Evaluation of radiation environment in the target area of fragment separator HFRS at HIAF

Evaluation of radiation environment in the target area of fragment separator HFRS at HIAF 1 2 first-author 1 corresp Corresponding author, suyouwu@impcas.ac.cn Corresponding author, suyouwu@impcas.ac.cn suyouwu@impcas.ac.cn 1 1 1 1 1 Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China University of Chinese Academy of Sciences, Beijing 100049, China University of Chinese Academy of Sciences, Beijing 100049, China In this work, the radiation environment in the target area of a fragment separator is evaluated using FLUKA code. The energy deposition in quadrupole coils is presented to provide guidance for a radiation resistant magnets’ design. Results show that neutrons dominate in the prompt radiation field. A compact shielding design is recommended for high radiation areas along with the minimization of air activation in the tunnel in order to minimize the radiation effect on nearby beam lines. The displacements per atom (DPA) results for the graphite target and copper coils indicate that the effect is insignificant. In addition, the activation level of the target is estimated for workers under possible hands-on maintenance condition. Fragment separator FLUKA Radiation levels Radiation damage 1 Introduction 1 The application of radioactive ion beams (RIBs) in nuclear physics and astrophysics led to the discovery of many new physical phenomena since it was first employed in Lawrence Berkeley Laboratory (LBL) by Tanihata in 1985 [ 1 1 ]. There are two prevalent approaches to produce RIBs. One is in-flight separation, which is also called the projectile fragmentation (PF) method, and the other is the isotope separation on line (ISOL) method [ 2 2 - 4 4 2-4 ]. Two radioactive ion beam lines RIBLL1 and RIBLL2 have been constructed in the Heavy Ion Research Facility in Lanzhou (HIRFL) and have been operated since 1998 and 2008, respectively. RIBs produced in both RIBLL1 and RIBLL2 are based on in-flight method and can provide multiple secondary beams in different energy ranges. Many experiments such as interaction cross-section measurement, proton halo studies, nuclear astrophysics studies, new isotope identification, and so on have been carried out using these two beam lines [ 5 5 - 9 9 5-9 ]. At present, there are many already-existing or under-plan RIBs facilities worldwide. FRS and Super-FRS in GSI, RIPS and BigRIPS in RIBF, FRIB in MSU, ISAC-I and ISAC-II in TRIUMF, HIE-ISOLDE in CERN, are a few examples of such facilities [ 3 3 , 4 4 , 7 7 , 10 10 - 15 15 10-15 ]. These facilities function in different energy regions, all owing for different reaction mechanisms, and therefore, they vary in the range of isotopes. A new radioactive ion beam line named HIAF FRagment Separator (HFRS) will be built at High Intensity heavy-ion Accelerator Facility (HIAF) by the Institute of Modern Physics (IMP) in the near future. The in-flight separation method will be employed in HFRS to produce RIBs. A schematic view of the HFRS in HIAF is given in Fig. 1 Fig. 1 [ 16 16 ]. It is located between the booster ring (BRing) and high precision spectrometer ring (SRing). It consists of a two-stage magnetic system, the pre-separator, and the main-separator, both of which are achromatic systems. The pre-separator is used to distinguish the primary beams from the secondary beams. The unreacted primary beams are stopped in the beam dumps located in the pre-separator. The secondary beams are separated and purified in the main-separator and finally transported to the terminals or SRing for conducting scientific research. The design parameters of the HFRS are listed in Table 1 Table 1 and compared with other in-flight fragment separators [ 3 3 - 11 11 3-11 , 17 17 ]. 