[PPT] - High Temperat ure Gas React ors The Next Generat ion ? Prof essor PowerPoint Presentation

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High Temperat ure Gas React ors The Next Generat ion ?

Prof essor Andrew C Kadak Massachuset t s I nst it ut e of Technology

Argonne Nat ional Laborat ory J uly 14, 2004

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Fundamentals of Technology

Use of Brayton vs. Rankine Cycle
High Temperature Helium Gas (900 C)
Direct or Indirect Cycle
Originally Used Steam Generators
Advanced Designs Use Helium w/wo HXs
High Efficiency (45% - 50%)
Microsphere Coated Particle Fuel

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History of Gas Reactors in US

Peach Bottom (40 MWe) 1967-1974
First Commercial (U/Thorium Cycle)
Generally Good Performance (75% CF)
Fort St. Vrain ( 330 MWe) 1979-1989 (U/Th)
Poor Performance
Mechanical Problems
Decommissioned

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Fort St. Vrain

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Different Types of Gas Reactors

Prismatic (Block) - General Atomics
Fuel Compacts in Graphite Blocks
Pebble Bed - German Technology
Fuel in Billiard Ball sized spheres
Direct Cycle
Indirect Cycle
Small Modular vs. Large Reactors

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GT-MHR Module General Arrangement

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GT-MHR Combines Meltdown-Proof Advanced Reactor and Gas Turbine

SLIDE 8

Flow through Power Conversion Vessel

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TRISO Fuel Particle -- “Microsphere”

0.9mm diameter
~ 11,000 in every pebble
109 microspheres in core
Fission products retained inside

microsphere

TRISO acts as a pressure vessel
Reliability

– Defective coatings during manufacture – ~ 1 defect in every fuel pebble

Microsphere (0.9mm) Fuel Pebble (60mm) Matrix Graphite Microspheres

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Fuel Components with Plutonium Load

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Comparison of 450 MWt and 600 MWt Cores

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PBMR Thermal Cycle

HP Turbo- compressor LP Turbo- compressor

Generator

Intercooler Precooler Recuperator Demin water circ pump Heat Exchanger Demin to Seawater Sea water OUT Sea water IN

Helium inlet 198.4 kg/sec Helium outlet 33.2°C 2920 kPa Helium

utlet 5616 kPa

31.6°C 1.26 m3/sec 49°C

Demin Water Discharge 21°C 1.48 m3/sec 18°C 40°C

2942 kPa 143.8°C 135°C 193.1 kg/sec

Heliu m Wate KEY

7160 kPa 802.5°C 8663 kPa 900°C 5267 kPa 678.6°C 7002 kPa 97.7°C 2994 kPa 495.8°C

Power Turbine

8954 kPa 482.4°C

Reactor

r

as at Oct 2002

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Power output: 400MWt 165 MWe Coolant: Helium Coolant pressure: 9 MPa Outlet temperature: 900°C Net cycle efficiency: >41%

Main Power System

Inter-cooler Pre-cooler Recuperator T/G LPT HPT CCS Reactor CBCS

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Integrated Plant Systems

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Differences Between LWRS

Higher Thermal Efficiencies Possible
Helium inert gas - non corrosive
Minimizes use of water in cycle
Utilizes gas turbine technology
Lower Power Density
Less Complicated Design (No ECCS)

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Advantages & Disadvantages

Advantages

Higher Efficiency
Lower Waste Quantity
Higher Safety Margins
High Burnup
100 MWD/kg

Disadvantages

Poor History in US
Little Helium Turbine

Experience

US Technology Water

Based

Licensing Hurdles due

to different designs

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Advanced Nuclear Energy Plants (Generation IV)

Competitive with Natural Gas
Demonstrated Safety
Proliferation Proof
Disposable High Level Waste Form
Used Internationally to Meet CO2 Build-Up

in the Environment

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International Activities

Countries with Active HTGR Programs

China - 10 MWth Pebble Bed - 2000 critical
Japan - 40 MWth Prismatic
South Africa - 250 MWth Pebble - 2006
Russia - 290 MWe - Pu Burner Prismatic

2007 (GA, Framatome, DOE, etc)

Netherlands - small industrial Pebble
Germany (past) - 300 MWe Pebble Operated
MIT - 250 MWth - Intermediate Heat Exch.

