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LOCA/LOFA Analyses for Blanket and Shield Only Regions – LiPb/FS/He System Carl Martin, Jake Blanchard Fusion Technology Institute University of Wisconsin - Madison ARIES-CS Project Meeting February 24-25, 2005

LOCA/LOFA Analyses for Blanket and Shield Only Regions – LiPb/FS/He System

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LOCA/LOFA Analyses for Blanket and Shield Only Regions – LiPb/FS/He System. Carl Martin, Jake Blanchard Fusion Technology Institute University of Wisconsin - Madison ARIES-CS Project Meeting February 24-25, 2005. LOCA/LOFA Analysis Update. - PowerPoint PPT Presentation

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Page 1: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

LOCA/LOFA Analyses for Blanket and Shield Only Regions –

LiPb/FS/He System

Carl Martin, Jake Blanchard

Fusion Technology InstituteUniversity of Wisconsin - Madison

ARIES-CS Project MeetingFebruary 24-25, 2005

Page 2: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

LOCA/LOFA Analysis Update

1. Results from LOCA/LOFA models with the gap between blanket and shield removed. The interface has been replaced with a perfect contact condition.

2. Maximum temperatures for LOCA and LOFA as a function of are presented to help establish thermal operating limits.

3. Preliminary results for the shield only regions will be discussed.

Page 3: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

ANSYS FE Model and Boundary Conditions for Thermal Analyses

Blanket Shield Vacuum Vessel

First WallTinit = 500 C

LiPBTinit = 625 C

Back WallTinit = 450 C

ShieldTinit = 450 C

Vacuum VesselTinit = 100 C

Gap

Rad

ius

= 2 .

0 m

Ferritic Steel Boronated Ferritic Steel LiPb

H20

H20

H20

• Adiabatic boundary at back of vacuum vessel.• Model is axisymmetric about plasma centerline and symmetric on sides. Gap

between blanket and shield replaced with perfect contact condition.• Emissivity of 0.3 assumed across vacuum gap and vacated cooling channels.• All analyses assume there is no helium in channels.

Page 4: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

Thermal Results LOFA for LiPb and Water and LOCA for He

740 C temp limit

1 cm Gap Between Blanket and ShieldMaximum temperature – 715 C

1 s 1 m 1 h 1 d 1 mo

740 C temp limit

Perfect Contact Between Blanket and ShieldMaximum temperature – 701 C

1 s 1 m 1 h 1 d 1 mo

• Model modified to remove vacuum gap between blanket and shield to agree with current configuration.

• Maximum temperature is 14 C lower with gap removed and perfect contact assumed.

Page 5: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

Thermal Response for LOCA in Blanket/Shield and LOFA in Vacuum Vessel

• Maximum temperature is 23 C lower with ideal contact between blanket and shield compared to 1 cm vacuum gap case.

• Maximum temperature is higher for LOCA (706 C) compared to LOFA (701 C).

Perfect Contact Between Blanket and ShieldMaximum temperature – 706 C

740 C temp limit

1 s 1 m 1 h 1 d 1 mo

740 C temp limit

1 cm Gap Between Blanket and ShieldMaximum temperature – 729 C

1 s 1 m 1 h 1 d 1 mo

Page 6: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

Thermal Results for Fusion Power Scaled by 1.5

740 C temp limit

LOCA for LiPb

801 C max 740 C temp limit

LOFA for LiPb

760 C max

1 s 1 m 1 h 1 d 1 mo1 s 1 m 1 h 1 d 1 mo

• Maximum temperatures for ratio =1.5 exceed 740 C FS limit.• Again, maximum temperature is higher for LOCA than LOFA.

Page 7: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

680

700

720

740

760

780

800

820

1.75 2 2.25 2.5 2.75 3 3.25

Average Neutron Wall Loading (MW/m2)

Max

imum

Tem

pera

ture

(C)

LOCA

LOFA

740 C temp limit

Variation of Maximum Temperature with

Maximum Temperature vs

• 740 C FS limit exceeded for > 2.3 MW/m2 with current configuration

Page 8: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

Shield Only Zone Analysis

FW BW Vacuum Vessel WC-Shield-II WC-Shield-I Gap

H20

H20

H20

FEA ModelAssumes shield only region about entire radius (conservative temperature estimate)

Replaceable

Pla

sma

Page 9: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

LOCA Thermal Results for Shield Only Region

Max. Temp – 1427 Cat 1 day

740 C temp limit

• Maximum temperature of 1427 C occurs after 24 hours.• Natural convection to water in vacuum vessel included.• Emissivity of 0.3 assumed for radiation in vacuum gap.• Initial temperatures of 500 C assumed for 1st wall and WC, 450 C for

cooling channels, and 100 C for vacuum vessel.

1 s 1 m 1 h 1 d 1 mo

Page 10: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

Temperature Distribution at t = 1Day

Vacuum gap T = 880 C

• Large gradient occurs across vacuum gap (=0.3 assumed).• Temperature gradients across Shield II and gap confirmed with hand calculations.

Page 11: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

Variation of Maximum Shield Temperature with Gap Emissivity

800

900

1000

1100

1200

1300

1400

1500

0 0.2 0.4 0.6 0.8 1

Gap Emissivity

Max

imum

Tem

pera

ture

(C)

• Increasing emissivity across can not reduce temperatures to acceptable levels.

• 3-D analysis with transition regions are required to properly analyze region.• Passive system may be required to achieve temperature limits.

Page 12: LOCA/LOFA Analyses for Blanket and Shield Only Regions –  LiPb/FS/He System

Summary and Future Plans

1. Removal of the gap between the vacuum and shield reduced the maximum temperatures by 14-23 C for LOCA/LOFA cases.

2. should not exceed 2.34 MW/m2 to keep blanket FS temperature below 740 C during LOCA/LOFA for current configuration.

3. Blanket and shield model is to be updated to latest configuration and temperature limits/design sensitivity will be further evaluated.

4. Shield only region temperatures greatly exceed limits. Increasing emissivity does not solve problem. Passive safety system may be needed.

5. A full 3-D model of shield only and transition regions will be developed to further investigate this problem.