kinetic analysis of coupled pulse reactor for npl experimenttobara/research/hikarigenshiro... ·...
TRANSCRIPT
Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
Toru Obara Hiroki TakezawaResearch Laboratory for Nuclear ReactorsTokyo Institute of Technology
American Nuclear Society 2010 Winter MeetingNovember 7-11 2010 Las Vegas Nevada Riviera Hotel amp Casino
2
BackgroundNuclear-Pumped Laser One of Direct Nuclear Energy Conversions
Nuclear Energy Optical Energy
Laser
Direct ConversionFP kinetic energy
Nuclear Reactor for Nuclear-Pumped Laser designed by IPPE Russia
Weakly Coupled System(Decoupled Spectrum System)
Fast neutrons pulsed from pulse cores
Diffusion and thermalization of the fast neutrons in the assembly
Pulse Cores (Fast Spectrum)
Subcritical Laser-Cell Assembly (Thermal Spectrum)
tU235 fissions on the fuel-coated wall +
Nuclear-pumping of laser medium
Laser-Cell
Front view Side view
Optical ApplicationsPhotonics Society
Pulse core with high-enriched uranium
High-enriched metallic uranium coating
3
Nuclear Pumped Laser Experiment reactor in IPPE
1 Fast pulse cores2 Laser cell assembly3 Inner polyethylene
moderator4 Outer polyethylene
moderator5 Laser cells
1 Moveable core2 Core3 Core4 Reactivity control system5 U-Mo alloy core6 Core cover7 B10+moderator8 Support tube9 Transient rod10 Reactivity control rod11 Safety rod
Expeiment reactor
BARS-6 pulse reactor
Front view Side view
① Coupled rector② Pulse
operation
4
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
Purpose of study
bull To show the possibility of performing NPL experiments using the pulse reactor concept with low-enriched uranium by performing kinetic analysis of the prompt supercritical condition
5
Methodology
Fission Density at region i
Secondary fission density in region i provided by the first fission in region j with time deference t-trsquo
Space-Dependent Kinetic Model
Fission Probability Density Function
Integral Kinetic Model + Monte Carlo Method
αij calculation method has developed using Monte Carlo method by the modified MVP20
6
Outline of αij calculation methodIntroduction of Cij
Time from the source fission
Cumulative number of fissions in region iby the time τ provided by the source
fission in region j
7
RegionFlight TimeFission Weight
Cij calculation formula
Non-analog Neutron Transport Monte Carlo
Method
Cij Calculation Formula
Source Region
Source Weight Ws
Source Weight
Microscopic fission probability Neutron Weight
End of History
t1t2 t3
t4t5Coln
Neutron Random Walk
Collision Estimator
Cumulative number of fissions in region i by the time τ
The number of the source fissions in region j
8
Space dependent kinetic calculation
1 Based on the integral transport equation2 Forward difference3 Stepwise reactivity insertion from critical condition in low power4 No delayed neutrons5 Temperature dependent Cij(τ) for feedback effect6 Temperature rise by fission power7 Cij(τ) by modified MVP20(νp eigenvalue calculation)
Kinetic analysis code using Cij has been developed
9
Calculation geometry of high-enriched uranium reactor
Region Enrichment
Pulse cores 1000wt
U coating 1000wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 10157Keff
p (800K) 10026
10
Calculation geometry of low-enriched uranium reactor
Region Enrichment
Pulse cores 200wt
U coating 200wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 1008Keff
p (800K) 09997
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
2
BackgroundNuclear-Pumped Laser One of Direct Nuclear Energy Conversions
Nuclear Energy Optical Energy
Laser
Direct ConversionFP kinetic energy
Nuclear Reactor for Nuclear-Pumped Laser designed by IPPE Russia
Weakly Coupled System(Decoupled Spectrum System)
Fast neutrons pulsed from pulse cores
Diffusion and thermalization of the fast neutrons in the assembly
Pulse Cores (Fast Spectrum)
Subcritical Laser-Cell Assembly (Thermal Spectrum)
tU235 fissions on the fuel-coated wall +
Nuclear-pumping of laser medium
Laser-Cell
Front view Side view
Optical ApplicationsPhotonics Society
Pulse core with high-enriched uranium
High-enriched metallic uranium coating
3
Nuclear Pumped Laser Experiment reactor in IPPE
1 Fast pulse cores2 Laser cell assembly3 Inner polyethylene
moderator4 Outer polyethylene
moderator5 Laser cells
1 Moveable core2 Core3 Core4 Reactivity control system5 U-Mo alloy core6 Core cover7 B10+moderator8 Support tube9 Transient rod10 Reactivity control rod11 Safety rod
Expeiment reactor
BARS-6 pulse reactor
Front view Side view
① Coupled rector② Pulse
operation
4
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
Purpose of study
bull To show the possibility of performing NPL experiments using the pulse reactor concept with low-enriched uranium by performing kinetic analysis of the prompt supercritical condition
