physics design of 600 mwth htr & 5 mwth nuclear power pack brahmananda chakraborty bhabha atomic...
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![Page 1: Physics Design of 600 MWth HTR & 5 MWth Nuclear Power Pack Brahmananda Chakraborty Bhabha Atomic Research Centre, India](https://reader035.vdocuments.mx/reader035/viewer/2022062409/56649f585503460f94c7d898/html5/thumbnails/1.jpg)
Physics Design of 600 MWth HTRPhysics Design of 600 MWth HTR&&
5 MWth Nuclear Power Pack5 MWth Nuclear Power Pack
Brahmananda ChakrabortyBhabha Atomic Research Centre, India
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Indian High Temperature
Reactors Programme
Compact High Temperature Reactor (CHTR)A technology demonstration facility
Nuclear Power Pack (NPP)To supply electricity in remote areas not connected to
grid
High Temperature Reactor (HTR)For hydrogen generation
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Ref: High Efficiency Generation of HydrogenFuels Using Nuclear Power, G.E. Besenbruch, L.C. Brown, J.F. Funk, S.K.
Showalter, Report GA–A23510 and ANL reports
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I-S Process Reaction Scheme
HH22SOSO44HH22O + SOO + SO22 + ½ O+ ½ O22
2HI2HI II22
HH22SOSO44 HH22O + SOO + SO22 + ½ O+ ½ O22850850ooCC
HEAT
2HI2HI HH22 + I+ I22
450oC
HEAT
2HI + H2HI + H22SOSO44 II22 + SO+ SO22 + 2H+ 2H22OO120120ooCC
WATERWATER
OO22
H2
HEATHH22SOSO44HH22O + SOO + SO22 + ½ O+ ½ O22
2HI2HI II22
HH22SOSO44 HH22O + SOO + SO22 + ½ O+ ½ O22850850ooCC
HEAT
HH22SOSO44 HH22O + SOO + SO22 + ½ O+ ½ O22850850ooCC
HH22SOSO44 HH22O + SOO + SO22 + ½ O+ ½ O22850850ooCC
HEATHEAT
2HI2HI HH22 + I+ I22
450oC
HEAT
2HI2HI HH22 + I+ I22
450oC2HI2HI HH22 + I+ I22
450oC
HEATHEAT
2HI + H2HI + H22SOSO44 II22 + SO+ SO22 + 2H+ 2H22OO120120ooCC
WATERWATER
OO22
H2
HEAT
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600 MW(Th) HTR
ObjectiveTo provide high temperature heat required for thermo-chemical processes for hydrogen productionPebble bed reactorIt is a Pebble Bed Reactor moderated and reflected by graphite & loaded with randomly packed spherical fuel elements called Pebble and cooled by molten Pb/Bi.
Key featuresUse of triso particlesIts an advanced design with a higher level of safety and efficiency
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REFLECTOR
HEAT EXCHANGERS
CHUTE FOR FUELING
CENTRAL
REFLECTORSIDE
CORE BARREL
REACTORVESSEL
REFLECTORMESHED
COOLANT INLET
COOLANT OUTLET
Core configuration for pebble bed design
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Cross-sectional view of
triso particle and
pebble
Triso Particle
(U+Th)O2 Kernel (250 m)
Pyrolitic Graphite (90 m)
Inner Dense Carbon (30 m)
Silicon Carbide (30 m)
Outer Dense Carbon (50 m)
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Advantages of Pebbles
On line refueling Homogeneous core (less power
peaking) Simple fuel management One way of control by replacing
dummy pebbles
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Reactor power 600 MWth for following deliverables (Optimized for hydrogen Production)1.Hydrogen: 80,000 m3/hr2.Electricity: 18 MWe Drinking water: 375 m3/hr
Coolant outlet/inlet temperature
1000°C / 600°C
Moderator Graphite
Coolant Molten lead
Reflector Graphite
Mode of cooling Natural circulation of coolant
Fuel 233UO2 & ThO2 based high burn-up TRISO coated particle fuel
Energy transfer systems
Intermediate heat exchangers for heat transfer for hydrogen production + High efficiency turbo-machinery based electricity generating system + Water desalination system for potable water
Hydrogen production
High efficiency thermo-chemical processes
Proposed Broad Specifications
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Pebble Configuration
Pebble diameter (fuelled portion): 90 mm
Outer pebble diameter: 100 mm
Number of pebbles: 150000
Packing density (Volume %) 59%
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Challenges in the design
To design optimum pebble and core configuration to get maximum energy per gm inventory of fissile isotopes.
Control initial excess reactivity
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Computational Technique
Multi-group Integral Transport theory code “ITRAN” & Diffusion theory code “ Tri-htr” used for simulations.
