Intro. to High Temperature Gas Cooled Reactor

High Temperature Gas-cooled Reactor

Topan [email protected]

Pusat Teknologi dan Keselamatan Reaktor Nuklir

BATAN

T.Setiadipura, Workshop Evaluasi Desain HTGR, BAPETEN, 22 April 20154/23/2015 1

Bahasan

1. Desain HTGR (Vs. PWR)

2. Fitur Keselamatan HTGR

3. Desain dan Analisis HTGR

1. Konsep desain dan keselamatan

2. Perhitungan Kritikalitas

3. Perhitungan Equilibrium (burnup)

4. Sejarah HTGR

T.Setiadipura, Workshop Evaluasi Desain HTGR, BAPETEN, 22 April 2015

4/23/2015 2

Sejarah HTGR


4/23/2015 3

Sejarah HTGR (dan Kita)

4/23/2015T.Setiadipura, Workshop Evaluasi Desain

HTGR, BAPETEN, 22 April 20154

Pressurized Water Reactor


4/23/2015 7

Teras Reaktor PWR

Fuel pin

Tampang lintang Fuel-pin

Fuel-Assembly(penampang lintang) teras reaktor


Bahanbakar UO2

berbentukpin/pellet.

4/23/2015 8

High Temp. Gas-cooled Reactor


4/23/2015 9

Teras Reaktor (Prismatik) HTGR


4/23/2015 10

Bahan Bakar (Prismatic) HTGR


4/23/2015 11

KomponenUtama:- Bahan bakar bola- Pendingin He- Reflektor graphite- Batang kendali

Teras PBR


4/23/2015 12

Bahan bakar (Pebble) HTGR


4/23/2015 13

4/23/2015 14T.Setiadipura, Workshop Evaluasi Desain


Fitur Keselamatan• Power density yang rendah (~3 W/cm3)• Heat capacity dan conductivity yang tinggi.• Pengungkungan produk fisi yang baik pada

bahan bakar hingga pada temp. tinggi. (limit 1620oC, karena teknologi TRISO ).

• Koeff. temp. negatif yang tinggi.• Kemampuan `afterheat removal through the

vessel wall` (diameter teras yang kecil ~3m)• Excess reactivity yang rendah (karena on-line

refueling).


4/23/2015 15

Fitur Keselamatan(1): ControlSecara inherent/melekat teras reaktor dapat mengkontrol laju reaksi fisi

bahkan hingga menghentikannya.


4/23/2015 16

HTR-Module Siemens Design

Fitur Keselamatan(1): ControlSecara inherent/melekat teras reaktor dapat mengkontrol laju reaksi fisi

bahkan hingga menghentikannya.


4/23/2015 17

HTR-Module Siemens Design

Fitur Keselamatan(2): CoolingMampu mengeluarkan panas yang dihasilkan dengan hanya bergantung

pada mekanisme alamiah tanpa perlu tindakan aktif:


4/23/2015 18

rcore

Fitur Keselamatan(3): Contain

Rilis zat radioaktif yang sangat kecil kepada lingkungan dalamkondisi apapun, bahkan pada kecelakaan terparah sekalipun:


4/23/2015 19

TRISO Integrity


Faktor utama dari fitur keselamatan `contain` tersebut adalah lapisan SiC(Silikon Karbida) pada partikel bahan bakar TRISO.

4/23/2015 20

Faile

d P

arti

cle

Fra

ctio

n

German Fuel

TRISO Integrity


Faktor utama dari fitur keselamatan `contain` tersebut adalah lapisan SiC(Silikon Karbida) pada partikel bahan bakar TRISO.

4/23/2015 21

Skema Operasi Pebble Bed Reactor(1)

Skema strategi pengisian bahan bakar Multipass dan OTTO pada reaktor PBR.


4/23/2015 22

Skema strategi pengisian bahan bakar peu-a-peu padareaktor PBR.

Skema Operasi Pebble Bed Reactor(2)


4/23/2015 23

Sistem Penanganan Bahan BakarHTR-Module

Siemens Design(Multipass)



Spesifikasi Teknis RDE



Siklus Pebble Bed Reactor

T.Setiadipura, Workshop Evaluasi

Desain HTGR, BAPETEN, 22 April

2015

4/23/2015 26

Perhitungan Kritikalitas

• HTR-10 Benchmarking

– CFP Modeling

– Fuel Pebble Modeling

• ASTRA Benchmarking

– Fuel Pebble Modeling


4/23/2015 27

HTR-10 Benchmarking


4/23/2015 28

HTR-10 Design Features


4/23/2015 29

HTR-10 Full Core ModelingBromated

carbon bricks

Graphite reflector

structure

Cold Coolant Chamber

Top reflector

Top core cavity

Mix of Fuel and dummy pebbles

Dummy pebbles

Control rod borings

Carbon bricks

Bottom reflector


4/23/2015 30

HTR-10 Core Cross Section


4/23/2015 31

CFP Modeling

• Coated Fuel Particles (CFP) are modeled explicitly in this benchmarking calculation.