5
Methodology
Fission Density at region i
Secondary fission density in region i provided by the first fission in region j with time deference t-trsquo
Space-Dependent Kinetic Model
Fission Probability Density Function
Integral Kinetic Model + Monte Carlo Method
αij calculation method has developed using Monte Carlo method by the modified MVP20
6
Outline of αij calculation methodIntroduction of Cij
Time from the source fission
Cumulative number of fissions in region iby the time τ provided by the source
fission in region j
7
RegionFlight TimeFission Weight
Cij calculation formula
Non-analog Neutron Transport Monte Carlo
Method
Cij Calculation Formula
Source Region
Source Weight Ws
Source Weight
Microscopic fission probability Neutron Weight
End of History
t1t2 t3
t4t5Coln
Neutron Random Walk
Collision Estimator
Cumulative number of fissions in region i by the time τ
The number of the source fissions in region j
8
Space dependent kinetic calculation
1 Based on the integral transport equation2 Forward difference3 Stepwise reactivity insertion from critical condition in low power4 No delayed neutrons5 Temperature dependent Cij(τ) for feedback effect6 Temperature rise by fission power7 Cij(τ) by modified MVP20(νp eigenvalue calculation)
Kinetic analysis code using Cij has been developed
9
Calculation geometry of high-enriched uranium reactor
Region Enrichment
Pulse cores 1000wt
U coating 1000wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 10157Keff
p (800K) 10026
10
Calculation geometry of low-enriched uranium reactor
Region Enrichment
Pulse cores 200wt
U coating 200wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 1008Keff
p (800K) 09997
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
3
Nuclear Pumped Laser Experiment reactor in IPPE
1 Fast pulse cores2 Laser cell assembly3 Inner polyethylene
moderator4 Outer polyethylene
moderator5 Laser cells
1 Moveable core2 Core3 Core4 Reactivity control system5 U-Mo alloy core6 Core cover7 B10+moderator8 Support tube9 Transient rod10 Reactivity control rod11 Safety rod
Expeiment reactor
BARS-6 pulse reactor
Front view Side view
① Coupled rector② Pulse
operation
4
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
Purpose of study
bull To show the possibility of performing NPL experiments using the pulse reactor concept with low-enriched uranium by performing kinetic analysis of the prompt supercritical condition
5
Methodology
Fission Density at region i
Secondary fission density in region i provided by the first fission in region j with time deference t-trsquo
Space-Dependent Kinetic Model
Fission Probability Density Function
Integral Kinetic Model + Monte Carlo Method
αij calculation method has developed using Monte Carlo method by the modified MVP20
6
Outline of αij calculation methodIntroduction of Cij
Time from the source fission
Cumulative number of fissions in region iby the time τ provided by the source
fission in region j
7
RegionFlight TimeFission Weight
Cij calculation formula
Non-analog Neutron Transport Monte Carlo
Method
Cij Calculation Formula
Source Region
Source Weight Ws
Source Weight
Microscopic fission probability Neutron Weight
End of History
t1t2 t3
t4t5Coln
Neutron Random Walk
Collision Estimator
Cumulative number of fissions in region i by the time τ
The number of the source fissions in region j
8
Space dependent kinetic calculation
1 Based on the integral transport equation2 Forward difference3 Stepwise reactivity insertion from critical condition in low power4 No delayed neutrons5 Temperature dependent Cij(τ) for feedback effect6 Temperature rise by fission power7 Cij(τ) by modified MVP20(νp eigenvalue calculation)
Kinetic analysis code using Cij has been developed
9
Calculation geometry of high-enriched uranium reactor
Region Enrichment
Pulse cores 1000wt
U coating 1000wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 10157Keff
p (800K) 10026
10
Calculation geometry of low-enriched uranium reactor
Region Enrichment
Pulse cores 200wt
U coating 200wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 1008Keff
p (800K) 09997
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
4
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
Purpose of study
bull To show the possibility of performing NPL experiments using the pulse reactor concept with low-enriched uranium by performing kinetic analysis of the prompt supercritical condition
5
Methodology
Fission Density at region i
Secondary fission density in region i provided by the first fission in region j with time deference t-trsquo
Space-Dependent Kinetic Model
Fission Probability Density Function
Integral Kinetic Model + Monte Carlo Method
