CFD Contributions to the Renaissance in US Nuclear Power Industry - - PowerPoint PPT Presentation

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CFD Contributions to the Renaissance in US Nuclear Power Industry - - PowerPoint PPT Presentation

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CFD Contributions to the Renaissance in US Nuclear Power Industry Eri ric V Vol olpenhei penhein, n, P P. E. eric.vo volpen penhei hein@ n@us. us.cd cd-adap dapco co.co com June 23, une 23, 2009 2009 30 years ago. Most

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SLIDE 1

CFD Contributions to the Renaissance in US Nuclear Power Industry

Eri ric V Vol

  • lpenhei

penhein, n, P

  • P. E.

eric.vo volpen penhei hein@ n@us. us.cd cd-adap dapco co.co com June 23, une 23, 2009 2009

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SLIDE 2

2

30 years ago….

  • Most severe accident in commercial nuclear power

industry (Three Mile Island)

– No significant release and no injuries – Awakening to the importance of human factors

  • Received BS Nuclear Engineering….oops!
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SLIDE 3

3

Next 30 years….

  • No nuclear plants ordered for the US Market
  • More plants cancelled than built
  • Nevertheless, until recently, power from nuclear

increased each year at a faster pace than during the peak period of plant startup

– power up-ratings, increased capacity factors

(extended fuel cycles, outage management, preventative maintenance, root cause investigations, and rigorous risk management)

  • New licensing process [COL] developed
  • International shift in technology and resources
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SLIDE 4

And nd Tod Today ay?

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SLIDE 5

5

Status of New Reactors in US

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SLIDE 6

6

  • DOE guaranteed loans to four companies for estimated 7

new nuclear reactors on-line by 2016 (May 2009)

  • Shaw Group receives full notice to proceed on two new

reactors from Southern Nuclear. These will serve as the Reference COL for Westinghouse / Toshiba AP1000 (April 2009)

– Progress Energy (Jan 2009) – SCANA / Santee Cooper (May 2008)

Other Recent Developments

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SLIDE 7

7

STAR-CCM+ / CD Licensing Revenue U.S. Nuclear Industry

1 2 3 4 5

2003 2004 2005 2006 2007 2008 2009 Normalized Revenue

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SLIDE 8

But ut….

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SLIDE 9

9

Formidable challenges remain….

  • “We may not need any new [large base load] plants, ever!” – Jon

Wellinghoff, chairman Federal Energy Regulatory Commission, April 22, 2009

  • Yucca Mountain project effectively stopped
  • Price of fossil fuels highly volatile => public support for nuclear power is

high but decreasing

  • Uncertainty in financial markets
  • Carbon cap & trade evolving
  • Safety & security
  • Waste management
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SLIDE 10

Applications in the Nuclear Pow er Industry

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SLIDE 11

11

Nuclear Fuel Assembly

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SLIDE 12

12

Fuel Performance

Nuclear fuel design

CHF Prediction Pea Peak Pow Power Per Performance Heat T Transf sfer Optimi mization Loca cal Fl Flow De Deta tail

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13

Phenomenological Investigations – Anisotropic Turbulence and Unsteady Flow

0.5 1 1.5 5 10 15 20 25 30 Experimental Standard k-ε Anisotropic k-ε (steady calc.) Anisotropic k-ε (Unsteady)

τ rel

θ degrees

The reproduction of the large scale oscillations in the numerical simulation, combined with the accurate anisotropic modeling lead to excellent agreement with experimental results.

Nuclear fuel design

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SLIDE 14

14

Coupled CFD / Neutronics (Courtesy ANL) Nuclear fuel design

¼ core height

Core Exit Power Density Void Fraction

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SLIDE 15

15

Courtesy of: J.A. Fort, Pacific Northwest National Laboratory

  • C. Bajwa, U.S. Nuclear Regulatory Commission

Heat Transfer in Spent Fuel Transfer Cask Neutron Shields

Spent Fuel Transfer Cask Simulation

Spent Fuel Storage and Transportation

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SLIDE 16

16

Spent Fuel Storage

  • Continuous modification of storage inventory.
  • Varying decay heat and design of casks.
  • Varying external conditions.
  • Requires periodic re-evaluation of flow and thermal

conditions.

Spent Fuel Storage and Transportation

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SLIDE 17

17

Spent Fuel Storage

  • Accurate storage simulations can

be run in 24 hrs.

  • The process can be fully

automated for run and report.

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SLIDE 18

18 18

Boron Distribution

Mixing

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SLIDE 19

19

Thermal Stratification, Cycling, and Striping - Industrial LES

  • Capability of introducing 3-dimensional

structures at turbulent inlets.

  • Choice of efficient and validated

subgrid scale models (WALE).

  • Adequate fully automated grid

generation.

  • Availability of resolved wall as well as

all Y+ implementations.

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 0.02 0.04 0.06

Averag age P e Passi sive ve S Scalar ar

Mixing

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SLIDE 20

20

Large e scal ale e struc uctur ures are computed by URA RANS NS (coher

  • heren

ent term)

The he incoher

  • herent t

ent term is rel elated ated to to the the fl fluc uctu tuation of

  • f

con

  • ncentr

trati tion gi given en by by the the inher nherent natur t nature of

  • f

turbul ulenc ence. e.

  • E. Merzari, H. Ninokata, E. Baglietto - 2008

Addi dditional equa equation for

  • r the

he tran ansport of

  • f

the he var ariance of

  • f the

he scalar conc ncen entration.

  • n.

Thermal Stratification, Cycling, and Striping - URANS Approach

Mixing

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SLIDE 21

21 21

Safety injection / thermal mixing

 Safety injection during LOCA  VOF model with HRIC

Gas Entrainment

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SLIDE 22

22

22

  • E. Merzari, H. Ninokata, Tokyo Institute of Technology
  • E. Baglietto, CD-adapco

Free-surface vortices

Gas Entrainment

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SLIDE 23

23 23

Location Diff ∆P err (%)

Pin

= =

P1

  • 0.006
  • 1.4%

P2

  • 0.001
  • 0.2%

P3

  • 0.018
  • 3.1%

Jet Pump Model Validation / Calibration

Jet Pump Validation

Component Performance

Pin P1 P2 P3

STAR-CD

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SLIDE 24

24

Steam Separator

Component Performance

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SLIDE 25

25

Pressurizer Heater Rods

Component Performance

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SLIDE 26

26

Containment Hydrogen – STAR-CCM+ and DARS

200 400 600 800 1000 5 10 Experiment

Flam ame Speed peed

Hydrogen Deflagration

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SLIDE 27

27

High Temperature Gas Reactor Licensing

Next Generation Nuclear Plant

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SLIDE 28

28

Advanced Burner Reactor

Advanced Fuel Cycle Initiative

Cou

  • urtesy of
  • f R. Wigel

geland & & K.

  • K. Ham

amman, I INL, L, t to

  • be

be pr pres esented at at Gl Global 2009 2009, Par Paris, F Fran ance

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SLIDE 29

29

High Performance CFD / FEA In Nuclear Engineering

Sing ngle phas phase fl flow

  • w

+ N Neutr eutron

  • nics

Two

  • phas

phase fl flow

  • w

+ C Conjugat ugate e heat heat tr trans ansfer + L + LES ES

Com

  • mpl

plex ex Phy hysics cs Com

  • mpl

plex ex Geome metry ry

Chann hannel Com

  • mpl

plete te fuel fuel assem embl bly Whol hole c cor

  • re

Spac acer er + B Boil ilin ing