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The JPARC Neutrino Target
Y.Hayato (ICRR, Univ. of Tokyo) for T.Nakadaira & J-PARC n beam-line construction group (I borrowed most of all the transparencies from Nakadaira-san)
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J-PARC neutrino beam line
Primary Proton beam line Proton Energy 50GeV T=0) # of Protons / pulse 3.31014 Beam Power 750kW Phase II Extraction point Target Target station Bunch structure Decay volume 8 (15) bunches/spill Spill width ~5ms beam dump muon monitor Cycle: 3~4 sec Near neutrino detector Bunch spacing: ~600(300) ns Bunch length: 58ns (Full width)
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Target Station Accommodate Area filled with Helium gas
Baffle: Graphite, 32mmf hole x 1.7m long to protect 1st horn Target 3 Horns Area filled with Helium gas reduce Tritium, NOx production Highly radio-activated ~1Sv/h, Need remote-controlled maintenance system Need cooling (Helium vessel, radiation shield,..) 3rd horn 2nd horn Trg& 1st horn Baffle Target Baffle beam 1st Horn 2nd Horn 3rd Horn
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Target dimension Cooing path
Co-axial 2 layer cooling pipe: Graphite / Ti-6Al-4V, Helium cooling Outer pipe 47.0 46.4 39.6 35.6 26.0 Ti-6Al-4V [mm] Inner pipe IG-43 target IG-43 spacer Sectional area = 4.610-4 [m2] Cooing path f=47mm f=26mm
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One design of the target & surrounding cooling pipe
(Not the final design). 陽子ビーム He inlet He outlet Ti-6Al-4V Beam window Ti-6Al-4V 陽子ビーム Target Need further design study Graphite IG-43
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Design of inlet and outlet of He Gas is not fixed.
} To downstream } To downstream Design of inlet and outlet of He Gas is not fixed.
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Disadvantage Target cooling : Water or Helium? Water Cooling
Helium Gas cooling Very Efficient High Heat transfer ratio Already tested. Simple circulation system We can control Ttarget to minimize the irradiation effect. (Ttarget = 400 ~ 800 C) Reduce radioactive waste water No target container is needed large Irradiation effect Ttarget 300C to avoid the water boiling: surface < 100C Target container is needed. DPwater= ~2MPa due to the temperature rise by a beam hit. Huge radioactive waste water Very High flow rate ~ 2000 l/min [0.5MPa] ~ l/min [0.1MPa] Circulation system is complicated. Special treatment for the high temperature gas (200C) is necessary. Advantage Disadvantage
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Target : Conceptual design
Core: Isotropic-Graphite : IG-43 (Toyo Tanso Co. Ltd) Energy deposit… Total: ~40kJ/spill (30GeV) DT 200K. seq = 7.5 [MPa] Tensile strength = 37.2 [MPa] Distribution of the energy deposit in the target (w/ 1 spill) J/gK degree MARS proton beam cm f=47mm f=26mm
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Energy deposit (30GeV, s x= s y =4.24mm) Target 39.3 [kJ/spill]
R target 13 [mm] DR (target ~ horn) 3[mm] Energy deposit (30GeV, s x= s y =4.24mm) Target 39.3 [kJ/spill] 3.5 [kJ/spill] 1.1 [kJ/spill] 1.5 [kJ/spill] 99.09% (0.91%loss) Inner Pipe Outer Pipe Insulator Targeting Efficiency For Gaussian beam Helium flow (T gas < 200C, suction=0.03MPa) Cross section 459.3 [mm2] 491 [Nm3/h] 246 [m/s] [MPa] Flow rate Avg. target part+1st hex
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Irradiation Effect of Graphite
Expected radiation damage of the target The approximation formula used by NuMI target group : 0.25dpa/year MARS simulation : 0.15~0.20 dpa/year Dimension change : shrinkage by ~5mm in length in 5 years at maximum ~75mm in radius Degradation of thermal conductivity … decreased by 97% @ 200 C 400 C Magnitude of the damage strongly depends on the irradiation temperature. It is better to keep the temperature of target around 400 ~ 800 C 400 600 800 1000 Irradiation Temperature(C) 1 2 3 (dpa) 400oC 800oC Thermal conductivity (After/Before) JAERI report (1991) 2dpa -0.5% 1dpa Dimension change Toyo-Tanso Co Ltd. IG-11
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FEM simulation of He cooling
Assumptions: 0.19MPa He Initial temperature: 25 C He flow rate: [l/min] 194 [m/sec] Heat convection rate: 820 [W/m2/K] (50GeV,f=15mm) Target Temperature Helium Temperature Max: ~ 500 C Min: ~ 300 C Avg. : ~380 C Max: ~160 C (DT = 135 C) Avg. : ~40 C
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FEM simulation of He cooling
(50GeV,f=15mm) Assumptions: 0.19MPa (Possible pressure drop at the downstream of target is taken into account.) He Initial temperature: 25 C He flow rate: [l/min] 194 [m/sec] Heat convection rate: [W/m2/K]
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fin.
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