αij calculation method has developed using Monte Carlo method by the modified MVP20
6
Outline of αij calculation methodIntroduction of Cij
Time from the source fission
Cumulative number of fissions in region iby the time τ provided by the source
fission in region j
7
RegionFlight TimeFission Weight
Cij calculation formula
Non-analog Neutron Transport Monte Carlo
Method
Cij Calculation Formula
Source Region
Source Weight Ws
Source Weight
Microscopic fission probability Neutron Weight
End of History
t1t2 t3
t4t5Coln
Neutron Random Walk
Collision Estimator
Cumulative number of fissions in region i by the time τ
The number of the source fissions in region j
8
Space dependent kinetic calculation
1 Based on the integral transport equation2 Forward difference3 Stepwise reactivity insertion from critical condition in low power4 No delayed neutrons5 Temperature dependent Cij(τ) for feedback effect6 Temperature rise by fission power7 Cij(τ) by modified MVP20(νp eigenvalue calculation)
Kinetic analysis code using Cij has been developed
9
Calculation geometry of high-enriched uranium reactor
Region Enrichment
Pulse cores 1000wt
U coating 1000wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 10157Keff
p (800K) 10026
10
Calculation geometry of low-enriched uranium reactor
Region Enrichment
Pulse cores 200wt
U coating 200wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 1008Keff
p (800K) 09997
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
5
Methodology
Fission Density at region i
Secondary fission density in region i provided by the first fission in region j with time deference t-trsquo
Space-Dependent Kinetic Model
Fission Probability Density Function
Integral Kinetic Model + Monte Carlo Method
αij calculation method has developed using Monte Carlo method by the modified MVP20
6
Outline of αij calculation methodIntroduction of Cij
Time from the source fission
Cumulative number of fissions in region iby the time τ provided by the source
fission in region j
7
RegionFlight TimeFission Weight
Cij calculation formula
Non-analog Neutron Transport Monte Carlo
Method
Cij Calculation Formula
Source Region
Source Weight Ws
Source Weight
Microscopic fission probability Neutron Weight
End of History
t1t2 t3
t4t5Coln
Neutron Random Walk
Collision Estimator
Cumulative number of fissions in region i by the time τ
The number of the source fissions in region j
8
Space dependent kinetic calculation
1 Based on the integral transport equation2 Forward difference3 Stepwise reactivity insertion from critical condition in low power4 No delayed neutrons5 Temperature dependent Cij(τ) for feedback effect6 Temperature rise by fission power7 Cij(τ) by modified MVP20(νp eigenvalue calculation)
Kinetic analysis code using Cij has been developed
9
Calculation geometry of high-enriched uranium reactor
Region Enrichment
Pulse cores 1000wt
U coating 1000wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 10157Keff
p (800K) 10026
10
Calculation geometry of low-enriched uranium reactor
Region Enrichment
Pulse cores 200wt
U coating 200wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 1008Keff
p (800K) 09997
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
6
Outline of αij calculation methodIntroduction of Cij
Time from the source fission
Cumulative number of fissions in region iby the time τ provided by the source
fission in region j
7
RegionFlight TimeFission Weight
Cij calculation formula
Non-analog Neutron Transport Monte Carlo
Method
Cij Calculation Formula
Source Region
Source Weight Ws
Source Weight
Microscopic fission probability Neutron Weight
End of History
t1t2 t3
t4t5Coln
Neutron Random Walk
Collision Estimator
Cumulative number of fissions in region i by the time τ
The number of the source fissions in region j
8
Space dependent kinetic calculation
1 Based on the integral transport equation2 Forward difference3 Stepwise reactivity insertion from critical condition in low power4 No delayed neutrons5 Temperature dependent Cij(τ) for feedback effect6 Temperature rise by fission power7 Cij(τ) by modified MVP20(νp eigenvalue calculation)
Kinetic analysis code using Cij has been developed
9
Calculation geometry of high-enriched uranium reactor
Region Enrichment
Pulse cores 1000wt
U coating 1000wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 10157Keff
p (800K) 10026
10
Calculation geometry of low-enriched uranium reactor
Region Enrichment
Pulse cores 200wt
U coating 200wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 1008Keff
p (800K) 09997
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
7
RegionFlight TimeFission Weight
Cij calculation formula
Non-analog Neutron Transport Monte Carlo
Method
Cij Calculation Formula
