study of radiation effect on rpv steel
Post on 15-Nov-2014
118 Views
Preview:
DESCRIPTION
TRANSCRIPT
Asian Physics Symposium 2007 Bandung
Study of Radiation Effect on Study of Radiation Effect on RPV Steel Using Monte RPV Steel Using Monte
Carlo MethodCarlo Method
Topan Setiadipura, Elfrida Saragi, Topan Setiadipura, Elfrida Saragi, Khairina NsKhairina Ns
tsdipura@batan.go.idtsdipura@batan.go.id
Computational DivisionComputational DivisionCenter for Development of Nuclear Center for Development of Nuclear
Informatics Informatics BATAN –INDONESIABATAN –INDONESIA
Asian Physics Symposium 2007 Bandung
PreviewPreview
ObjectiveObjective Introduction:Introduction:
- radiation damage issue of RPV- radiation damage issue of RPV- multiscale computing- multiscale computing
Computational MethodComputational Method- Monte Carlo or MCNP model- Monte Carlo or MCNP model- Tally - Tally
ResultsResults Conclusion and DiscussionConclusion and Discussion
Asian Physics Symposium 2007 Bandung
ObjectiveObjective
To demonstrate the application of To demonstrate the application of monte carlo method as particle monte carlo method as particle transport and reaction simulation in transport and reaction simulation in radiation effect simulation.radiation effect simulation.
As preliminary calculation of nuclear As preliminary calculation of nuclear parameter in material subjected to parameter in material subjected to neutron irradiation.neutron irradiation.
Asian Physics Symposium 2007 Bandung
IntroductionIntroduction The safety of commercial light-water The safety of commercial light-water
reactors is highly dependent on the reactors is highly dependent on the structural integrity of the RPV. The structural integrity of the RPV. The degrading effects of neutron degrading effects of neutron irradiation on carbon and low-alloy irradiation on carbon and low-alloy pressure vessel steels have been pressure vessel steels have been recognized and investigated since the recognized and investigated since the early 1950s. early 1950s.
• • In those steels at RPV operating In those steels at RPV operating temperatures (260~288temperatures (260~288°°C), radiation C), radiation damage is produced when neutrons damage is produced when neutrons of sufficient energy displace atoms of sufficient energy displace atoms from their lattice sites. from their lattice sites.
Asian Physics Symposium 2007 Bandung
Introduction (cont’d)Introduction (cont’d)
• • The synergistic The synergistic effects of neutron effects of neutron fluence, flux, and fluence, flux, and spectrum, the spectrum, the irradiation irradiation temperature, and the temperature, and the chemical composition chemical composition and microstructure and microstructure of the steel must be of the steel must be understood to reduce understood to reduce the uncertainties the uncertainties associated with the associated with the development of development of predictive models of predictive models of embrittlement.embrittlement.
Asian Physics Symposium 2007 Bandung
Asian Physics Symposium 2007 Bandung
Multiscale Physics and ModellingMultiscale Physics and Modelling
An illustration of the sequence of basic embrittlement processes: (a) creation of primary radiation damage defects: (b) formation of nanoscale solute and defect clusters (iron atoms not shown); (c) pinning of dislocations and hardening by nanofeatures; (d) hardening enhanced cleavage fracture; at a (e) stress concentration.
Asian Physics Symposium 2007 Bandung
Monte Carlo MethodMonte Carlo Method
Simulation approach to Simulation approach to particle transport :particle transport :
““Faithfully simulate the hystory of a Faithfully simulate the hystory of a single particle from birth to death.single particle from birth to death.
Random walk for single Random walk for single particleparticle
- Model collisions using physics - Model collisions using physics equations & cross-section data.equations & cross-section data.
- Model free-flight between collisions - Model free-flight between collisions using computational geometry.using computational geometry.
- Tally the occurences of events in - Tally the occurences of events in each regioneach region
- Save any secondary particle, - Save any secondary particle, analyze them later.analyze them later.
