Advanced L WRs

Jacopo Buongiorno

Associa t e Pr of essor of Nuc l ear Science and Engineering

22.06 : Engineering of Nuclear Systems

Outline

Performance goals for near-term advanced LWRs Technical features of advanced LWRs:

- U S-EPR (Evolutionary Pressurized Reactor)

- US - APWR (Advanced Pressurized W ater Reactor)

- AP1000 (Advanced Passive 1000)

- A BWR ( Advanced BWR )

- ESBWR (Economic Simplified BWR) Summar y of common characteristics Conclusions

2

Nuclear Reactor Timeline

3

Mission/Goals f or Advanced LWRs

Baseload generation of electricity (hydrogen is not emphasized)

Improved economics. Targets:

- Increased plant design life (60 years)

- Shorter construction schedule (36 months * )

- Low overnight capital cost (  $1000/kWe** for NOAK plant)

- Low O&M cost of electricity (  1¢/kWh)

* First concrete to fuel loading (does not include site excavation and pre-service testing)

** Unrealistic target set in early 2000s . Current contracts in Europe, China and US have overnight capital costs

>$3000/kWe

Improved safety and reliability

- Reduced need for operator action

- Expected to beat NRC goal of CDF<10 -4 /yr

- R e d uce d l arge re l ease pro b a bilit y

- More redundancy or passive safety

4

U . S . NRC C er t i f i ca t i on o f A d vance d L W R s

U.S. Economic Pressurized Reactor ( US - EPR)

b y A reva

6

US - EPR Overview

1600 MWe PWR

Typical P WR operating conditions in primary system, pressure,

temperatures , etc.

4 loops

linear power ,

Hi g h er pressure i n SG s results in somewhat higher efficiency (35% net)

Safety systems are active High redundancy

7

US - EPR Parameters

US-EPR Safet y

Four identical diesel- driven trains, each 100%, provide redundancy for maintenance or single- failure criterion (N+2)

Physical separation against internal hazards (e.g. fire)

Shield building extends airplane crash and external explosion protection to two safeguard buildings and fuel building (blue walls)

9

US-EPR Safet y ( 2 )

U.S. NRC

Safety Goal

Current U.S. LW R P l a n t s

EPRI Utility Requirement

1 x 10 -4 5 x 10 -5 1 x 10 -5 4 x 10 -7

Core Damage Frequency Per Y ear

10

US-EPR Containment

Inner wall pre-stressed concrete w i t h stee l li ner

Outer wall reinforced concrete

Protection a gainst airplane crash

Protection against external explosions

Annulus sub-atmospheric and filtered to reduce radioisotope release

11

US - E P R S e v e r e A c c i d e n t s M M i i t t i i g g a a t t i i o o n n

IR WST

Corium Spreading Area

E x - vessel core catcher concept (passive)

- Molten core is assumed to breach vessel

- Molten core flows into spreading area and is cooled by IRWST water

- H ydrogen recombiners ensure no detonation within container

12

EPR is bein g built now

Olkiluoto – S eptember 2009 T a ishan – S eptember 2009

Olkiluoto 3 (Finland) - construction start 2004 Flamanville 3 (France) - construction start 2007 Taishan (China) – construction start 2008

Flamanville – O ctober 2009

© source unknown. All rights reserved. This content is excluded from our Creative Commons license. For more information, see http://ocw.mit.edu/fairuse .

U.S. Advanced PWR (US-APWR)

by Mitsubishi

14

US-APWR Overview

(fundamentally similar to US-EPR)

1700 MWe P WR

Typical PWR operating conditions in primary system, pressure,

temperatures , etc .

Long (14 ft.) fuel assemblies with reduced power density for 24 months operation

4 loops

High efficiency turbine (70" blades) results i n > 35% thermal e fficiency of plant

RPV with no bottom penetrations

Safety systems a re active with h igh redundancy

15

US- A PWR Safet y

16

US- A PWR Safet y ( 2 )

Accumulator design with flow damper eliminates need for active high-pressure injection system

S evere acc id en t s m iti ga ti on b ase d on core - ca t c h er concep t similar to US-EPR

17

Advanced Passive 1000 (AP1000)

b y W es ti ng h ouse- T os hib a

18

AP1000 Overview

1100 MWe PWR

T yp ical PWR o p eratin g conditions, pressure, temperature, flow rates, linear power, etc.