Source Region
Source Weight Ws
Source Weight
Microscopic fission probability Neutron Weight
End of History
t1t2 t3
t4t5Coln
Neutron Random Walk
Collision Estimator
Cumulative number of fissions in region i by the time τ
The number of the source fissions in region j
8
Space dependent kinetic calculation
1 Based on the integral transport equation2 Forward difference3 Stepwise reactivity insertion from critical condition in low power4 No delayed neutrons5 Temperature dependent Cij(τ) for feedback effect6 Temperature rise by fission power7 Cij(τ) by modified MVP20(νp eigenvalue calculation)
Kinetic analysis code using Cij has been developed
9
Calculation geometry of high-enriched uranium reactor
Region Enrichment
Pulse cores 1000wt
U coating 1000wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 10157Keff
p (800K) 10026
10
Calculation geometry of low-enriched uranium reactor
Region Enrichment
Pulse cores 200wt
U coating 200wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 1008Keff
p (800K) 09997
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
8
Space dependent kinetic calculation
1 Based on the integral transport equation2 Forward difference3 Stepwise reactivity insertion from critical condition in low power4 No delayed neutrons5 Temperature dependent Cij(τ) for feedback effect6 Temperature rise by fission power7 Cij(τ) by modified MVP20(νp eigenvalue calculation)
Kinetic analysis code using Cij has been developed
9
Calculation geometry of high-enriched uranium reactor
Region Enrichment
Pulse cores 1000wt
U coating 1000wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 10157Keff
p (800K) 10026
10
Calculation geometry of low-enriched uranium reactor
Region Enrichment
Pulse cores 200wt
U coating 200wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 1008Keff
p (800K) 09997
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
9
Calculation geometry of high-enriched uranium reactor
Region Enrichment
Pulse cores 1000wt
U coating 1000wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 10157Keff
p (800K) 10026
10
Calculation geometry of low-enriched uranium reactor
Region Enrichment
Pulse cores 200wt
U coating 200wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 1008Keff
p (800K) 09997
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
10
Calculation geometry of low-enriched uranium reactor
Region Enrichment
Pulse cores 200wt
U coating 200wt
Initial power 1WTime step Δt 10 x 10-7 sKeff
p (300K) 1008Keff
p (800K) 09997
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
11
Fission power in each region
① Delay of power peak in outer region
② Delay of power peak in low enriched uranium reactor
③ Power in laser cell region
①
②
11
③
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
12
Peak power density in laser cell tubes
Inner region Outer region
Peak power density [Wcm3] 12x103 62x102
Full width at half maximum [s] 4x10-3 4x10-3
Delay of power peak [s] - 1x10-4
High-enriched uranium reactor
Low-enriched uranium reactorInner region Outer region
Peak power density [Wcm3] 92x102 34x102
Full width at half maximum [s] 9x10-3 9x10-3
Delay of power peak [s] - 2x10-4
bull Threshold of laser pumping in Ar-Xe laser gasndash About 10 Wcm3 by Russian report
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
13
Conclusions
bull Kinetic analyses based on the method for weakly coupled systems were performed for a nuclear pumped laser experiment reactor
bull The calculation results show that it is possible to provide enough energy to the laser gas medium in the cell tubes not only in the reactor with highly enriched uranium but also in the reactor with low enriched uranium
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-
14
Conclusions (continued)
bull It is also possible to provide enough energy to both the laser cell tubes in the inner region and the tubes in the outer region far from the pulse cores
bull It was also found that there was some delay of the peak of the power in the cell tubes in the outer region which was caused by neutron thermalization and diffusion in the thermal laser module
bull It was shown that performing NPL experiments using the pulse reactor concept with low-enriched uranium was possible
Toru Obara ANS 2010 Winter Meeting Las Vegas Nevada (2010)
- Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment
- Background
- Nuclear Pumped Laser Experiment reactor in IPPE
- Purpose of study
- Methodology
- Outline of αij calculation method
- Cij calculation formula
- スライド番号 8
- Calculation geometry of high-enriched uranium reactor
- Calculation geometry of low-enriched uranium reactor
- Fission power in each region
- Peak power density in laser cell tubes
- Conclusions
- Conclusions (continued)
-