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Pebble Bed Modular Reactor

South Africa

165 MWe Pebble Bed Plant - ESKOM
Direct Helium High Temperature Cycle
In Licensing Process
Schedule for construction start 2006/7
Operation Date 2010
Commercial Reference Plant

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AVR: Jülich

15 MWe Research Reactor

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THTR: Hamm-Uentrop

300 Mwe Demonstration Reactor

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Modular High Temperature Gas Reactor Russia

General Atomics Design
290 MWe - Prismatic Core
Excess Weapons Plutonium Burner
In Design Phase in Russia
Direct Cycle
Start of Construction - 2007

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High Temperature Test Reactor

Japan

40 MWth Test Reactor
First Critical 1999
Prismatic Core
Intermediate Heat Exchanger
Currently in Testing for Power Ascension

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High Temperature Test Reactor

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High Temperature Reactor

China

10 MWth - 4 MWe Electric Pebble Bed
Under Construction
Initial Criticality Dec 2000
Intermediate Heat Exchanger - Steam Cycle

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HTR- 10 China First Criticality Dec.1, 2000

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Modular Pebble Bed Reactor

MIT/INEEL

Pebble Bed Design
120 MWe
Intermediate Heat Exchanger

Helium/Helium

Similar Core Design to ESKOM
Balance of Plant Different

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Project Objective

Develop a sufficient technical and economic basis for this type of reactor plant to determine whether it can compete with natural gas and still meet safety, proliferation resistance and waste disposal concerns.

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Modular High Temperature Pebble Bed Reactor

110 MWe
Helium Cooled
“Indirect” Cycle
8 % Enriched Fuel
Built in 2 Years
Factory Built
Site Assembled
On-line Refueling
Modules added to

meet demand.

No Reprocessing
High Burnup 90,000

MWd/MT

Direct Disposal of

HLW

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What is a Pebble Bed Reactor ?

360,000 pebbles in core
about 3,000 pebbles

handled by FHS each day

about 350 discarded daily
one pebble discharged

every 30 seconds

average pebble cycles

through core 15 times

Fuel handling most

maintenance-intensive part

f plant

SLIDE 32

Fuel Sphere Half Section Coated Particle Fuel

Dia. 60mm
Dia. 0,92mm

Dia.0,5mm 5mm Graphite layer Coated particles imbedded in Graphite Matrix

Pyrolytic Carbon Silicon Carbite Barrier Coating Inner Pyrolytic Carbon Porous Carbon Buffer

40/1000mm 35/1000 40/1000mm 95/1000mm

Uranium Dioxide

FUEL ELEM ENT DESIGN FOR PBM R

32

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Core Neutronics

Helium-cooled, graphite

moderated high-temp reactor

~360,000 fuel balls in a

cylindrical graphite core

central graphite reflector
graphite fuel balls added and

removed every 30 s

recycle fuel balls up to 15

times for high burnup

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MPBR Side Views

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MPBR Core Cross Section

A Pebble Bed Core B Pebble Deposit Points C Inner Reflector D Outer Reflector E Core Barrel F Control Rod Channels G,H Absorber Ball Channels I Pebble Circulation Channels J Helium Flow Channels K Helium Gap L Pressure Vessel

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Reactor Unit

Helium Flowpath

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Fuel Handling & Storage System

Fuel/Graphite Discrimination system Damaged Sphere Container Graphite Return Fresh Fuel Container Fuel Return Spent Fuel Tank

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Fuel Handling System

Reactor Vessel in this Area - Not shown Fresh Fuel Storage Used Fuel Storage Tanks