1 1 Facility 1 1 Location 1 1 Ω (msr) 1 1 Δ p/p 1 1 B ρ max (Tm) 1 1 Momentum resolution 1 1 Length (m) 1 1 HFRS 1 1 IMP(China) 1 1 1.4 1 1 ±2.0 1 1 15.0 1 1 1500 1 1 152.0 1 1 RIBLL1 1 1 IMP(China) 1 1 >7.0 1 1 ±5.0 1 1 4.2 1 1 1200 1 1 35.0 1 1 RIBLL2 1 1 IMP(China) 1 1 2.0 1 1 ±1.0 1 1 10.64 1 1 1200 1 1 55.0 1 1 LISE 1 1 GANIL(France) 1 1 1.0 1 1 ±2.5 1 1 3.2 1 1 800 1 1 18.0 1 1 FRS 1 1 GSI(Germany) 1 1 0.2 1 1 ±1.0 1 1 18.0 1 1 1500 1 1 73.0 1 1 Super-FRS 1 1 GSI(Germany) 1 1 0.8 1 1 ±2.5 1 1 20.0 1 1 1500 1 1 140.0 1 1 RIPS 1 1 RIBF(Japan) 1 1 5.0 1 1 ±3.0 1 1 5.76 1 1 1500 1 1 21.0 1 1 Big-RIPS 1 1 RIBF(Japan) 1 1 8.0 1 1 ±3.0 1 1 9.0 1 1 1290/3300 1 1 77.0 1 1 COMBAS 1 1 Dubna(Russia) 1 1 6.0 1 1 ±10.0 1 1 4.5 1 1 4360 1 1 14.5 1 1 A1200 1 1 NSCL(USA) 1 1 0.8-4.3 1 1 ±1.5 1 1 5.4 1 1 700-1500 1 1 22.0 1 1 A1900 1 1 NSCL(USA) 1 1 8.0 1 1 ±2.25 1 1 6.0 1 1 2900 1 1 35.0 The high-energy and high-intensity primary beams are made incident on a target with a thickness of a few g/cm 2 , and the production and separation of interesting RIBs can induce a strong and complex radiation field in the HFRS, especially in the target and beam dump area. High-yield neutrons with strong penetrability dominate the prompt radiation field around high-energy heavy-ion accelerators [ 18 18 , 19 19 ]. The main objective of this study is to analyze and evaluate the prompt radiation field in the target area by using the FLUKA code and provide parameters for further shielding calculation. The magnets behind the target are exposed to a high-level radiation environment; therefore, the energy deposition in magnet coils has been calculated for the radiation resistant magnets’ design. Radiation damage evaluations for the target and magnet coils are also presented. In the end, in view of a possible hands-on maintenance of target by workers, the radionuclides produced in the target and the corresponding residual dose rate are estimated. 2 Monte Carlo calculations 1 The simulations were performed with the FLUKA Monte Carlo code version 2011. 2c.5. Nuclear interactions induced by ions were treated by linking different physical models such as DPMJET, RQMD, and BME [ 20 20 , 21 21 ]. The transport of low-energy neutrons ( E < 20 MeV) was performed using its own neutron cross section library, wherein the energy of interest was divided into a given number of intervals [ 20 20 ]. A rotated target with different thickness was employed in the HFRS. This design was similar to the Super-FRS at GSI [ 22 22 ], target-E at PSI [ 23 23 ], and Big-RIPS at RIKEN [ 24 24 ]. In this study, a static and circular disk of target with inner radius R 1 =13.5 cm and outer radius R 2 =22.5 cm was adopted in the model. The primary beams were considered incident on a point at R =( R 1 + R 2 )/2=18.0 cm. The beam spot on target was assumed to be ±1 mm and ±2 mm in the horizontal and vertical directions, respectively. The geometry model built in FLUKA is shown in Fig. 2 Fig. 2 . The target and a 40-cm-long cube iron shielding block were installed in the vacuum chamber. Three quadrupole magnets Q1, Q2, and Q3 were placed 130 cm, 330 cm, and 508 cm away from the target site, respectively. The magnetic field in quadrupoles was activated by the MGNFIELD and ASSIGNMA cards by compiling the user routine magfld.f with FORTRAN programming. Secondary particle yields were scored through the USRBDX card at 0°, 15°, 30°, 60°, and 90° angles; the range of each angle was ±2.5° except at 0°. For forward angle measurements, the statistical error was higher compared with that for other angles; hence, the angular range was set to ±4.0° in the 0° direction. Physical process for precision nuclear interaction was set by the PHYSICS card to activate electromagnetic dissociation, heavy fragment evaporation, and coalescence. The dose equivalent was calculated with the help of the USRBIN card together with the AUXSCORE card by linking the fluence-to-dose conversion coefficients. The IRRPROFI card and DCYTIMES card were used to define the irradiation time and decay time, respectively. The residual radionuclides were scored by the RESNUCLE card after the bombardment ended. Moreover, the value of the radiation damage threshold E th was obtained using the NJOY99 code [ 25 25 ], and set through the MAT-PROP card. The DEFAULTS card used in simulation was with the PRECISIO option. Cartesian binning, R - Φ - Z binning, and regional scoring methods were used in the calculation. 