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Feasibility Study Part – I Thermal Hydraulic Analysis of LEU Target for 99Mo Production in Tajoura Reactor By
Bsebsu F. M., Abotweirat F. Reactor Department and
Elwaer S.
Radiochemistry Department Renewable Energies and Water Desalinization Research Center, Tajoura – Libya
RERTR Meeting, Prague, Czech Republic, September 23 –27, 2007 REWDRC RENEWABLE ENERGIES and WATER DESALINIZATION RESERCH CENTER
TAJOURA REACTOR CORE DESCRIPTION IRT-4M FUEL ASSEMBLIES DESCRIPTION LEU FOIL TARGET DESCRIPTION REACTOR WITH LEU TARGET STEADY STATE THERMAL HYDRAULIC REACTOR WITH LEU TARGET ACCIDENTAL ANALYSIS
Pool type, water moderator & coolant Located at Renewable Energies & Water Desalinization Research Center, Tajoura, Libya 1983: began operation, HEU fuel, 10 MW Used for experiments in neutron activation analysis, solid state physics, isotope production 2006: converting from High to Low Enriched Uranium (HEU to LEU) fuel Thermal Power (design) = 10 MWth Reflector , Moderator, coolant = Beryllium, Water o
2VCR
2VCV
• Grid plate: 6 x 6 positions • Compact core asy: – 16 fuel – 20 reflector
• Control:
– 8 shim – 2 safety – 1 regulating
1VCR
1VCV
4VCR
3VCR 6
4VCV
5
4
3
2
1
3VCV 1 2
6VCR
3
8VCR
5VCR 7VCR
4 10VCR
5
6VCV
6
8VCV 10VCV
14VCR 16VCR
9VCR 5VCV 7VCV
11VCR 12VCR
13VCR 18VCR
15VCR 17VCR
19VCR
9VCV
Fuel Assembly and Fuel Materials Descriptions • IRT- 4M FA type • 6 or 8 tubes/FA • 19.7% enriched
U • UO2 – Al fuel, Al clad • Active length=60 cm • Fuel 0.7 mm 235
The Tajoura Compact Core Loading Consists of 16 Fuel Assemblies LEU: 16 FAs = 10 x 6TFA + 6 x 8TFA
Two aluminum cylinder having 15.5 – 17.5 cm length and outside diameters of 27.99 and 30 mm, and inside diameters of 28.22 and 26.21 mm, respectively. One foil of uranium (LEU) of 7.6 ± 0.2 × 4.4 ± 0.2 × 0.0125 cm. Coating nickel foil of 0.0013 cm thickness. Uranium mass of 8 grams with 19.7 % enrichment of 235U. Irradiation cylinder (rig) of 19 mm radius.
LEU Target Horizontal and Vertical Cross Section III
VI
II
I
Be Unit
Al Plug
10 mm 13.22 13.94 13.96 14.095 14.11 15.00 17.50 19.00 Inner Radius of Be Unit = 20 or 22 Equivalent Radius of Be Unit = 38.93 Equivelant Radius of Reactor Pitch = 40.34
H 2O
LEU foil
Nickel foil
Al tube
Be unit
Parameter LEU Target Volume, cm3 Uranium Mass, gm
Value 0.418 8
Uranium Density, kg/m3
19.14
LEU Target Volumetric Heat Source ×106, kW/ m3
17.11
LEU Target Power Generation, kW
7.15
U Number Density ×1021, nuclei/cm3
8.51
Thermal Neutron Flux ×1014, n/cm2 .sec
1.60
235
Linear Heat Source, kW/m
162.56
o C m
Sub-channel Param I (b/w eter Be Units) V, 3.87 m/sec
II
III
IV
3.82
3.84
3.90
1.35
1.16
0.97
0.91
0.12
0.12
0.12
0.12
Tout, C
45
45
50
50
CHF, MW/m2
0.0
0.0
2.73
2.74
m, kg/sec Pout, MPa
Reactor Core Fuel Assemblies and LEU Target Maximum Temperatures and Safety Factors Reactor Core Power Level, MW 10 Paramete r
LEU Targe 8TFA t
8
6TFA
LEU Targe 8TFA t
5 LEU 6TFA Targe 8TFA t
6TFA
Tfuel,
124
116
108
115
104
97
91
84
79
Tclad,
123
115
107
115
103
96
91
83
79
Tboiling,
135
131
130
134
129
128
130
125
123
TONB,
136
120
119
122
118
118
119
116
116
Tsat,
107.2
DNBR
1.4
2.3
2.5
1.7
2.9
3.1
2.8
4.6
5.0
ONBF
1.2
1.2
1.4
1.3
1.5
1.6
1.9
2.1
2.4
Using PARET For Transient Calculation Coupled neutronics & thermal hydraulics One-dimensional (axial), multi channel. Present calculations use 3 channels 5. Steady State Calculation 6. Accidental Analysis 2.1 Control Rod Follower Disengagement 2.2 Loss of Flow Accident
