2021 Vol. 38, No. 2
Display Method:
2021, 38(2): 117-122.
doi: 10.11804/NuclPhysRev.38.2020084
Abstract:
The nucleus 28S (isospin projection\begin{document}$ T_{Z}=-2 $\end{document} ![]()
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The nucleus 28S (isospin projection
2021, 38(2): 123-128.
doi: 10.11804/NuclPhysRev.38.2021019
Abstract:
Neutron star matter is mainly composed of asymmetric dense nuclear matter. At present, there is still great uncertainty in the understanding of the high-density asymmetric nuclear matter through the terrestrial experiments, such as the heavy ion collisions. With the improvement of astronomical observation accuracy and the increase of observable measurements of neutron stars, it is possible to reverse constraint the state of high-density nuclear matter based on astronomical observation of neutron stars. Theoretically investigating the correlation between the observable measurements of neutron stars and the equation of states (EOSs) at different density sections will be helpful to the research of the reverse constraints. In this work, by employing the piecewise polytrope EOSs, the observable measurements of the radius(R), tidal deformability(\begin{document}$\varLambda$\end{document} ![]()
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\begin{document}$M \!=\! 1.4\, M_{\odot}$\end{document} ![]()
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\begin{document}$0.5\rho_{\rm{sat}} \!\sim\! 1.5\rho_{ sat}$\end{document} ![]()
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Neutron star matter is mainly composed of asymmetric dense nuclear matter. At present, there is still great uncertainty in the understanding of the high-density asymmetric nuclear matter through the terrestrial experiments, such as the heavy ion collisions. With the improvement of astronomical observation accuracy and the increase of observable measurements of neutron stars, it is possible to reverse constraint the state of high-density nuclear matter based on astronomical observation of neutron stars. Theoretically investigating the correlation between the observable measurements of neutron stars and the equation of states (EOSs) at different density sections will be helpful to the research of the reverse constraints. In this work, by employing the piecewise polytrope EOSs, the observable measurements of the radius(R), tidal deformability(
2021, 38(2): 129-135.
doi: 10.11804/NuclPhysRev.38.2021022
Abstract:
Configurations are the basis of lattice QCD calculations. In this paper, we generate a set of configurations with the Wilson clover quark action using the open source software Chroma. The parameters are tuned such that the lattice spacing is ~0.105 fm, pion mass is ~220 MeV. The volume is\begin{document}$32^3 \times 64$\end{document} ![]()
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Configurations are the basis of lattice QCD calculations. In this paper, we generate a set of configurations with the Wilson clover quark action using the open source software Chroma. The parameters are tuned such that the lattice spacing is ~0.105 fm, pion mass is ~220 MeV. The volume is
2021, 38(2): 136-146.
doi: 10.11804/NuclPhysRev.38.2021010
Abstract:
This paper discusses the finite-volume effect in calculating hadron form factors using lattice QCD framework. Taking Pion as the example, we introduce the method of extracting hadron form factors from three-point correlation functions computed in lattice QCD, but only at separated points in the momentum space because of the finite-volume effect. This paper gives one interpolation algorithm which respects rotation symmetry and also provides a sketch of another interpolation method which applies the continuous Fourier transform, both methods continuously giving form factor results on the momentum space based on the discrete values. These algorithms are examined under numerical models and realistic lattice systems. The results given by the interpolation are independent of specific systems and can be easily generalized to a variety of lattice systems. Our conclusion also provides valuable information which could help determining the proper size of lattice systems.
This paper discusses the finite-volume effect in calculating hadron form factors using lattice QCD framework. Taking Pion as the example, we introduce the method of extracting hadron form factors from three-point correlation functions computed in lattice QCD, but only at separated points in the momentum space because of the finite-volume effect. This paper gives one interpolation algorithm which respects rotation symmetry and also provides a sketch of another interpolation method which applies the continuous Fourier transform, both methods continuously giving form factor results on the momentum space based on the discrete values. These algorithms are examined under numerical models and realistic lattice systems. The results given by the interpolation are independent of specific systems and can be easily generalized to a variety of lattice systems. Our conclusion also provides valuable information which could help determining the proper size of lattice systems.
2021, 38(2): 147-152.
doi: 10.11804/NuclPhysRev.38.2021001
Abstract:
The beam energy extracted from cyclotron is fixed, it is necessary to adjust it to meet different demands of different experiments. This study focuses on the feasibility of using thin film materials to change the beam energy. The ranges of 30 MeV α beams (extracted from cyclotron) in materials include diamond, aluminum and copper are calculated by the SRIM program, and the relationship between material thickness and the required beam energy is determined. The horizontal and vertical emittances of α beams, after being reduced to 9 MeV by interacting with different materials, are calculated by G4Beamline program. The following results are obtained: After penetrating the thin film materials, the size of beam spot approximately remained the same. The growth of beam transverse emittances is mainly caused by the increase of the divergence angles, among which the diamond film causes the least increase of beam emittance, and the root mean square value of the divergence angle is about 16 mrad. There is no significant dependency on the value of initial beam divergence angle (the root mean square value of initial divergence angle is less than 1 mrad). Vertical energy spread caused by different materials is about 1 MeV (FWHM) that is only determined by the final beam energy and has no connection with the kind of material. The more energy has lost, the greater the energy spread would be. Besides, the 30 MeV initial α beams interacting with thin film materials (diamond, copper, aluminum etc.) could produce about 109/μA neutrons and γ particles, so radiation protection must be considered in practical applications.
