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Simulations in support of RIA Target Area R&D Reg Ronningen NSCL/MSU Igor Remec ORNL 2 nd High-Power Targetry Workshop October 10–14, 2005 Oak Ridge, TN.

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Presentation on theme: "Simulations in support of RIA Target Area R&D Reg Ronningen NSCL/MSU Igor Remec ORNL 2 nd High-Power Targetry Workshop October 10–14, 2005 Oak Ridge, TN."— Presentation transcript:

1 Simulations in support of RIA Target Area R&D Reg Ronningen NSCL/MSU Igor Remec ORNL 2 nd High-Power Targetry Workshop October 10–14, 2005 Oak Ridge, TN

2 RIA R&D Participants (now starting 2 nd year of funded effort) Argonne National Lab: J. Nolen, C. Reed, T. Levand, I. Gomez Lawrence Berkley National Lab: L. Heilbronn Lawrence Livermore National Lab: L. Ahle, J. Boles, S. Reyes, W. Stein Michigan State U./National Superconducting Cyclotron Lab: I. Baek, V. Blideanu, G. Bollen, D. Lawton, P. Mantica, D. Morrissey, R. Ronningen, B. Sherrill, A. Zeller Oak Ridge National Lab: J. Beene, T. Burgess, D. Conner, T. Gabriel, I. Remec, M. Wendel

3 Outline Ronningen –Examples of Simulations for Fragment Pre- Separator Area Pre-Conceptual Design Quadrupole radiation damage simulations Beam Dump simulations Bulk Shielding Remec –Examples of Simulations for ISOL Target Area Pre-Conceptual Design Two-step target simulations Large-scale simulations examples

4 A Sampling of RIA Primary Beams IONAZ ENERGY (MeV/nucleon) H111019 3 He32777 D21622 O188560 Ar4018566 Kr8636510 Xe13654470 U23892400 Current technology limits U to about 130 kW. All the rest are 400 kW.

5 Where Do Primary Beam and Fragments Go?

6 Sample Beam-Fragment Combinations

7 Target Beam Dump Quadrupoles Dipole Resistive Sextupole Simple Geometry of Fragment Pre-Separator for Simulations W Shield Developed using MORITZ Geometry Editor (White Rock Science)

8 Primary beam 400 MeV/u 238 U Cu beam dump Transport of Primary Beam using PHITS

9 TargetBeam dump Steel shell surrounding system Resistive sextupole Neutron Flux in Pre-Separator using PHITS: 48Ca beam at 500 MeV/u

10 Target Hevimet shield Frames are cryostat walls HTS Coil: Ag+BSCCO Insulator: AlO+He “Realistic” Quadrupole Geometry using BNL Design with Realistic Material Compositions

11 Neutron Flux in Target, 1 st Quad Area - No Magnetic Field

12 Neutron spectrum at the coil for 136 Xe at 500 MeV/u (PHITS simulation)

13 Protons – no magnetic field

14 Protons – Quadrupole magnetic field ON

15 Total Heat Tally

16 Triplet heat – no magnetic fields Like the peak magnetic field determining the conductor requirements, the maximum dose in a single area determines the coil life time. Note the dose is a factor of two higher than calculations done for a single quad. This is because of the enclosure reflecting low energy neutron back into the coils. The peak doses on each subsequent quad is only reduced by a factor of two due to both the reflected neutrons and the high flux of very energetic ones (>100 MeV).

17 Using an average density of 10 g/cm 3, 10 mW/cm 3 give a dose rate of 1 Gy/s With 10 7 s per year operation, this is 10 MGy dose. If HTS is as radiation resistant as Nb 3 Sn (500 MGy), then coils last 50 years. Plan to test HTS 12/05 at LBNL with protons. It will be compared with Nb 3 Sn, which has known tolerance. Coil Life Estimate

18 Advanced beam dump designs To mitigate radiation damage, rotating beam dump concepts are being considered In particular, a rotating barrel-shaped dump has been designed capable of withstanding a 1cm-diameter beam spot U beam stops in cooling water, avoiding high DPA values in structural material Need to address prompt and decay dose to sensitive components in rotating vacuum seal

19 Radiation transport results We have used the heavy ion transport code PHITS to simulate particle transport in pre-separator area Model includes barrel beam dump, steel water inlet/outlet pipes, hub region with representative materials and downstream multipole magnet Assumed operation with a 320 MeV U beam with 1 cm-diameter spot size at a current of 3x10 13 pps

20 Vacuum enclosure and dipole included

21 Radiation transport results: prompt dose and DPA MaterialDensity (g/cc) Effective dose (MGy/yr*) Dose limit (MGy) DPA/yr* NdFeB60.290.14.5E-06 SmCo8.820.151005.9E-06 Kapton1.420.74107.6E-07 FerroFluid1.421.08>1?7.1E-07 Dose to NdFeB magnet exceeds recommended limit after ~ 2 months of full power operation: shielding needed to extend lifetime DPA in the hub materials found to be negligible Maximum DPA rate in the Al barrel ~0.03 DPA/yr* (most of the primary beam stops in water); maximum DPA in multipole ~5x10 -4 DPA/yr* Peak energy deposition in multipole = 0.03 W/cc, with 2.1 kW total *Assumed that fragmentation line is operating at full power for one-third of the calendar year

22 Borated (5 wt%) polyethylene shielding around NdFeB magnet (5 cm thick spherical shell) MaterialDensity (g/cc)Effective dose (MGy/yr*) Limit (MGy) NdFeB60.050.1 * Assumes operational for 1/3 of each year

23 Simplified geometry model Water wheel dump with 3 mm Al window STST shaft containing water Sample materials outside concrete enclosure: LCS, FerroFluid, Kapton, SmCo Vacuum region enclosure (2 m thick concrete walls) AIR surrounding the whole system 136Xe at 341 MeV/u, 3.74x10 13 ions/sec

24 Investigate Radioactivity Inventory for Components

25

26 Proton, 3 He, 238 U Comparison U-238 : 400 MeV/u He-3 : 777 MeV/uproton : 1 GeV Beam on stopping Cu target Beam direction

27 Compare Effective Dose Equivalent for Different Beams

28 Results for Proton Beam and Concrete Shield

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