3 Results and discussion 1 Neutron yields depend on the projectile type, incident energy, and target material. Typical beam-target combinations of HFRS together with the FLUKA calculated neutron yields are listed in Table 2 Table 2 . The statistical error of yields is less than 2%. The results indicate that the highest neutron yield is achieved at 800 MeV/u 238 U impinging on a 4.0 g/cm 2 graphite target. Hence, the following calculations are based on this situation and the beam intensity is 3.33×10 10 pps (particles per second). 1 1 Ion 1 1 Energy (MeV/u) 1 1 Target 1 1 Yields (n/pri) 1 1 86 Kr 1 1 500 1 1 Be (1.0 g/cm 2 ) 1 1 2.8 1 1 86 Kr 1 1 1500 1 1 C (4.0 g/cm 2 ) 1 1 10.8 1 1 12 C 1 1 900 1 1 Be (8.0 g/cm 2 ) 1 1 3.5 1 1 124 Xe 1 1 1000 1 1 C (4.0 g/cm 2 ) 1 1 14.1 1 1 238 U 1 1 800 1 1 C (2.5 g/cm 2 ) 1 1 18.9 1 1 238 U 1 1 800 1 1 C (4.0 g/cm 2 ) 1 1 28.9 3.1 Energy deposition 2 The quadrupole magnets in the target area and the dipole magnets in the beam dump area are exposed to a high-level radiation environment. Hence, radiation resistant magnets need to be employed. In this work, the energy deposition in quadrupole coils is studied and presented as below. Table 3 Table 3 lists the radiation limit of various magnet materials [ 26 26 ]. 1 1 Material 1 1 Radiation limit (Gy) 1 1 NbTi 1 1 ≈ 5×10 8 1 1 Nb 3 Sn 1 1 ≈ 5×10 8 1 1 Copper 1 1 > 10 10 1 1 Ceramics(Al 2 O 3 , MgO, etc.) 1 1 > 10 9 1 1 Organics 1 1 10 6 -10 8 In calculation, coils were assumed to be made of pure copper and for each quadrupole, the coils were divided into five parts for dose calculation. The first and second layers in the front edge, third part in the iron yoke, and the fourth and fifth layers in the back edge, as shown in Fig. 4 Fig. 4 . The third part coil in a simplified geometry model of Q1 is shown in Fig. 3 Fig. 3 . Q2 is the same as Q1 while Q3 has the same structure but with different parameters. The lifetime of the magnets is determined by the peak dose in the coil. In this work, the energy deposition is scored with R - Φ - Z binning method, and very small binnings are used to determine the peak dose. R is given by the inner and outer radii of each coil and is divided into 120 bins. Φ is the azimuthal angle around Z (beam) axis and is set to 180 bins. Z -bins value is set to 400. The comparison of peak dose in different parts of coils is scaled to the same mesh size with 0.15 cm, 2°, and 0.25 cm as the values for R , Φ , and Z , respectively. To convert energy deposition expressed in GeV/cm 3 /pri to Gy/s (J/kg/s), the results were multiplied by 1.0e12 × C e- × I / ρ , where C e- is the electron charge, I is the beam intensity (pps), and ρ is the density of the material (g/cm 3 ). In view of the possible contribution of charged particles to the energy deposition on the coils, the magnetic field in the quadrupoles was added as discussed above. Peak dose distribution in three quadrupole coils is shown in Fig. 4(a) Fig. 4(a) . The results indicate that peak dose in the coil decreased gradually along the beam direction. Moreover, the peak dose in each part of Q1 was found to be greater than that in the corresponding part in Q2 and Q3. Peak dose in the first layer in the front edge of Q1 was 0.026 Gy/s, which is about a factor of 1.6 and 3.6 higher compared to that in Q2 and Q3. Fig. 4(b) Fig. 4(b) shows the dose distribution in the first layer in the front edge of Q1. Further, the results showed that neutrons are the major contributors to the energy deposition. In our simulation, a hollow iron shielding block was installed in the vacuum chamber to prevent the secondary particles. This can dramatically reduce the energy deposition in the coils, especially in Q1. Similar protection designs have been reported for other facilities [ 27 27 - 29 29 27-29 ]. For other coil materials such as Nb 3 Sn and NbTi listed in Table 3 Table 3 , owing to almost similar density as copper, similar results as in the case of copper were obtained. Assuming that the operation time of HFRS is 4000 hours per year, the accumulated dose in the first layer in the front edge of Q1 will be 4.176×10 5 Gy per year. In this case, copper can meet the operational requirement based on the radiation limit listed in Table 2 Table 2 . However, the dose