고온 발전소와 수소 시스템

포항공과대학교
Shripad T. Revankar

페이스북 트위터 카카오톡 네이버밴드 링크복사

주제분류

공학 >정밀ㆍ에너지 >원자력공학
강의학기

2013년 1학기

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4,904

이 강좌는 원자력 및 그와 관련된 시스템 중 수소생산영역을 집중 강의한다.

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introduction

차시별 강의

1.	introduction	introduction to global energy, primary energy sources, and issues with fossil fuels
	thermal nuclear reactors	current light water thermal reactor systems, their design and operational parameters
2.	high temperature reactors, GEN IV Reactors	hydrogen and as energy carrier, hydrogen economy, nuclear heat and electrical driven hydrogen generation systems
	hydrogen economy, nuclear hydrogen system	nuclear power plant heat source, decay heat, reactor heat transport systems, power conversion, intermediate heat exchanger, process heat exchangers
3.	nuclear reactor heat source, IHX	hydrogen production with steam methane reformation, water shift reactor, process parameters, conversion efficiency
	hydrogen generation via steam reformation process	high temperature thermochemical based hydrogen generation, various chemical intermediates, electrochemical processes
4.	thermochemical cycles overview	sulfur based thermochemical process, sulfur iodine cycle, Westinghouse hybrid cycle, process flow sheets, operating conditions and reaction details
	SI cycle, HyS cycle	non-sulfur thermochemical cycles, university of Tokyo cycle, calcium chloride, calcium bromide cycle, high temperature electrolysis
5.	UT-3, High Temp. Electrolysis	nuclear reactor heat coupling to hydrogen production schemes, heat and temperature matching to thermochemical process conditions thermal efficiency
	H2 production Processes Heat matching, efficiency	nuclear hydrogen system schemes, heat and temperature matching to thermochemical process conditions, thermal efficiency
6.	IHX Systems nuclear H2 R&D projects	nuclear hydrogen system schemes, intermediate heat exchanger, process heat exchanger, design parameters, global programs in nuclear hydrogen
	prismatic HTGR, PBMR	high temperature gas cooled reactors, pebble bed modular reactor, prismatic pebble bed, design and operating parameters
7.	VHTR, GFR, LFR	very high temperature reactor, gas cooled fast reactor, liquid metal cooled fast reactor design and operating conditions
	MSR, SCWR	molten salt cooled reactor, supercritical water reactor, design and operating parameters
8.	Kinetics model-point kinetic model	neutronic model for nuclear reactor core, neutron transport equation, point kinetics model
	neutronic kinetic codes	reactor physics codes, reactor kinetics models, regulatory and commercial code structure, 2-D and 3-D neutronic codes, PARCS
9.	thermal-hydraulics analysis, 3-D TH codes	nuclear reactor cooling, thermal hydraulics analysis, codes, 3-D and 1-D thermal analysis codes, RELAP5, THERMIX
	safety analysis	Reactor safety, defense in depth, safety philosophy, analysis methods
10.	HTR fuels and performance	high reactor fuels, TRISO fuel, fuel performance
	HTR materials issues, advanced materials	high temperature reactor vessel, core and other component materials and issues, advanced materials for high temperature and radiation environment
11.	energy conversion systems-Brayton Cycle	high temperature reactor energy conversion systems, Brayton Cycle, cycle efficiency
	ECS control system	high temperature reactor energy conversion control system, coolant inventory, coolant bypass methods
12.	coupled HTR and hydrogen plant-simplified models	coupled high temperature reactor and hydrogen plant, models for HTGR neutronic and thermal hydraulics, and hydrogen plant chemical models-simplified models
	coupled HTR-H2plant dynamics	dynamic analysis of coupled HTR and hydrogen plant, accident analysis
13.	Safety in a process heat HTR	high temperature reactor safety, heat transfer through process heat exchanger
	HTR licensing issues, PIRT	phenomena identification and ranking table, HTR licensing issues
14.	Market potential, review for final exam	nuclear hydrogen commercialization
	Project I	nuclear hydrogen system components, design projects
15.	Project II	nuclear hydrogen system components, design projects, models, reviews
	Project III	nuclear hydrogen system, components safety, analysis