ρ ρo C max
Tajoura Reactor Core at Several Transient Trips in the Case of Control Rod Follower Disengagement Overpow er Trip
Steady State Time, sec Power, MW Reactivit y, DNBR Tcool,
Max. Power Trip
-ve insertion Trip
–ve insertion trip
0
0.19
0.22
0.69
10.01
5
5.76
5.84
5.33
0.28
0
0.14
0.15
-0.25
-32.71
5.58 75.74
5.17 76.34
5.08 76.57
4.79 79.24
106.28 46.70
Tclad,
100.68
101.39
102.19
105.13
48.43
Tfuel,
104.15
105.23
106.09
109.11
48.62
Tajoura Reactor Core at Several Transient Trips in the Case of Loss of Flow Accident -ve Steady Overpower insertion State Trip Trip Time, sec Power, MW Reactivity,
–ve insertion trip
0
10.015
10.595
71.047
5
5.041
5.028
0.179
0
0.0028
-0.00002
-33.064
5.575
5.615
5.561
71.596
75.958
74.735
75.260
115.041
Tclad,
100.686
97.898
98.707
117.398
Tfuel,
104.153
101.394
102.181
117.527
DNBR Tcool,
From the steady state calculations for the Tajoura reactor core with LEU target at different power levels (Table 3) and from safety point of view, we conclude that the permissible reactor core operating power level is 5 MW. Finally, from the all cases of transient analysis results for Tajoura reactor core loaded with LEU target for 99Mo production, we conclude that the cladding surface temperature still remains much lower than the temperature at which clad damage might occur, when operate the reactor core at power level of 5 MW only.
THANK YOU FOR YOUR ATTENTION !!!!!!!!!!!!!!!!
Bsebsu F. M., Abotweirat F. Reactor Department and
Elwaer S.
Radiochemistry Department Renewable Energies and Water Desalinization Research Center, Tajoura – Libya
RERTR Meeting, Prague, Czech Republic, September 23 –27, 2007 REWDRC RENEWABLE ENERGIES and WATER DESALINIZATION RESERCH CENTER
TAJOURA REACTOR CORE DESCRIPTION IRT-4M FUEL ASSEMBLIES DESCRIPTION LEU FOIL TARGET DESCRIPTION REACTOR WITH LEU TARGET STEADY STATE THERMAL HYDRAULIC REACTOR WITH LEU TARGET ACCIDENTAL ANALYSIS
Pool type, water moderator & coolant Located at Renewable Energies & Water Desalinization Research Center, Tajoura, Libya 1983: began operation, HEU fuel, 10 MW Used for experiments in neutron activation analysis, solid state physics, isotope production 2006: converting from High to Low Enriched Uranium (HEU to LEU) fuel Thermal Power (design) = 10 MWth Reflector , Moderator, coolant = Beryllium, Water o
2VCR
2VCV
• Grid plate: 6 x 6 positions • Compact core asy: – 16 fuel – 20 reflector
• Control:
– 8 shim – 2 safety – 1 regulating
1VCR
1VCV
4VCR
3VCR 6
4VCV
5
4
3
2
1
3VCV 1 2
6VCR
3
8VCR
5VCR 7VCR
4 10VCR
5
6VCV
6
8VCV 10VCV
14VCR 16VCR
9VCR 5VCV 7VCV
11VCR 12VCR
13VCR 18VCR
15VCR 17VCR
19VCR
9VCV
Fuel Assembly and Fuel Materials Descriptions • IRT- 4M FA type • 6 or 8 tubes/FA • 19.7% enriched
U • UO2 – Al fuel, Al clad • Active length=60 cm • Fuel 0.7 mm 235
The Tajoura Compact Core Loading Consists of 16 Fuel Assemblies LEU: 16 FAs = 10 x 6TFA + 6 x 8TFA
Two aluminum cylinder having 15.5 – 17.5 cm length and outside diameters of 27.99 and 30 mm, and inside diameters of 28.22 and 26.21 mm, respectively. One foil of uranium (LEU) of 7.6 ± 0.2 × 4.4 ± 0.2 × 0.0125 cm. Coating nickel foil of 0.0013 cm thickness. Uranium mass of 8 grams with 19.7 % enrichment of 235U. Irradiation cylinder (rig) of 19 mm radius.