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MPBR Specifications

Thermal Power 250 MW Core Height 10.0 m Core Diameter 3.5 m Pressure Vessel Height 16 m Pressure Vessel Diameter 5.6 m Number of Fuel Pebbles 360,000 Microspheres/Fuel Pebble 11,000 Fuel UO2 Fuel Pebble Diameter 60 mm Fuel Pebble enrichment 8% Uranium Mass/Fuel Pebble 7 g Coolant Helium Helium mass flow rate 120 kg/s (100% power) Helium entry/exit temperatures 520oC/900oC Helium pressure 80 bar Mean Power Density 3.54 MW/m3 Number of Control Rods 6 Number of Absorber Ball Systems 18

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Features of Current Design

Three-shaft Arrangement Power conversion unit 2.96 Cycle pressure ratio 900°C/520°C Core Outlet/Inlet T 126.7 kg/s Helium Mass flowrate 48.1% (Not take into account cooling IHX and HPT. if considering, it is believed > 45%) Plant Net Efficiency 120.3 MW Net Electrical Power 132.5 MW Gross Electrical Power 250 MW Thermal Power

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Indirect Cycle with Intermediate Helium to Helium Heat Exchanger

Current Design Schematic

Generator

522.5°C 7.89MPa 125.4kg/s 509.2°C 7.59MPa 350°C 7.90MPa

Reactor core

900°C 7.73MPa 800°C 7.75MPa 511.0°C 2.75MPa 96.1°C 2.73MPa 69.7°C 8.0MPa 326°C 105.7kg/s 115 °C 1.3kg/s 69.7°C 1.3kg/s 280 °C 520°C 126.7kg/s

Circulator HPT

52.8MW

Precooler Inventory control Bypass Valve Intercooler IHX Recuperator Cooling RPV

LPT 52.8MW PT 136.9MW 799.2 C 6.44 MPa 719.°C 5.21MPa MPC2 26.1 MW MPC1 26.1MW LPC 26.1 MW HPC 26.1MW 30 C 2.71MPa 69.7 C 4.67MPa

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Features of Current Design

Three-shaft Arrangement Power conversion unit 2.96 Cycle pressure ratio 900°C/520°C Core Outlet/Inlet T 126.7 kg/s Helium Mass flowrate 48.1% (Not take into account cooling IHX and HPT. if considering, it is believed > 45%) Plant Net Efficiency 120.3 MW Net Electrical Power 132.5 MW Gross Electrical Power 250 MW Thermal Power

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1150 MW Combined Heat and Power Station

Turbine Hall Boundary

Admin Training Control Bldg. Maintenance Parts / Tools

10 9 8 7 6 4 2 5 3 1

0 20 40 60 80 100 120 140 160 20 40 60 80 100

Primary island with reactor and IHX Turbomachinery

Ten-Unit VHTR Plant Layout (Top View)

(distances in meters)

Equip Access Hatch Equip Access Hatch Equip Access Hatch

Oil Refinery Hydrogen Production

Desalinization Plant VHTR Characteristics

Temperatures > 900 C
Indirect Cycle
Core Options Available
Waste Minimization

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Modularity Progression

Conventional Nuclear Power Systems
Assembled on site
Component-level transportation
Extensive Site Preparation
Advanced Systems
Mass Produced / “Off the Shelf” Designs
Construction / Assembly Still Primarily on Site
MPBR
Mass Produced Components
Remote Assembly / Simple Transportation &

Construction This is different than other Generation IV approaches in that modularity is the objective which means smaller units.

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MPBR Modularity Plan

Road- Truck / Standard-Rail Transportable

– 8 x 10 x 60 ft. 100,000 kg Limits

Bolt-together Assembly

– Minimum labor / time on site required – Minimum assembly tools – Goal: Zero Welding

Minimum Site Preparation

– BOP Facilities designed as “Plug-and-Play” Modules – Single Level Foundation – System Enclosure integrated into modules

ASME Code compliant

– Thermal expansion limitations – Code material limitations

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Design Elements

Assembly
Self-locating Space-frame Contained Modules and

Piping.

