introduction History of HTGRs and Coated Particle Fuel Development HTGRs Built and Operated HTGRs Designed but Not Built Modular Reactors (1980 s Design) Current Modular Reactor Designs Coated Particle Fuel Development Development in the UK Development in G ermany Development in the US Recent Directions Fuel Manufacturing Processes Fuel K ernel Manufacture Powder Metallurgical Process Sol–Gel Process Gel‐Precipitation Process for UO 2 Kernels Gel‐Precipitation Process for UCO Kernels Fabrication of PuO 2 Kernels Ceramic Coatings by CVD Pyrolytic Carbon ( PyC ) Coatings Silicon Carbide ( SiC ) Coatings Fuel Element Manufacture Spherical Fuel Elements for Pebble‐Bed Cores Hexagonal‐Block Fuel Elements for Prismatic Cores HTGR Fuel Materials Properties Properties of UO 2 Fuel Kernels Thermal Properties of UO 2 Mechanical Properties of UO 2 Swelling Rate of UO 2 Properties of Pyrolytic Carbon ( PyC ) Coatings Thermal Properties of PyC Theoretical Density of PyC Mechanical Properties of PyC Irradiation‐Induced Dimensional Change of PyC Properties of Silicon Carbide ( SiC ) Coatings Thermal Properties of SiC Mechanical Properties of SiC Swelling Rate of SiC Fuel Quality Control and Performance Evaluation Quality Control of UO 2 Kernels Quality Control of Coated Particles Quality Control of Spherical Fuel Elements Failure Statistics and Performance Requirements The Mathematics of Failure Statistics Statistical Analysis of Fuel Element Manufacture Statistical Analysis of Irradiation Performance Statistical Analysis of Accident Condition Performance Comparison to Performance Requirements Fuel Performance under Normal Operating Conditions Irradiation Testing of Modern UO 2 TRISO‐Coated Particles Accelerated Irradiations in Material Test Reactors HFR ‐ P 4 Test SL ‐ P 1 Test HFR ‐ K 3 Test FRJ 2‐ K 13 Test FRJ 2‐ K 15 Test FRJ 2‐ P 27 Test Conduct of the Accelerated Tests HTR MODUL Proof Tests HFR ‐ K 5 and HFR‐K 6 AVR Real‐Time Irradiation Testing Performance Assessment for Normal Operating Conditions Fuel Performance under Accident Conditions Simulation of Core Heat‐Up after Depressurization under Dry Conditions Analysis of Accident Simulation Testing Behavior after Water and Air Ingress Simulation of Water Ingress Simulation of Air Ingress HTGR Fission Product Generation and Transport Fission Product Generation Fission Product Transport Equivalent Sphere Model for Gas Release Recoil Release from Fuel Kernel Release from Post‐Irradiation Heating Tests Release of Short‐Lived Xe and Kr Isotopes Retention by a Single Coating Layer Release for a Single Shell Diffusion Data for Coating Layers Applicability and Uncertainties of Transport Data Transport and Release from Fuel Elements in Reactor Tests and HTGRs Fission Product Chemistry and CO Generation in UO 2 Coated Particle Failure Mechanisms Pressure‐Induced Failure Internal Gas Pressure Buildup Predicting Pre

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