LEU Target Horizontal and Vertical Cross Section III
VI
II
I
Be Unit
Al Plug
10 mm 13.22 13.94 13.96 14.095 14.11 15.00 17.50 19.00 Inner Radius of Be Unit = 20 or 22 Equivalent Radius of Be Unit = 38.93 Equivelant Radius of Reactor Pitch = 40.34
H 2O
LEU foil
Nickel foil
Al tube
Be unit
Parameter LEU Target Volume, cm3 Uranium Mass, gm
Value 0.418 8
Uranium Density, kg/m3
19.14
LEU Target Volumetric Heat Source ×106, kW/ m3
17.11
LEU Target Power Generation, kW
7.15
U Number Density ×1021, nuclei/cm3
8.51
Thermal Neutron Flux ×1014, n/cm2 .sec
1.60
235
Linear Heat Source, kW/m
162.56
o C m
Sub-channel Param I (b/w eter Be Units) V, 3.87 m/sec
II
III
IV
3.82
3.84
3.90
1.35
1.16
0.97
0.91
0.12
0.12
0.12
0.12
Tout, C
45
45
50
50
CHF, MW/m2
0.0
0.0
2.73
2.74
m, kg/sec Pout, MPa
Reactor Core Fuel Assemblies and LEU Target Maximum Temperatures and Safety Factors Reactor Core Power Level, MW 10 Paramete r
LEU Targe 8TFA t
8
6TFA
LEU Targe 8TFA t
5 LEU 6TFA Targe 8TFA t
6TFA
Tfuel,
124
116
108
115
104
97
91
84
79
Tclad,
123
115
107
115
103
96
91
83
79
Tboiling,
135
131
130
134
129
128
130
125
123
TONB,
136
120
119
122
118
118
119
116
116
Tsat,
107.2
DNBR
1.4
2.3
2.5
1.7
2.9
3.1
2.8
4.6
5.0
ONBF
1.2
1.2
1.4
1.3
1.5
1.6
1.9
2.1
2.4
Using PARET For Transient Calculation Coupled neutronics & thermal hydraulics One-dimensional (axial), multi channel. Present calculations use 3 channels 5. Steady State Calculation 6. Accidental Analysis 2.1 Control Rod Follower Disengagement 2.2 Loss of Flow Accident
ρ ρo C max
Tajoura Reactor Core at Several Transient Trips in the Case of Control Rod Follower Disengagement Overpow er Trip
Steady State Time, sec Power, MW Reactivit y, DNBR Tcool,
Max. Power Trip
-ve insertion Trip
–ve insertion trip
0
0.19
0.22
0.69
10.01
5
5.76
5.84
5.33
0.28
0
0.14
0.15
-0.25
-32.71
5.58 75.74
5.17 76.34
5.08 76.57
4.79 79.24
106.28 46.70
Tclad,
100.68
101.39
102.19
105.13
48.43
Tfuel,
104.15
105.23
106.09
109.11
48.62
Tajoura Reactor Core at Several Transient Trips in the Case of Loss of Flow Accident -ve Steady Overpower insertion State Trip Trip Time, sec Power, MW Reactivity,
–ve insertion trip
0
10.015
10.595
71.047
5
5.041
5.028
0.179
0
0.0028
-0.00002
-33.064
5.575
5.615
5.561
71.596
75.958
74.735
75.260
115.041
Tclad,
100.686
97.898
98.707
117.398
Tfuel,
104.153
101.394
102.181
117.527
DNBR Tcool,
From the steady state calculations for the Tajoura reactor core with LEU target at different power levels (Table 3) and from safety point of view, we conclude that the permissible reactor core operating power level is 5 MW. Finally, from the all cases of transient analysis results for Tajoura reactor core loaded with LEU target for 99Mo production, we conclude that the cladding surface temperature still remains much lower than the temperature at which clad damage might occur, when operate the reactor core at power level of 5 MW only.
THANK YOU FOR YOUR ATTENTION !!!!!!!!!!!!!!!!
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