Bolt-together Flanges Join Module to Module
Space-frame Bears Facility Loads, No Additional

Structure

Transportation / Delivery
Road-mobile Transportation Option

– Reduces Site Requirements (Rail Spur Not Required)

Module Placement on Site Requires Simple Equipment
Footprint
Two Layer Module Layout Minimizes Plant Footprint
High Maintenance Modules Placed on Upper Layer

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Top Down View of Pebble Bed Reactor Plant

IHX Module Reactor Vessel Recuperator Module Turbogenerator HP Turbine MP Turbine LP Turbine Power Turbine HP Compressor MP Compressor LP Compressor Intercooler #1 Intercooler #2 Precooler ~77 ft. ~70 ft. Plant Footprint

TOP VIEW WHOLE PLANT

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Total Modules Needed For Plant Assembly (21): Nine 8x30 Modules, Five 8x40 Modules, Seven 8x20 Modules Six 8x30 IHX Modules Six 8x20 Recuperator Modules 8x30 Lower Manifold Module 8x30 Upper Manifold Module 8x30 Power Turbine Module 8x40 Piping & Intercooler #1 Module 8x40 HP Turbine, LP Compressor Module 8x40 MP Turbine, MP Compressor Module 8x40 LP Turbine, HP Compressor Module 8x40 Piping and Precooler Module 8x20 Intercooler #2 Module

PLANT MODULE SHIPPING BREAKDOWN

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Concept

Modular Construction

– Space-frame modules

Stackable
Self-aligning
Pre-constructed off-site

– Minimal Assembly On-Site

Connect Flanges / Fluid Lines /

Utilities

Pre-Assembled Control Facilities
Distributed Production

– Common, Simple Module Design – Minimizes Transportation Req. – Eliminates Manufacturing Capital Expense – Module Replacement Instead of Repair—Modules Returned to Fabricator

Road-mobile Transportation

– Reduces Cost—Construction of Rail Spur / Canal Not Required – Reduces Location Requirements

SLIDE 50

Present Layout

Reactor Vessel IHX Vessel High Pressure Turbine Low Pressure Turbine Compressor (4) Power Turbine Recuperator Vessel 50

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Detail of Connecting Piping

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17.5 m 32 m

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Plant With Space Frames

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2.5 m 10 m

Upper IHX Manifold in Spaceframe

3 m

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Distributed Production Concept

“MPBR Inc.”

Space-Frame Specification

Component Fabricator #1

e.g. Turbine Manufacturer

Component Fabricator #N

e.g. Turbine Manufacturer

Component Design

MPBR Construction Site

Site Preparation Contractor Assembly Contractor

S i t e a n d A s s e m b l y S p e c i f i c a t i

n

s Management and Operation

Labor Component Transportation Design Information

SLIDE 56

Turbine Hall Boundary

Admin Training Control Bldg. Maintenance Parts / Tools

10 9 8 7 6 4 2 5 3 1

0 20 40 60 80 100 120 140 160 20 40 60 80 100

Primary island with reactor and IHX Turbomachinery

Ten-Unit MPBR Plant Layout (Top View)

(distances in meters)

Equip Access Hatch Equip Access Hatch Equip Access Hatch

56

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Safety Advantages

Low Power Density
Naturally Safe
No melt down
No significant

radiation release in accident

Demonstrate with

actual test of reactor

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“Naturally” Safe Fuel

Shut Off All Cooling
Withdraw All Control Rods
No Emergency Cooling
No Operator Action

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Safety

LOCA Analysis Complete - No Meltdown
Air Ingress now Beginning focusing on

fundamentals of phenomenon

Objectives
Conservative analysis show no “flame”
Address Chimney effect
Address Safety of Fuel < 1600 C
Use Fluent for detailed modeling of RV

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The Prediction of the Air Velocity (By Dr. H. C. No)

Fig-14: Trends of maximum temperature for 0, 2, 4, 6 m/s of air velocity in the air gap region

200 400 600 800 1000 1200 1400 1600 1800 30 60 90 120 150 180 210 Time (hr) Temperature (C)

