Advanced Nuclear Energy Systems: Heat Transfer Issues and Trends - - PowerPoint PPT Presentation

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Advanced Nuclear Energy Systems: Heat Transfer Issues and Trends - - PowerPoint PPT Presentation

Jul 05, 2023 384 likes •575 views

Advanced Nuclear Energy Systems: Heat Transfer Issues and Trends Michael Corradini Wisconsin Institute of Nuclear Systems Nuclear Engr. & Engr. Physics University of Wisconsin - Madison n i I s n n s o t i c t s u i W t e

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Wisconsin Institute of Nuclear Systems MIT Rohsenow Symposium on Future Trends in Heat Transfer

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Advanced Nuclear Energy Systems: Heat Transfer Issues and Trends

Michael Corradini Wisconsin Institute of Nuclear Systems Nuclear Engr. & Engr. Physics University of Wisconsin - Madison

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ENERGY SUSTAINABILITY

Conditions Needed for Energy Sustainability:

Economically feasible technology Minimal by-product streams Acceptable land usage “Unlimited” supply of energy resource Neither the power source nor the technology to

exploit it can be controlled by a few nations/regions

Nuclear energy systems meet these conditions and can be part of the solution for future energy growth (Electricity growth estimates range 1 - 4.5%/yr)

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Evolution of Nuclear Power Systems

1960 1970 1980 1990 2000 2010 2020 2030 Gen IV

Generation IV Generation IV

  • Enhanced

Safety

  • More

economical

  • Minimized

Wastes

  • Proliferation

Resistance

  • Enhanced

Safety

  • More

economical

  • Minimized

Wastes

  • Proliferation

Resistance

Gen I

Generation I Generation I Early Prototype Reactors

  • Shippingport
  • Dresden,Fermi-I
  • Magnox

Gen II

Generation II Generation II Commercial Power Reactors

  • LWR: PWR/BWR
  • CANDU
  • VVER/RBMK

Gen III

Generation III Generation III Advanced LWRs

  • System 80+
  • ABWR
  • AP1000
  • ESBWR
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Advanced Light Water Reactors: AP1000-Enhanced Passive Safety

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Advanced Light Water Reactors: ESBWR-Simplified Operation & Safety

Natural Circulation in the Vessel Passive Safety Systems

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Advanced Light Water Reactors: Multiphase Heat Transfer Issues

Passive systems can simplify construction and

  • peration but may complicate engr. analyses

Natural-circulation multiphase flow in complex

geometries (plant geom. dependent)

Condensation heat transfer with non-condensible

gases in reactor containment

Multiphase/multicomponent heat transfer in

safety analyses beyond the ALWR design base

In-vessel lower head cooling & Ex-vessel debris coolability Multiphase/multicomponent direct-contact heat-exchange

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BWR/6 ESBWR ABWR

Steam g

A More Advanced LWR

The next logical step in path toward simplification ? PWR

SCWR

A boiling water reactor …without the boiling.

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SUPERCRITICAL WATER REACTOR

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Heat Transfer in SCW Reactor:

500 600 700 800 900 1000 1100 1200 1300 1400 0.5 1 1.5 2 2.5 3 Height of the core [m] Temperature [K] 5000 10000 15000 20000 25000 30000 35000 40000 Linear heat generation [W/m] Jackson: 1.53 Jackson: 1.34 Jackson: 1.23 Bishop: 1.23 Bishop: 1.34 Bishop: 1.53 Qlinear

P/D

Absence of boiling crisis (CHF), but with heat transfer degradation

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SCW Flow Control and Instabilities

100 200 300 400 500 600 700 800 900 5 10 15 20 25 30 Power (kW ) G (kg/m2s) 20 30 40 50 60 70 80 90 100 110 Temperature (oC) M ass Velocity Hot Side Tem perature

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Nuclear Fuel Recycle

Spent Fuel From Commercial Plants Direct Disposal Conventional Reprocessing PUREX Spent Fuel Pu Uranium MOX LWRs/ALWRs U and Pu Actinides Fission Products Repository Repository Less U and Pu Actinides Fission Products Advanced, Proliferation-Resistant Recycling AFCI ADS Transmuter Trace U and Pu Trace Actinides Less Fission Products Repository Gen IV Fast Reactors Once Through Fuel Cycle European/Japanese Fuel Cycle Advanced Proliferation Resistant Fuel Cycle Gen IV Fuel Fabrication LWRs/ALWRs Advanced Separations

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Liquid-Metal-Cooled Fast Reactor (e.g. LFR)

Characteristics

  • Pb or Pb/Bi coolant
  • 550°C to 800°C outlet

temperature

  • 120–400 MWe

Key Benefit

  • Waste minimization and

efficient use of uranium resources

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Liquid Metal-Water Direct Contact HX

L Lsub Lsat Lsup Liquid Metal

Steam

Advantages:

  • Vigorous interaction between the

liquid metal and the water

  • Excellent contact so smaller volume

is required to transfer the same amount of energy.

  • Potential replacement of IHX loop.

=> Need to determine the local heat transfer coefficient and flow stability for a range of flow rates and regimes.

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Void [cm]

0 .0 0 .1 0 .2 0 .3 0 .4 0 .5 0 .6 0 .0 0 0 .0 5 0 .1 0 0 .1 5 0 .2 0 0 .2 5 0 .3 0

E x p t. P = 0 .1 M p a

αwater

D is ta n c e a b o v e in je c to r z [m ]

DCHT via Xray Imaging

1000 2000 3000 2.5 5 7.5 10 12.5 15 Distance from the Injector [cm] HTC (w/m2K)

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Very-High-Temperature Reactor (VHTR)

Characteristics

  • Helium coolant
  • 1000°C outlet temp.
  • 600 MWth
  • Water-cracking cycle

Key Benefit

  • Hydrogen production

by water-cracking

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GAS-COOLED REACTOR

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Process Heat for Hydrogen Production

N u clear H eat N ucle ar H e at H ydrogen H ydrogen O xyg en O xyg en

H

2

O

2

2 1 9 C 4 C

R ejecte d H ea t 1

C

R e je cte d H e a t 1

C

S (S ulfu r) C ircu la tion

S O

2+H 2O

+

O

2

2 1 H

2S

O

4

S O

2

+ H

2O

H

2O

H

2

I2

+

2H I H

2S

O

4

S O

2+H 2O

H

2O

+ + +

I (Io d in e ) C ircu latio n

2 H I I2

I2

W a te r W ater N u clear H eat N ucle ar H e at H ydrogen H ydrogen O xyg en O xyg en

H

2

O

2

2 1O

2

2 1 2 1 9 C 4 C

R ejecte d H ea t 1

C

R e je cte d H e a t 1

C

S (S ulfu r) C ircu la tion

S O

2+H 2O

+

O

2

2 1 H

2S

O

4

S O

2

+ H

2O

H

2O

H

2

I2

+

2H I H

2S

O

4

S O

2+H 2O

H

2O

+ + +

I (Io d in e ) C ircu latio n

2 H I I2

I2

W a te r W ater L Liquid Metal

Hydrogen CxHy Carbon Recycle

200 C 1000 C Iodine/Sulfuric-Acid Thermochemical Process LM Condensed Phase Reforming (pyrolysis) Aqueous-phase Carbohydrate Reforming (ACR)

H2, CO2

CATALYST AQUEOUS CARBOHYDRATE

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Micro-Nuclear Power Applications (NAE-Blanchard)

Self-Reciprocating Cantilever Wireless Transmitter Micro Thermoelectric or Thermionic Generator

N P

Direct Conversion (Electricity from radiation used to create ion-hole pair in PN Jnc)