Thermal Hydraulic Design Requirements in Safety Analysis: Transients & Accidents
Course 22.39, Lecture 4 9/18/06
Professor Neil Todreas
Reactor Safety Fundamentals
Goal: Prevent Fission Product Release to the Environm ent
Concepts to Insure Core Cooling
PWR – A P600
Courtesy of Regis Matzie. Used with permission.
Concepts to Dump Heat to Ultimate Heat Sink
Schem a tic View of the AP-600 Reactor Concept, showing the containm ent building and associated cooling systems
Courtesy of Regis Matzie. Used with permission.
Heat/Mass Transfer Model
Court e sy of U.S. DOE.
Schematic View of the IFR/ALMR Reactor Concept, showing the reactor coolant and major safety systems
Severe Accident Issues Resolved
• C ore debris coolability
• H ydrogen burning
• D irect containment heating
• C ore concrete interaction
• Steam explosions
Core Debris Chamber and Cavity Exit Pathway on System 80+ Design
Courtesy of Regis Matzie. Used with permission.
Containment Atmosphere Hydrogen
Control in System 80+ Design
• 8 0 Igniters located in pathways of generated hydrogen
• Approximately half are battery- backed
Courtesy of Regis Matzie. Used with permission.
9/18/06 Course 22.39, Lecture 4 12
System 80+ Cavity Flooding System
Courtesy of Regis Matzie. Used with permission.
9/18/06 Course 22.39, Lecture 4 13
Paradigm – A ltering Safety Assurance Differences *
PWR |
G FR |
LM R |
Coolant is high pressure (15 MPa ), H 2 O liq uid; Lo w boi l i ng po in t, Good h eat trans f er |
Coolant is high pressure (7-20 MPa), G as: He, CO 2 ; Medioc re heat trans f er |
Coolant is low pressure ( ï‚£ 0.5 MPa ) , L i qu id met a l: Na, P b ; Hi g h b o iling p o i n t, Excellent heat trans f er |
Som e fract io n of coo l in g i nven to r y rem a ins afte r LO C A |
>98% of coolant escapes in a com p le te depressurization |
Use of guard vessel re tains adequate liquid inventory in reactor vessel |
Large liquid reflood reservoir is ava i lable; Bo i lin g and heat of v a p ori zati o n facilit ate co o lin g |
Lim i ted high pressure gas injec t ion available ; A t low pressure only a i r available in la rge am ount |
Can design for pass ive decay heat rem oval by natura l convect ion to am bi ent a i r or water |
P o st-L O C A g o al i s ti mely red u c ti on of conta i nm ent pressure to re duce leakage Reducing p r e ssure af te r sh ut down does no t n e g a ti v e ly i m p act co ol ability |
Maintainin g h i g h pressure facilitates lon g term cooling, es pecially via natura l convection Lo w pressure is a l way s detrim enta l to heat tran sfer an d tran sp o r t; Co o l i ng cap ability is proportiona l to pressure; Adequate natura l convection only at several atm o sphe res |
Sy s t em is low pressure |
Refueling under water at 1 atm can re ly on an effective pass ive heat s i nk; Visual observa t i on p o ss ib le |
Cool ing du r i n g depres sur i z e d refue l i ng i s challenging; Refueling a t high pressure creates m o re L O C A seque nces; Visua l observa t i on p o ss ib le |
Refueling is at low press ure, but blind; H eat rem oval is assured |
Benign reactor phys ics characteris tics ; Negative coolant void reactivity (in c o m m on with m o st the r m a l reactors) |
Sm all de la y e d neu tr on fra ct ion and Dopp ler reactivity; Positive coolant void reactivity (in com m on with a l l fas t reactors ) ; Fue l co mp act io n an d recriti cality |
Sm all de la y e d neu tr on fra ct ion ; Mo des t Doppler reactivity; Large loca l pos itive void reactivity; Fuel com p action and recriti cality |
9/18/06 Course 22.39, Lecture 4
*Driscoll, 12/05 14
Paper Reactors, Real Reactors
9/18/06 Course 22.39, Lecture 4 15