Hot-Point Temperature of the core(0m/s) Hot-Point Temperature of the Vessel (0m/s) Hot-Point Temperature of the Concrete Wall (0m/s) Hot-Point Temperature of the Core (2m/s) Hot-Point Temperature of the Vessel (2m/s) Hot-Point Temperature of the Concrete Wall (2m/s) Hot-Point Temperature of the Core (6m/s) Hot-Point Temperature of the Vessel (6m/s) Hot-Point Temperature of the Concrete Wall (6m/s) Limiting Temperature for the Vessel Limiting Temperature for the Containment

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Air I ngress Fundament als

Air/Cox Out

Vary Choke Flow

Graphite Lower Reflector Air In

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Preliminary Conclusions Air Ingress

For an open cylinder of pebbles:

Due to the very high resistance through the pebble

bed, the inlet air velocity will not exceed 0.08 m/s.

The negative feedback: the Air inlet velocity does

not always increase when the core is heated up. It reaches its peak value at 300 °C.

Preliminary combined chemical and chimney

effect analysis completed - peak temperatures about 1670 C.

SLIDE 63

M PBR BUSBAR G ENERATIO N CO STS (‘92$)

Reactor Therm al Pow er (M W t) 10 x 250 N et Efficiency (% ) 45.3% N et Electrical Rating (M W e) 1100 Capacity Factor (% ) 90 Total Overnight Cost (M $) 2,046 Levelized Capital Cost ($/kW e) 1,860 Total Capital Cost (M $) 2,296 Fixed Charge Rate (% ) 9.47 30 year level cost (M $/YR): Levelized Capital Cost 217 A nnual O&M Cost 31.5 Level Fuel Cycle Cost 32.7 Level Decom m issioning Cost 5.4 Revenue R equirem ent 286.6 Busbar Cost (m ill/kW h): Capital 25.0 O&M 3.6 FU EL 3.8 DECOM M 0.6

TO TA L 33.0m ills/kwhr

This is the number that counts

This number is important but not not as important as this number

SLIDE 64

I NCOME DURI NG CONSTRUCTI ON ?

G raph for Incom e D uring C

nstruction

60,000 30,000 40 80 120 160 200 240 280 320 360 400 Tim e (W eek) Incom e D uring C

nstruction : M
st

Lik l D

llars/W

eek

likely

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Generating Cost Generating Cost

PBMR vs. AP600, AP1000, CCGT and Coal PBMR vs. AP600, AP1000, CCGT and Coal

(Comparison at 11% IRR for Nuclear Options, 9% for Coal and CCGT (Comparison at 11% IRR for Nuclear Options, 9% for Coal and CCGT1

1)

)

(All in (All in ¢ ¢/kWh) /kWh)

AP1000 @ AP1000 @ Coal Coal2

2

CCGT @ Nat. Gas = CCGT @ Nat. Gas = 3

3

AP600 AP600 3000Th 3000Th 3400Th 3400Th PBMR PBMR ‘ ‘Clean Clean’ ’ ‘ ‘Normal Normal’ ’ $3.00 $3.00 $3.50 $3.50 $4.00 $4.00 Fuel Fuel 0.5 0.5 0.5 0.5 0.5 0.5

0.48 0.48

0.6 0.6 0.6 0.6 2.1 2.45 2.8 2.1 2.45 2.8 O&M O&M 0.8 0.52 0.46 0.8 0.52 0.46 0.23

0.23

0.8 0.8 0.6 0.6 0.25 0.25 0.25 0.25 0.25 0.25 Decommissioning Decommissioning 0.1 0.1 0.1 0.1 0.1 0.1 0.08 0.08

Fuel Cycle

Fuel Cycle 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1

_

_

_

_

_

_ Total Op Costs Total Op Costs 1.5 1.22 1.16 1.5 1.22 1.16 0.89

0.89

1.4 1.4 1.2 1.2 2.35 2.70 3.05 2.35 2.70 3.05 Capital Recovery Capital Recovery 3.4 3.4 2.5 2.5 2.1 2.1 2.2 2.2 2.0 2.0 1.5 1.5 1.0 1.0 1.0 1.0 1.0 1.0 Total Total 4.9 3.72 3.26 4.9 3.72 3.26 3.09