limit of organic insulators like epoxy resin ranges from 10 6 Gy to 10 8 Gy, which is more radiation sensitive than other materials. Therefore, the energy deposition on organic insulators needs careful consideration. The results are obtained by replacing the copper coil with epoxy resin. As the insulator is very thin, the binning size is very small compared to the size used in copper. The results indicate that the peak dose in epoxy resin is 0.062 Gy/s, which is twice that of copper. Hence, metal-oxide insulation materials such as MgO, Al 2 O 3 , and others are suggested for the magnet design. A typical radiation resistant cable is Mineral Insulation Cable (MIC) for which the ceramic insulators are used. The cable allows direct water cooling with a hole in the center of the conductor; therefore, high current density can be achieved. 3.2 Prompt radiation field analysis 2 Neutron energy spectrum is given in Fig. 5(a) Fig. 5(a) . Broad peaks appear in the forward angles (0° and 15°) and are mainly caused by the high-energy neutrons shown in the results. These neutrons are emitted via the intra-nuclear cascade process with the same energy and direction as the incident particles. As the neutron energy increases, the distribution is more forward peaked as shown in Fig. 5(a) Fig. 5(a) and Fig. 5(b) Fig. 5(b) . In backward angles (larger angles), the proportion of high-energy neutrons is reduced and the peaks disappear gradually. Meanwhile, low-energy neutrons dominate in the backward angles, where the neutrons are mainly produced from the evaporation process of the compound nucleus and emit isotropically. With the increase of angle, the photon yields first decrease slightly, reaching a minimum at 90°, then increase gradually and remains unchanged at angles greater than 120°, as shown in Fig. 5(b) Fig. 5(b) . Fig. 6(a) Fig. 6(a) and Fig. 6(b) Fig. 6(b) show the prompt radiation field of the neutron and the photon, respectively. The results indicate that the neutron dose rate is about two orders of magnitude higher than the photon. For example, in the lateral direction of vacuum chamber, the neutron and photon dose rate is 2.20×10 5 mSv/h and 6.29×10 2 mSv/h, and 1.67×10 5 mSv/h and 5.71×10 2 mSv/h in the lateral direction of Q1, respectively. Along the beam direction, the dose rate gets reduced due to the shielding of quadrupoles. In Q2 and Q3 lateral direction, the dose rate is 1.54×10 4 mSv/h and 5.32×10 3 mSv/h for neutron and 62.7 mSv/h and 39.0 mSv/h for photon, respectively. Subsequent shielding calculations were based on these results. In order to reduce the radiation effect on nearby beam lines, air activation in the tunnel was minimized and a compact shielding design was employed in the preseparator of HFRS from the target area to focal plane PF2 (shown in Fig. 1 Fig. 1 ). 3.3 Radiation damage 2 Displacements per atom (DPA) is a measure of the amount of primary radiation damages in irradiated materials. The results of DPA and corresponding non-ionising energy losses due to energy deposition (shown as NIEL-DEP in FLUKA) caused by different particles are presented in Fig. 7 Fig. 7 . The results show that the uranium beam induced DPA decreased slightly with the increase of depth, whereas, for neutron, proton, and photon, the condition was found to be different, it increased first and then nearly stabilized at a certain value. For the uranium beam, the magnitude of the displacement rate is in 10 -7 dpa/s, followed by about 10 -10 dpa/s for neutron and proton while it is least at about 10 -16 dpa/s for photon. Hence, for the graphite target, primary uranium beams-induced radiation damages are the main contributions. The total DPA is 2.20 for 4000 hours of operation per year. As graphite is used as absorber in the beam dumps, the damages will be more severe due to the fact that all unreacted primary beams will be stopped in the graphite. For copper coils, the largest radiation damage appears in the first layer in the front edge of Q1. Neutrons are the main contributors and the damages induced by other particles are almost negligible; the total DPA is 1.53e-3 per year. Hence, the DPA results are expected to be