PRISM Heat Removal Safety Systems
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1 PRISM Heat Removal Safety Systems 5 th IAEA/GIF SFR Safety Workshop David Powell Ph.D. 23/24 June 2015 Copyright 2013 GE Hitachi Nuclear Energy International All rights reserved
2 PRISM: The Commercialization of EBR-II USA s EBR II Small Pool Metal fuel Passive safety EBR-II proved the technology GEH s PRISM Small Pool Metal fuel Passive safety PRISM commercializes the technology Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 2
3 Decades of technology development PRISM related technology programs GE Program PRISM 1988 PRDA ALMR S-PRISM GNEP GE funded Innovative design approaches DOE funded $30M Competitive LMR concepts Advanced Conceptual Design DOE funded $5M Continuing trade studies Development sponsored by US Government Various US development programs since 1985 Nuclear Regulatory Commission: no obvious impediments to licensing DOE funded $42M Preliminary design Regulatory review Economics Commercialization Tech development ($107M additional) PRDA - Program Research & Development Announcement ALMR Advanced Liquid Metal Reactor program GNEP Global Nuclear Energy Partnership GE Funded Improved economics Actinide burning scenarios Demo reactor Actinide burning Commercial Best practices Advanced power conversion cycle PRISM Conceptual Design Document Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 3
4 Fundamentals of reactor safety Controlling Reactivity Decay Heat Removal This presentation focuses on Decay Heat Removal Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 4
5 PRISM decay heat removal Full power block consists of 2 reactors (840 MWt each) that power 1 turbine-generator (622 MWe) Liquid sodium is the reactor coolant, superheated steam drives turbine Each reactor module: 4 primary electromagnetic pumps 2 intermediate heat exchangers 2 secondary electromagnetic pumps 1 steam generator Reactor core inlet/outlet temperatures: 360 o C/500 o C Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 5
6 PRISM safety grade systems Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 6
7 Two methods of heat removal Reactor Vessel Auxiliary Cooling System (RVACS) Auxiliary Cooling System (ACS) RVACS Flow Paths Air Outlet Inlet Plenum Overflow Flow Path Both Safety Systems Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 7
8 Auxiliary Cooling System (ACS) Removes decay heat from Steam Generator shell via natural circulation Reduce the primary system temperature following a loss of heat sink (Turbine Condenser) Increase plant availability by reducing the reactor cool down time when heat cannot be rejected to the condenser Cooling can be augmented and increased with safety power Steam Generator System ACS EM Pumps Intermediate Heat Transfer System Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 8
9 ACS flow path Fan driven by safety power Air flows into the annulus between the bottom of the shroud and Steam Generator shell Natural circulation is initiated by opening the exhaust damper so that air receives heat by thermal radiation from the steam generator shell The intermediate sodium loop, like the primary loop, operates under natural circulation conditions and thus requires no power for core decay heat removal ACS Flow Path External air Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 9
10 ACS Auxiliary Fan Auxiliary fan located in the exhaust stack can be activated in order to increase the heat removal rate Fan is only started if additional heat removal capacity is required to reduce the system temperature for maintenance Fan is powered by two sources of power: power generation bus and safety batteries Vent above the root line Auxiliary Fan Insulating Shroud Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 10
11 PRISM safety heat removal Combination of the ACS and the RVACS system has the capability to maintain the reactor temperatures well below design limits (1250F Upset Conditions). ACS and RVACS provide two safety grade heat removal systems PRISM decay heat removal architecture is robust for global enveloping of SFR standards NUREG 1368 The three systems that can provide RHR are quite reliable and appears difficult to disable all three systems Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 11
12 Thank You PRISM Copyright 2015 GE Hitachi Nuclear Energy International, LLC - All rights reserved 12
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