Triso particles homogenized
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Comparison of fuel inventoryPacking
Percentage
Enrichment
Percentage
Amount of U233 in gm per pebble
Burn up (FPDs)
Initial k-eff
Remarks
8.6 7.3 3.4 450 1.2701
5.0 8.0 2.2 190 1.2415
5.0 10.0 2.7 330 1.3372
4.5 7.0 1.7 80 1.1559
4.5 8.0 2.0 150 1.2169
4.5 10.0 2.4 270 1.1559
4.0 8.0 1.7 100 1.1879
4.0 10.0 2.2 210 1.2902
4.0 12.0 2.6 320 1.3686
4.0 14.5 3.2 450 1.4456
3.5 8.0 1.5 60 1.1507
3.5 10.0 1.9 160 1.2576
3.5 12.0 2.3 250 1.3402
3.5 16.3 3.1 450 1.468
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Optimized Pebble Configuration
Packing fraction 8.6%Enrichment 7.3% (H=800 cm,
900FPDs)
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Comparison between different height
Parameters H=8 m H=10 m H=12 m
Enrichment (%)
7.3 6.6 6.1
Initial K-eff 1.2701 1.23556 1.20545
Amount of heavy metal Per pebble
(gm)
U233 =3.4Th232 = 43.2
U233 =3.1Th232 = 43.5
U233 =2.8Th232 = 43.7
No. of Pebbles 150,000 187,000 225,000
Amount of fuel
In the core (Kg)
U233 =510Th232 = 6480
U233 =581Th232 = 8156
U233 =630Th232 = 9832
U233+U235) out (Kg) 219.3 284.8 353.53
MWD/gm fissile elements
1.85 1.90 1.95
Burn up ( FPDs)
900 900 900
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0 100 200 300 400 5000.90
0.95
1.00
1.05
1.10
1.15
1.20
1.25
1.30
Variation of K-eff with Burn Up for different height
K-e
ff
Burn Up in FPDs
H-800 E-7.3 H-1000 E-6.6 H-1200 E-6.1
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Estimation of Fuel Temperature Coefficient
(H=1200, P=8.6%, E=6.1%)
Fuel temperature
(0C)
Value of K-eff
Fuel Temperature
Coefficient (per 0C)
1000 1.20545 Reference
1100 1.20361 -1.268x10-5
1200 1.20193 -1.214x 10-5
900 1.20745 -1.374 x 10-5
800 1.20965 -1.440x 10-5
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Major Problem
Initial K-eff is too high
1.276 for 8m height 7.3% Enrichment
1.205 for 12m height 6.1Enrichment
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Study to reduce initial k-eff
OPTIONS
Reduce number of fuel balls & keep (fuel balls + dummy balls = constant)
Initial power will be reduced
Reduce enrichment
Available burn up will be less
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H (M) P (%)
E (%)
FUEL BALL
DUMMY BALL
INITIAL K-EFF
REMARK
12 8.6 6.1 1/2 1/2 1.1588008
Little improveme
nt
8 8.6 7.3 1/2 1/2 1.2356665
Not much improveme
nt
8 8.6 6 1/2 1/2 1.1440712
Beneficial
8 8.6 6 All fuel
- 1.1899716
Beneficial
12 8.6 5 2/3 1/3 1.1086059
Initial K-eff reduces
sufficiently
Comparison of different cases
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CONCLUSIONS
For the same burn up fuel inventory is less for lower packing fraction. But as packing fraction decreases initial K-eff increases.
Energy production in terms of MWD/gm of fissile inventory is more for 12m core height compared to 8m core height.
Initial reactivity can be controlled by reducing enrichment as well using control rods. But burn up reduces.
Further study to control initial reactivity by using ThO2 ball is in progress.
Fuel temperature coefficient is satisfactory System can be controlled using control rods &
burnable absorber.
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Physics Design of5 MWth
Nuclear Power Pack
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Salient Features
It will be compact and can run for around 10 years without any refueling.
The reactor should be able to control and regulate its operation in a perfectly passive manner.
The overall reactivity change during core life should be less.
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Basic Design ParametersReactor Power : 5 Mwth
Core Life : Around 10 years
Fuel : Metallic U233 + Th232
Moderator : BeO
Reflector Material : BeO and Graphite
Coolant : Pb-Bi
Core Height : 1000 mm
Core Inlet Temperature : 4500C
Core Outlet Temperature
: 6000C
No. Of Fuel Assemblies : 30
No. Of Control Locations
: 31
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Nuclear Power Pack
NPP
30 Fuel beds24 (Ex) + 7 (In) control locations
Ø8
Ø8.5
Ø10
Metallic Fuel (90% (U233+Th) + 10% Zr) Heat Tr. Medium
Clad of Zr-4
Fuel Pin
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Important Parameters
Enrichment 14%
Core life 3000 FPDs
Amount of Gd 300gm in each of 12
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Total fuel for entire core
U233 28.88 Kgs
Th232 156.78 Kgs
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Estimation of Control Rods Worth at Hot Condition
(14% enrichment) Position Of Control Rods Value of K-eff
All Control Rods out 1.07280
All Control Rods in 0.79748
All Control Rods in except one having Maximum worth
0.80661
Worth of all Control Rods = 321.8 mk
Max. Worth of a Single Control Rod = 14.19 mk
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Height of Control Rods at Criticality
(14% enrichment)
At criticality control rods will be 39.5 cm in the core plus 15 cm in the bottom reflector.
In this condition the worth of one control rod having maximum worth is 2.9 mk.
Estimation of Fuel Temperature Coefficient
Fuel temperature coefficient is at 7750C it is -1.6953 x 10-5 per 0C
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CONCLUSION
Initial K-eff is very large necessitating the introduction of burnable poison in the core.
14.0 cm pitch is considered adequate.
This can be used as a Nuclear battery which will run around 10 years without any refueling.
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ACKNOLEDGEMENT
P.D. KrishnaniI.V. Dulera
R. SrivenkatesanR. K. Sinha
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THANK YOU
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Indian High Temperature
Reactors Programme
Compact High Temperature Reactor (CHTR)A technology demonstration facility
Nuclear Power Pack (NPP)To supply electricity in remote areas not connected to
grid
High Temperature Reactor (HTR)For hydrogen generation