4/23/2015 32

Pebble Fuel Model

Statistical Geometry Model Regular Lattice Model

Statistical Vs. Regular Lattice Model


4/23/2015 33

ASTRA Benchmarking


4/23/2015 34

ASTRA Critical Assembly


4/23/2015 35

ASTRA Benchmark Model(1)1. Annular Core2. Bottom reflector3. Lower part IR support

structure (air)4. Upper part IR support

structure (metal)5. Side graphite

reflector6. Separating sheet7. Top reflector8. Internal reflector (IR)


4/23/2015 36

ASTRA Benchmark Model(2)Borings Function

CR1, … CR7 Channels for Control rods CR1-CR7

MR Channel for Manual Rod

SR1, …SR8 Channels for Safety rods SR1-SR8

LIPR1, LIPR2 Channels for Placement of Rods LIPR1 and LIPR2

Outer dimension of side reflector is 380 cmT.Setiadipura, Workshop Evaluasi Desain HTGR, BAPETEN, 22 April 2015

4/23/2015 37

ASTRA Benchmark Model(3)

Model of -Control Rods (CR)- Safety Rods (SR)- Leave in Place Rods (LIPR)Contain B4C material.

Model of Manual Rods (MR), made of Aluminum.


4/23/2015 38

ASTRA Benchmarking Cases

Cas

e

Position, Z, along the channel height,

cm*

Core

Height**

Packing

Fraction

LIPR1 LIPR2 MR CR5 Hc fi

1 OUT OUT 178.8 402.6 180.354 0.59914

2 42.6 OUT 160.5 402.6 215.134 0.60304

3 42.6 42.6 225.1 402.6 292.584 0.6048

4 42.6 42.6 403.5 184.6 321.044 0.60618

5 42.6 42.6 403.5 93 321.044 0.60618

CasePosition, Z, along the channel height, cm

CR1 CR2 CR3 CR4 CR6 CR6 SR 1-8

All

Case404.8 402.8 391.2 398.7 395.1 395 400

* Z vertical distance between the bottom of the graphite reflector (bottomsurface of SRf and BR) and bottom of the poison rod** Core height is from the upper boundary of the bottom reflector of lowerboundary of the core.


4/23/2015 39

HTGR Benchmark Summary

Carbon

thermal

capture

cross section

JENDL-4.0 JENDL-3.3 ENDF/B-VII.0 JEFF-3.1

3.85 mb 3.53 mb 3.36 mb 3.36 mb

0.98500

0.99000

0.99500

1.00000

1.00500

1.01000

1.01500

1.02000

1.02500

1.03000

HTR-10(IAEA)

HTR-10(IRPhEP)

ASTRA#1

ASTRA#2

ASTRA#3

ASTRA#4

ASTRA#5

HTTR

K-E

FF

Benchmark Model

ENDF/B-VII.0

JENDL-3.3

JENDL-4.0

EXP.


4/23/2015 40

Perhitungan Teras EquilibriumBurnup Calculation of Moving Core Pebble Bed Reactor


4/23/2015 41

Concept of PBR BU Calculation

The interdependence of neutron flux and nuclide density requiresthat the depletion equation should be solve simultaneously withneutronic core calculation. The common method applied multi-group neutron diffusion approximation for neutronic corecalculation.

Depletion analysis in PBR type needs to account simultaneously for themovement of the fuel elements and for the changes of their composition.

Modeled as


4/23/2015 42

Equilibrium Analysis of 10MWt Small PBR

Design parameters [units] Values

Power [MWt] 10

Core height [cm] 196.5

Core diameter [cm] 180

Top reflector height [cm] 90

Bottom reflector height [cm] 121

Void region height [cm] 42

Power density [W/cc] 2

U-235 enrichment [wt%] 10

Axial fuel velocity [cm/day] 0.5

Core residence time [days] 393

Initial and equilibrium keff for different HM/pebble


4/23/2015 43


• Effective multiplication factor for different HM-loading with 20% U-

235 enrichment. HM-loading of 2.1 g/pebble was the lowest to

achieve a critical equilibrium core.

• The related optimized burnup is of 69.4 MWd/kg-HM achieved

by 20% U-235 enrichment and 2.1 gHM/pebble.