insignificant for the graphite target and copper coil. In addition to the displacement damages, helium and hydrogen gas atoms participate in transmutation reactions during irradiation process. This also has a negative effect on mechanical properties. Hydrogen is believed to diffuse out of graphite due to the high temperature produced during irradiation while helium can accumulate in bubbles, which can grow at grain boundaries. These factors will lead to embrittlement and swelling in irradiated graphite and can shorten the lifetime. Other factors such as radiation heating, and mechanical stress will be discussed in the following work using the ANSYS software. 3.4 Residual activity in target 2 Activation calculations are given under 30 days irradiation. At the end of bombardment, 20 more radionuclides are produced in graphite target. The dominant radionuclides are depicted in Fig. 8 Fig. 8 . Short-lived isotopes like 13 B, 12 Be, 12 N, 9 C, 9 B, and 9 Li, will rapidly decay to a very low level. After one hour decay, the main contributions are 11 C, 7 Be, and 3 H, while later, up to six hours, 7 Be and 3 H become dominant. Most of the tritium will evaporate during irradiation as discussed above, so in a long operation period the activated graphite for target and beam dumps in HFRS might be a source of 7 Be and 10 Be. In order to move the activated components, radiation shielding bottle at PSI has been designed to move activated parts like target and beam dumps to a storage cell [ 23 23 ]. Residual dose rate at 20 cm from the surface of the target after different cooling times have also been evaluated for possible hands-on maintenance condition. The results are shown on the right Y-axis of Fig. 8 Fig. 8 . After one hour cooling, the dose rate is 3.64×3μSv/h, while later, up to six hours or longer, the dose rate decreased by two orders of magnitude and appeared to be unchanged at about 1.44×2μSv/h. For conservative calculation, the target will be changed after 6 hours of turning down the accelerator, each time takes one hour, and it is done 6 times in a year, so the annual dose is about 0.86 mSv for the workers. This value is below the dose limit 20 mSv/a for occupational radiation workers. In case of short time cooling, it is not advisable to conduct hands-on maintenance. Hence, remote handling needs to be executed. 4 Summary 1 Primary radiation environment evaluations have been conducted for the target area of fragment separator HFRS in HIAF by using the FLUKA program. The energy deposition in the quadrupole coils was analyzed. The largest value appeared in the first layer in the front edge of Q1 and the total dose was 4.176×10 5 Gy for 4000 hours of operation in a year. 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Ronningen et al ., Radiation resistant magnets for the RIA fragment separator . in Proceeeding of IPAC05 , Knoxville, USA , 16-20 May 2005 . doi: 10.1109/PAC.2005.1591056 http://doi.org/10.1109/PAC.2005.1591056 Radiation resistant magnets for the RIA fragment separator R. Ronningen , G. Bollen , V. Blideanu et al ., Radiation simulations and development of concepts for high power beam dumps, catchers and pre-separator area layouts for the fragment separators for RIA . in Proceeeding of IPAC05 , Knoxville, USA , 16-20 May 2005 . doi: 10.1109/PAC.2005.1591550 http://doi.org/10.1109/PAC.2005.1591550 Radiation simulations and development of concepts for high power beam dumps, catchers and pre-separator area layouts for the fragment separators for RIA 10.1007/s41365-018-0479-9 * This work was supported by the National Key Research and Development Program of China (No. 2017YFC0107700). 2017-08-16 2018-01-16 2018-03-12 2018-09-01 2018-10-01 2021-04-11 © China Science Publishing & Media Ltd. (Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, ChineseNuclear Society and Springer Nature Singapore Pte Ltd. 2018 This is a post-peer-review, pre-copyedit version of an article published in Nuclear Science and Techniques. The final authenticated version is available online at: http://dx.doi.org/10.1007/s41365-018-0479-9 http://dx.doi.org/10.1007/s41365-018-0479-9 . 2018 Nuclear Science and Techniques 10 29