Intro. to High Temperature Gas Cooled Reactor

High Temperature Gas-cooled Reactor
Topan Setiadipura
tsdipura@batan.go.id
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
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Sejarah HTGR (dan Kita)
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4

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5

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6

Pressurized Water Reactor
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Teras Reaktor PWR
Fuel pin
Tampang lintang Fuel-
pin
Fuel-Assembly
(penampang lintang) teras reaktor
Bahan
bakar UO2
berbentuk
pin/pellet.
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High Temp. Gas-cooled Reactor
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Teras Reaktor (Prismatik) HTGR
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Bahan Bakar (Prismatic) HTGR
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Komponen
Utama:
- Bahan bakar bola
- Pendingin He
- Reflektor graphite
- Batang kendali
Teras PBR
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Bahan bakar (Pebble) HTGR
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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).
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Fitur Keselamatan(1): Control
Secara inherent/melekat teras reaktor dapat mengkontrol laju reaksi fisi
bahkan hingga menghentikannya.
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HTR-Module
Siemens Design

Fitur Keselamatan(1): Control
Secara inherent/melekat teras reaktor dapat mengkontrol laju reaksi fisi
bahkan hingga menghentikannya.
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HTR-Module
Siemens Design

Fitur Keselamatan(2): Cooling
Mampu 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 dalam
kondisi apapun, bahkan pada kecelakaan terparah sekalipun:
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TRISO Integrity
Faktor utama dari fitur keselamatan `contain` tersebut adalah lapisan SiC
(Silikon Karbida) pada partikel bahan bakar TRISO.
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FailedParticleFraction
German Fuel

TRISO Integrity
Faktor utama dari fitur keselamatan `contain` tersebut adalah lapisan SiC
(Silikon Karbida) pada partikel bahan bakar TRISO.
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Skema Operasi Pebble Bed Reactor(1)
Skema strategi pengisian bahan bakar Multipass dan OTTO pada reaktor
PBR.
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Skema strategi pengisian bahan bakar peu-a-peu pada
reaktor PBR.
Skema Operasi Pebble Bed Reactor(2)
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Sistem Penanganan Bahan Bakar
HTR-Module
Siemens Design
(Multipass)
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Spesifikasi Teknis RDE
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25

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
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HTR-10 Benchmarking
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HTR-10 Design Features
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HTR-10 Full Core Modeling
Bromated
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
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HTR-10 Core Cross Section
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CFP Modeling
• Coated Fuel
Particles (CFP)
are modeled
explicitly in this
benchmarking
calculation.
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Pebble Fuel Model
Statistical Geometry Model Regular Lattice Model
Statistical Vs. Regular Lattice Model
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ASTRA Benchmarking
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ASTRA Critical Assembly
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ASTRA Benchmark Model(1)
1. Annular Core
2. Bottom reflector
3. Lower part IR support
structure (air)
4. Upper part IR support
structure (metal)
5. Side graphite
reflector
6. Separating sheet
7. Top reflector
8. Internal reflector (IR)
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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
4/23/2015 37

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
Case
Position, Z, along the channel height, cm
CR1 CR2 CR3 CR4 CR6 CR6 SR 1-8
All
Case
404.8 402.8 391.2 398.7 395.1 395 400
* Z vertical distance between the bottom of the graphite reflector (bottom
surface of SRf and BR) and bottom of the poison rod
** Core height is from the upper boundary of the bottom reflector of lower
boundary 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-EFF
Benchmark Model
ENDF/B-VII.0
JENDL-3.3
JENDL-4.0
EXP.
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Perhitungan Teras Equilibrium
Burnup Calculation of Moving Core Pebble Bed Reactor
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Concept of PBR BU Calculation
The interdependence of neutron flux and nuclide density requires
that the depletion equation should be solve simultaneously with
neutronic core calculation. The common method applied multi-
group neutron diffusion approximation for neutronic core
calculation.
Depletion analysis in PBR type needs to account simultaneously for the
movement 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
EffectiveMultiplicationFactor
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
PowerDensity[W/cm3]
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
1.3282
1.2867
1.2642
1.2338
1.0114
1.0333
1.0448 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.MultiplicationFactor
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
1.435
1.427
1.373
1.341
1.300
1.278
1.250
1.0229
1.0800
1.0876 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
HM-Loading [g-HM/pebble]
Init. Core
Equil. Core
is 7 gHM/pebble.
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Effective multiplication for different HM loading with
20wt% U-235 enrichment of initial and equilibrium core
1.483
1.477
1.464
1.447
1.393
1.360
1.319
1.298
1.270
1.039
1.083
1.121 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
HM-Loading [g-HM/pebble]
Init. Core
Equil. Core
is 6 gHM/pebble.
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
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
PowerDensity[kW/pebble]
Axial Region (top to bottom)
v=0.5cm/day v=0.8cm/day
200MWt ; 20wt% ; 6 gHM/pebble
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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 ?
- Cost  memperkecil biaya pembangkitan.
- Resource  memperbesar energi densitas (energi
per bahan bakar, MWd/TU), membangun konsep
pembiak?.
- Accident  Inherent safety aspect, keselamatan
bergantung pada hukum alam yang availability-nya
100%.
- Bomb  aspek Non-proliferasi (kemudahan untuk
digunakan sebagai bom).
- Waste  konsep reaktor nuklir pemakan `sampah
nuklir`, close-cycle system.
4/23/2015 52

Sejarah HTGR(1)
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Sejarah HTGR(2)
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Terimakasih…
4/23/2015 55

Intro. to High Temperature Gas Cooled Reactor

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