0.95

1

1.05

1.1

1.15

1.2

1.25

1.3

0 100 200 300 400 500 600 700 800 900

Eff

ec

tive

Mu

ltip

lic

ati

on

Fa

cto

r

Operation Time (days)

1.4 gHM/pebble

1.6 gHM/pebble

1.8 gHM/pebble

2 gHM/pebble

2.1 gHM/pebble

2.5 gHM/pebble

3 gHM/pebble

4 gHM/pebble

Parametric survey for 20wt% enrichment


4/23/2015 44


Effect of lower HM loading (also means lower burnup):- increase the burnup- increase and shift the peak power density to the upper part

of the core.

1

1.2

1.4

1.6

1.8

2

2.2

2.4

0 2 4 6 8 10 12 14 16 18 20

Po

we

r D

en

sit

y [

W/c

m3

]

Axial Region (top to bottom)

4 ; 20wt%

3 ; 20wt%

2.5 ; 20wt%

2.1;20wt%

Power density profile for different HM-loading.

4/23/2015 45


1.3494

1.3857

1.3597

1.32821.2867

1.26421.2338

1.0114

1.03331.0448 1.0537 1.0603 1.0565 1.0519

0.9000

1.0000

1.1000

1.2000

1.3000

1.4000

1.5000

5 7 9 11 13 15 17 19 21

Eff.

Mu

ltip

licat

ion

Fac

tor

HM-Loading[g-HM/pebble]

Init. Core

Equil. Core

Effective multiplication for different HM loading with 15wt% U-235 enrichment of initial and equilibrium core.

For 15wt% enrichment of U-235, the lowest HM-loading to achieve critical equilibrium condition is 8 gHM/pebble.

Equilibrium Analysis of 200MWt PBR

4/23/2015 46


Effective multiplication for different HM loading with 17wt% U-235

enrichment of initial and equilibrium core

1.461 1.445

1.4351.427

1.3731.341

1.3001.278

1.250

1.0229

1.08001.0876 1.0862 1.0827 1.0805

0.900

1.000

1.100

1.200

1.300

1.400

1.500

0 5 10 15 20 25

Eff.

Mu

ltip

licat

ion

Fac

tor

HM-Loading [g-HM/pebble]

Init. Core

Equil. Core



4/23/2015 47


Effective multiplication for different HM loading with

20wt% U-235 enrichment of initial and equilibrium core

1.4831.477

1.464

1.447

1.3931.360

1.3191.298

1.270

1.039

1.0831.121 1.125 1.121 1.116 1.115

0.900

1.000

1.100

1.200

1.300

1.400

1.500

1.600

0 5 10 15 20 25

Eff

. M

ultip

licatio

n F

acto

r

HM-Loading [g-HM/pebble]

Init. Core

Equil. Core



4/23/2015 48

Effect of Fuel Velocity

1

1.05

1.1

1.15

1.2

1.25

1.3

1.35

1.4

1.45

1.5

0 500 1000 1500 2000 2500

Eff.

Mu

ltip

licat

ion

Fac

tor

Operation Time (days)

v=0.5cm/day v=0.8cm/day

200MWt ; 20wt% ; 6 gHM/pebble


4/23/2015 49

Power Density & Effect of Velocity

6.34

3.41

0.00

1.00

2.00

3.00

4.00

5.00

6.00

7.00

0 2 4 6 8 10 12 14 16 18 20

Po

we

r D

en

sity

[kW

/pe

bb

le]

Axial Region (top to bottom)

v=0.5cm/day v=0.8cm/day

200MWt ; 20wt% ; 6 gHM/pebble


4/23/2015 50

Parameter Desain


• Skema pemuatan bahan bakar: Multipass / OTTO / Peu a Peu•Geometri teras dan bahan bakar• Pengayaan U-235• Pemuatan Heavy Metal (HM) per pebble (fraksi volume CFP di fuel zone pebble bed)• Kecepatan axial rerata bahan bakar / core residence time.• BU target

4/23/2015 51

Tantangan dan Peluang ?

- Costmemperkecil biaya pembangkitan.- Resourcememperbesar energi densitas (energi

per bahan bakar, MWd/TU), membangun konseppembiak?.

- Accident Inherent safety aspect, keselamatanbergantung pada hukum alam yang availability-nya100%.

- Bomb aspek Non-proliferasi (kemudahan untukdigunakan sebagai bom).

- Waste konsep reaktor nuklir pemakan `sampahnuklir`, close-cycle system.



Sejarah HTGR(1)


4/23/2015 53

Sejarah HTGR(2)


4/23/2015 54

Terimakasih…


4/23/2015 55

Intro. to High Temperature Gas Cooled Reactor

Engineering

Transcript of Intro. to High Temperature Gas Cooled Reactor