Asian Physics Symposium 2007 Bandung
Track Length Estimate of Cell Flux Track Length Estimate of Cell Flux (F4 Tally)(F4 Tally)
The quantity The quantity NN(r,(r,EE,,tt))ds ds may be thought of as may be thought of as a track length density; thus, the average flux a track length density; thus, the average flux can be estimated by summing track lengths. can be estimated by summing track lengths.
Asian Physics Symposium 2007 Bandung
Material CompositionMaterial Composition
Material C Si Mn P S Ni Cr Cu Mo Fe density
JRQ 0.18 0.24 1.42 0.017 0.004 0.84 0.12 0.14 0.51 96.529 7.765087
Steel A 0.19 0.3 1.3 0.015 0.01 0.68 0.17 0.16 0.53 96.645 7.750524
Steel B 0.19 0.19 1.43 0.004 0.001 0.65 0.13 0.04 0.5 96.865 7.771709
Steel L 0.17 0.24 1.36 0.003 0.003 0.61 0.07 0.02 0.47 97.054 7.768824
Asian Physics Symposium 2007 Bandung
ResultsResultsNeutron Fluence Distribution
5.20E-03
5.40E-03
5.60E-03
5.80E-03
6.00E-03
6.20E-03
6.40E-03
6.60E-03
1 3 5 7 9 11 13 15 17 19
Depth/layer
JRQ
Steel L
Asian Physics Symposium 2007 Bandung
Distribution of (n,H) reaction
3.70E-053.80E-053.90E-054.00E-054.10E-054.20E-054.30E-054.40E-054.50E-054.60E-054.70E-05
1 3 5 7 9 11 13 15 17 19
Depth/layer
JRQ
Steel L
Asian Physics Symposium 2007 Bandung
Distribution of (n,gamma) reaction
2.30E-072.40E-072.50E-072.60E-072.70E-072.80E-072.90E-073.00E-073.10E-07
Depth/layer
JRQ
Steel L
Asian Physics Symposium 2007 Bandung
Distribution of (n,d) reactions
1.40E-06
1.45E-06
1.50E-06
1.55E-06
1.60E-06
1.65E-06
1.70E-06
1.75E-06
1 3 5 7 9 11 13 15 17 19
Depth/layer
JRQ
Steel L
Asian Physics Symposium 2007 Bandung
Distribution of (n,alpha) reactions
1.05E-05
1.10E-05
1.15E-05
1.20E-05
1.25E-05
1.30E-05
1.35E-05
1 3 5 7 9 11 13 15 17 19
Depth/layer
JRQ
Steel L
Asian Physics Symposium 2007 Bandung
Total Cross SectionTotal Cross Section
Asian Physics Symposium 2007 Bandung
Elastic Cross SectionElastic Cross Section
Asian Physics Symposium 2007 Bandung
Absorption Cross SectionAbsorption Cross Section
Asian Physics Symposium 2007 Bandung
ConclusionConclusion Preliminary calculation have been performed by Monte Preliminary calculation have been performed by Monte
Carlo method using the continous energy MCNP 5 transport Carlo method using the continous energy MCNP 5 transport code to determine the nuclear parameters in the RPV steel code to determine the nuclear parameters in the RPV steel as an effect of neutron radiation.as an effect of neutron radiation.
The parameters include the high energy neutron fluence The parameters include the high energy neutron fluence distribution, the defect production in form of H,D, and He distribution, the defect production in form of H,D, and He atoms, photon production and primary knock-on atoms, atoms, photon production and primary knock-on atoms, nuclear heating, yield of the nuclear reaction on certain nuclear heating, yield of the nuclear reaction on certain isotop.isotop.
Further calculation to determine the primary damage and Further calculation to determine the primary damage and its transport/diffusion on the steel because of the neutron its transport/diffusion on the steel because of the neutron radiation is needed.radiation is needed.
Further analyses of the effect of each particle resulted Further analyses of the effect of each particle resulted haven’t been discussed, it need a co-operation with other haven’t been discussed, it need a co-operation with other division.division.
top related