3.09

3.4 3.4 2.7 2.7 3.35 3.70 4.05 3.35 3.70 4.05

1 1 All options exclude property taxes

All options exclude property taxes

2 2 Preliminary best case coal options:

Preliminary best case coal options: “ “mine mouth mine mouth” ” location with $20/ton coal, 90% capacity factor & 10,000 BTU/kW location with $20/ton coal, 90% capacity factor & 10,000 BTU/kWh heat rate h heat rate

3 3 Natural gas price in $/million Btu

Natural gas price in $/million Btu

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Next Generation Nuclear Plant NGNP

High Temperature Gas Reactor (either pebble
r block)
Electricity and Hydrogen Production Mission
Built at the Idaho National Laboratory
No later than 2020 (hopefully 2013)
Research and Demonstration Project
Competition to begin shortly to decide which

to build

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Technical Challenges

Fuel is the safety system - need to prove that fuels
perating at these and higher temperatures don’t

fail.

Develop high temperature gas safety analysis

codes that are verified and validated

Above 950 C huge materials challenges
Graphite properties need to be better understood at

high temperatures and irradiation.

Want to make hydrogen either thermo-chemically
r with high temperature electrolysis. - 900 to

1000 C

Thermo-chemical production of hydrogen in lab.

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There Are Families of Thermochemical Cycles

03-112

Sulfur Iodine

(Both sides)

Ispra Mark 13 Westinghouse

Heat Heat Reject Heat Oxygen Hydrogen Water

850 C

450 C
H O

2

H2 I2 SO , H O

2 2

O2 H2

4

SO HI I + SO

2 2 2

+ 2H O Br + SO

2 2 2

+ 2H O H SO

2 4

H2

3

O + SO H2

2 2

O + SO + ½O 2HI + H2

4

SO 2HBr + H2

4

SO H2

2

+ I 2HI 120 C

77 C
Hydrogen

H2 Electrolysis SO2

2

+ 2H O H2

4 2

SO + H Heat Reject Heat Oxygen Water 700 C

H O

2

SO , H O

2 2

SO , H O

2 2

O2 H SO

2 4

Membrane Separation H2

3

O + SO H2

2 2

O + SO + ½O Reject Heat Hydrogen 77 C

Br2

H2 Br2 Electrolysis H2

2

+ Br 2HBr HBr H2

4

SO H2

4

SO

Inorganic Membrane

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Hydrogen Generation Options

Sulfur Iodine S/I Process - three T/C reactions

H2SO4 SO2 + H2O + .5O2 (>800°C heat required) I2 + SO2 +2H2O 2HI + H2SO4 (200°C heat generated) 2HI H2 + I2 (>400°C heat required)

Westinghouse Sulfur Process - single T/C reaction

H2SO4 SO2 + H2O + .5O2 (>800°C heat required) 2H2O + SO2 H2 + H2SO4 (electrolytic at 100°C using HTGR electricity)

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Summary of H2 Production Efficiencies

Efficiencies of Various H2 Routes vs. Temperature

0% 10% 20% 30% 40% 50% 250 450 650 850 1050 Available Temperature (°C) Thermal Efficiency

LWR Electrolysis HTR Electrolysis S/I H2 Generation LWR SOEC HTR SOEC Westinghouse Process

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HTGR (assumed as PMBR)– Westinghouse Process Interface

0.25 mile separation
f nuclear and H2

plant

Circulates H2SO4 and

products from the reactor at low temperatures (single chemical reaction)

Single heat

transmission required

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Intermediate Heat Exchanger (IHX) Installed In Hot Pipe for PBMR NGNP

Intermediate Heat Exchanger Pipes for Intermediate Helium Loop

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So What Does the Future Look Like ?