RPV with no bottom penetrations

2 loops, 2 SGs

4 recirculation pumps (canned motor pumps, no shaft seals)

Large pressurize r

 50% larger than operating plants

All safety-grade systems

are passive 19

Courtesy of Westinghouse. Used with permission.

A A P P 1 1 0 0 0 0 0 0 P P a a s s s s i i v v e e C o r e C o o l i n g S y s t e m

PRHR HX

 Natural circ. heat removal

Passive Safety Injection

 Core Makeup T anks (CMT)

 Full press, natural circ. inject

 Replaces HPCI pumps

 Accumulators

 Kick in at intermediate pressure

 IR WST Injection

 Low press (replaces LPCI pumps)

 Automatic RCS Depressurization

Courtesy of Westinghouse. Used with permission.

20

A P1000 Passive Containment Coolin g S y stem

21

Courtesy of Westinghouse. Used with permission.

AP1000 Severe Accidents Mitigation

Core-Concrete Interaction

 In- V essel Retention (IVR) / ex-vessel cooling

 Means of cooling damaged core

 T e sts and analysis of IVR reviewed by

U . S . NRC

ST E A M VE N T S

R E AC T O R VESSE L

RE A C TO R V E S S E L S U PP O R T ST E E L

High Pressure Core Melt TYP I C A L 4 PL AC ES

 Eliminated by redundant, diverse ADS

Hydrogen Burn, Detonation

 Hydrogen vent paths from RCS kept away from containment shell

Wa te r

CORE

4.8 m

Vessel

SHI E L D WAL L

IN S U LA T I O N

 Redundant, diverse igniters

Steam Explosions

 Ex-vessel prevented by IVR

Coriu m me lt

W A TE R I N LE T

22 cm W at e r

Courtesy of Westinghouse. Used with permission. 22

AP1000 videos

ECCS

http://ww w .ap1000.westinghousenucl ea r .com/ap1000_psrs_pccs.html

PCCS

http://ww w .ap1000.westinghousenucl ea r .com/ap1000_psrs_pcs.html

IVR

http://ww w .ap1000.westinghousenuclea r .com/ap1000_safety_ircd.html

AP1000 Safety Margins and Risk

T y p i cal P l an t A P 1000

• Los s F l ow M a r g in t o ~ 1 - 5% ~ 1 6% D N B R L i m i t

• F eedline Br e a k ( o F) >0 o F ~ 140 o F S u b c o o l i n g M a r g i n

• S G T u be R u pt ur e O per a t o r ac t i ons O per at or ac t i ons

r e quir ed in 10 m i n NO T re q u i r e d

• Sm a l l LO C A 3 " LO C A < 8 " LO C A

co r e u n co v e r s NO co r e

PC T ~ 1 5 0 0 o F u nc ov er y

• Lar ge LO C A P C T ( o F) 2000 - 2200 o F < 1600 o F

w i th u n c e r ta i n ty (1 )

Courtesy of Westinghouse. Used with permission.

Use o f passive safety systems s implifies the p l a nt

S a f e t y V a l v e s P u m p s S a f e t y P i p e S e i s m i c B u i l d i n g V o l u m e C a b l e R e d u c e d N u m b e r o f C o m p o n e n t s :
		1 0 0 0 M W R e f e r e n c e	A P 1 0 0 0	R e d u c t i o n
	S a f e t y V a l v e s	2 8 4 4	1 4 0 0	5 1 %
	P u m p s	2 8 0	1 8 4	3 4 %
	S a f e t y P i p i n g	1 1 . 0 x 1 0 4 f e e t	1 . 9 x 1 0 4 f e e t	8 3 %
	C a b l e	9 . 1 m i l . f e e t	1 . 2 m i l . f e e t	8 7 %
	S e i s m i c B u i l d i n g V o l u m e	1 2 . 7 m i l . f t 3	5 . 6 m i l . f t 3	5 6 %

Image by MIT OpenCourseWare. 25

…an d R e d uces S a f e t y /S e i sm i c B u ildi ng V o l ume

LE G E N D :

1 . C O NTA I NM E N T/ S H I E L D B U I L DI NG

6 2 . S A F E G U A R D B U I L DI NG

3. F U E L B U I L D I N G

4 . A U X I L I A R Y B U I L DI NG

5 . DI E S E L G E N E R A TO R B U I L DI NG

6. E S S E N T IAL S E R V I C E W A T E R / CI RCU L A T I N G W A T E R P U M P H O U S E

7. L I Q U ID R A D W A S T E B U I L D I N G

2 2

2 4

5 5

2 1 2 1

EP R A P 1000

Sa f e t y /

Se i s m i c St r u ct u r e s

S a f et y / S ei s m i c S t r u c t u r e s

0 20 40 60 80 10 0M

Courtesy of Westinghouse. Used with permission.

26

A P1000 Construction

 Simplification of Systems

 Reduction in bulk materials and field labo r

 Maximum Use of Modularization

 300 rail-shippable equipment and piping modules

 50 l arge s t ruc t ura l mo d u l es ( assem bl e d on-s it e )

- U nder construction at T a ishen (China) since 2008

- 4 P&E orders in US Courtesy of Westinghouse. Used with permission.

Advanced BWR (ABWR) and Economic Simplified B WR (ESBWR)

b y G enera l El ec t r i c- Hit ac hi

28

ABWR O verview

1350 MW e BWR

T y pical BWR operating con diti ons, pressure,

Steam dryer

temperature, linear powe r ,

Steam nozzle

Steam separator

Internal recirculation pumps

Feedwater (no jet pumps) = no external

Fuel assem b lies

loop

Pressure vessel Large vessel with large

water inventory + no large

V e ssel support Control rod piping = no core uncovery

skirt

guide tubes

Redundant active safety

Recirculation pum p

Control rod drives systems

Proven technology (built and operated for over ten years in Japan and T a iwan) 29

Courtesy of GE Hitachi Nuclear Systems. Used with permission.

ESBWR O verview

1550 MW e BWR

T yp i ca l BWR opera ti ng

DP V / I C O u t l et

S t e a m S e par a t or s

R W CU / S DC

Out l e t

IC R e t u r n GDC S I n l e t

Su p p o r t ( s li ding blo c k )

GDC S E q u a l i z i ng L i ne I n l et

Core S h ro ud

Cont rol R od Gui d e T u b e s

I n - c or e H ou s i n g

M a in S t e a m L in e F l o w R e st ri ct o r

RP V S t a b i l i z e r

Fe ed wat e r I n l et

Ch i m n e y

C h i m n e y P arti ti on s Co r e T o p G u i de

Fu el A s s e m b li es C o r e P l a t e

S h r o ud S u p p or t

CR D H o u si n g

C o n t rol R od Dri v es ( C RD)

conditions, pressure, temperature, linear powe r , etc .

Natural circulation reactor = No reactor pumps

Large vessel with large water inventory

Core at lower elevation within vessel

All safety-grade systems are passive

30

Courtesy of GE Hitachi Nuclear Systems. Used with permission.

BWR Primar y S y stem Evolution

D r e s d e n 1 KRB

O y s t er C r eek

Dr es d e n 2

ABWR

SBW R

ES BW R 31

Courtesy of GE Hitachi Nuclear Systems. Used with permission.

ABWR & ESBWR B alance o f P lant is T r aditional

Courtesy of GE Hitachi Nuclear Systems. Used with permission.

32

ABWR & ESBWR Parameters

Courtesy of GE Hitachi Nuclear Systems. Used with permission.

A BWR Safet y

Steam line

CSS

CSS

Feedwater line

HPCF

HPCF

Feedwater line

LPFL

LPFL

LPFL

Supression Pool

LPFL

LPFL

Condensate Storage Pool

Supression Pool

LPFL

SPC

Supression Pool

RHR RHR

SPC

Supression Pool

RHR

RCIC

Division 2 Division 1 Division 3