Turbine Hall Boundary

Admin Training Control Bldg. Maintenance Parts / Tools

10 9 8 7 6 4 2 5 3 1

0 20 40 60 80 100 120 140 160 20 40 60 80 100

Primary island with reactor and IHX Turbomachinery

Ten-Unit VHTR Plant Layout (Top View)

(distances in meters)

Equip Access Hatch Equip Access Hatch Equip Access Hatch

For 1150 MW Combined Heat and Power Station

Oil Refinery Hydrogen Production

Desalinization Plant VHTR Characteristics

Temperatures > 900 C
Indirect Cycle
Core Options Available
Waste Minimization

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Project Overview

Fuel Performance
Fission Product Barrier

(silver migration)

Core Physics
Safety

Loss of Coolant Air Ingress

Balance of Plant Design
Modularity Design
Intermediate Heat

Exchanger Design

Core Power Distribution

Monitoring

Pebble Flow Experiments
Non-Proliferation
Safeguards
Waste Disposal
Reactor Research/

Demonstration Facility

License by Test

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75

Fuel Performance Model

Detailed modeling of fuel kernel
Microsphere
Monte Carlo Sampling of Properties
Use of Real Reactor Power Histories
Fracture Mechanics Based
Considers Creep, stress, strains, fission

product gases, irradiation and temperature dependent properties.

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Barrier Integrity

Silver Diffusion observed in tests @ temps
Experiments Proceeding with Clear

Objective - Understand phenomenon

Palladium Attack Experiments Underway
Zirconium Carbide being tested as a

reference against SiC.

Focus on Grain SiC Structure Effect
Will update model with this information

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Core Physics

Basic tool Very Special Old Programs (VSOP)
Developing MNCP Modeling Process
Tested Against HTR-10 Benchmark
Tested Against ASTRA Tests with South

African Fuel and Annular Core

VSOP Verification and Validation Effort

Beginning

Working on International Benchmark

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78

MIT Nuclear Engineering Departm ent

HTR-10 MCNP4B Model

12 Reactor TRISO fuel particle Core Fuel sphere Core lattice

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Safety

LOCA Analysis Complete - No Meltdown
Air Ingress benchmarking with FLUENT

CFD code Japanese and German Experiments

Objectives
Conservative analysis show no “flame”
Address Chimney effect
Address Safety of Fuel < 1600 C
Use Fluent for detailed modeling of RV

SLIDE 80

Massachusetts Institute of Technology Department of Nuclear Engineering

Advanced Reactor Technology Pebble Bed Project

MPBR-5

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81

Verify the Chemical Model (FLUENT 6.0)

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The Detailed Model in Progress

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Extrinsic Safeguards System for Pebble Bed Reactors

Waste Package Fresh Fuel Room Scrap Waste Can

Typical Waste Storage Room

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Video Demo

19.mpg 20.mpg 21.mpg

22.mpg

23.mpg

SLIDE 85

MI T’s Proj ect I nnovat ions

Advanced Fuels
Tot ally modular - build in a f act ory

and assemble at t he sit e

Replace component s inst ead of repair
I ndirect Cycle f or Hydrogen

Generat ion f or f uel cells & t ransport at ion

Advanced comput er aut omat ion
Demonst rat ion of saf et y t est s

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86

Collaborative Research Areas

Air Ingress
Accident Performance
f TRISO Fuel
Water Ingress
Burnup Measurements
Power Distribution

Measurements

Graphite Lifetime
Defueling Systems
Verification of

Computer Codes - VSOP, Tinte

Xenon Effects
Modeling of Pebble

Flow

Mixing in Lower

Reflector

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87

Research Areas Continued

Blowdown Impacts
Release Models
Break Spectrum
Water Ingress
Seismic Impacts
Post Accident

Recovery

“License By Test”
Containment
Terrorist Impacts
Burning Potential
Advanced I&C -

Computer Control

Safeguards
International

Standards

Materials - ASME

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88

MIT Projects on Advanced Reactors Technology

Coolant Near Term Long Term Core Design Options High Burnup Thorium Fuel Annular Fuel Pressure Tube Water IRIS Gas Pebble Bed Reactor Modular Fast Gas-Cooled- Gas Turbine Lead Actinide Burning Reactor Turbine Cycle Options Helium Indirect Cycle High Temperature for H2 Production CO2 Super Critical CO2

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Summary

Nuclear Energy is

coming back

Global Environmental

Issues are worrisome

Plenty of research

challenges in NGNP and Generation IV

It is a good time to be