The beam energy extracted from cyclotron is fixed, it is necessary to adjust it to meet different demands of different experiments. This study focuses on the feasibility of using thin film materials to change the beam energy. The ranges of 30 MeV α beams (extracted from cyclotron) in materials include diamond, aluminum and copper are calculated by the SRIM program, and the relationship between material thickness and the required beam energy is determined. The horizontal and vertical emittances of α beams, after being reduced to 9 MeV by interacting with different materials, are calculated by G4Beamline program. The following results are obtained: After penetrating the thin film materials, the size of beam spot approximately remained the same. The growth of beam transverse emittances is mainly caused by the increase of the divergence angles, among which the diamond film causes the least increase of beam emittance, and the root mean square value of the divergence angle is about 16 mrad. There is no significant dependency on the value of initial beam divergence angle (the root mean square value of initial divergence angle is less than 1 mrad). Vertical energy spread caused by different materials is about 1 MeV (FWHM) that is only determined by the final beam energy and has no connection with the kind of material. The more energy has lost, the greater the energy spread would be. Besides, the 30 MeV initial α beams interacting with thin film materials (diamond, copper, aluminum etc.) could produce about 109/μA neutrons and γ particles, so radiation protection must be considered in practical applications.
2021, 38(2): 153-158.
doi: 10.11804/NuclPhysRev.38.2020080
Abstract:
The BUMP power supply is the key equipment responsible for the beam extraction of the medical heavy ion accelerator. The synchronization of the current rise affects the extraction efficiency of the beam, and the diversity of the current waveform is closely related to the treatment mode and treatment accuracy. It is necessary to generate 1~5 ms rising and accurately synchronized excitation current on the convex rail magnet (0.2~0.4 mH), and ensure the current tracking and the diversity of the waveform. Real-time adjustment of the strong excitation voltage and current waveform based on characteristic parameters are adopted. Control Method. This article introduces the software and hardware design of the digital controller for the BUMP power supply based on Inter's SoC(System-on-a-Chip) technology, and it is applied to the medical heavy ion accelerator device for the first time. After field verification, it is produced on different convex rail magnets. The synchronously changing current of 1~5 ms is achieved, and the tracking accuracy (>5 s) of the current rising period is guaranteed, which meets the design requirements.
The BUMP power supply is the key equipment responsible for the beam extraction of the medical heavy ion accelerator. The synchronization of the current rise affects the extraction efficiency of the beam, and the diversity of the current waveform is closely related to the treatment mode and treatment accuracy. It is necessary to generate 1~5 ms rising and accurately synchronized excitation current on the convex rail magnet (0.2~0.4 mH), and ensure the current tracking and the diversity of the waveform. Real-time adjustment of the strong excitation voltage and current waveform based on characteristic parameters are adopted. Control Method. This article introduces the software and hardware design of the digital controller for the BUMP power supply based on Inter's SoC(System-on-a-Chip) technology, and it is applied to the medical heavy ion accelerator device for the first time. After field verification, it is produced on different convex rail magnets. The synchronously changing current of 1~5 ms is achieved, and the tracking accuracy (>5 s) of the current rising period is guaranteed, which meets the design requirements.
2021, 38(2): 159-165.
doi: 10.11804/NuclPhysRev.38.2020074
Abstract:
In recent years, ion therapy technology has developed rapidly in China and abroad. To meet the demands of the accelerator commissioning and the energy requirements of the different treatment scheme for the accelerator facility, the power supplies of the dipole magnets in the energy selection and beam transport system are required to work in the modes of DC, in-order trigger and periodic pulse. Using the integrated box controller independently developed by the Institute of Modern Physics, Chinese Academy of Sciences, the control and protection function of the power supply are realized. In order to meet the requirements of commissioning and treatment working modes, the controller has been designed to support the local and remote control network protocols, between which the switch can be achieved through the button on the touch screen. The power supply specifications has been tested after the main circuit and controller were designed and assembled. The test results indicate that the power supply can work well under the different modes, the long-term stability of current rating reached 21 ppm, and the current ripple was less than 0.000 4, exceeding the design index.
In recent years, ion therapy technology has developed rapidly in China and abroad. To meet the demands of the accelerator commissioning and the energy requirements of the different treatment scheme for the accelerator facility, the power supplies of the dipole magnets in the energy selection and beam transport system are required to work in the modes of DC, in-order trigger and periodic pulse. Using the integrated box controller independently developed by the Institute of Modern Physics, Chinese Academy of Sciences, the control and protection function of the power supply are realized. In order to meet the requirements of commissioning and treatment working modes, the controller has been designed to support the local and remote control network protocols, between which the switch can be achieved through the button on the touch screen. The power supply specifications has been tested after the main circuit and controller were designed and assembled. The test results indicate that the power supply can work well under the different modes, the long-term stability of current rating reached 21 ppm, and the current ripple was less than 0.000 4, exceeding the design index.
2021, 38(2): 166-174.
doi: 10.11804/NuclPhysRev.38.2020064
Abstract:
Due to the existence of a large number of nonlinear devices in the accelerator system, a large number of ripples are generated, which seriously affects the control of the accelerator magnetic field on the particle trajectory. In order to realize the suppression of accelerator DC power supply ripple, related researches mainly focused on using voltage-type active power filter to reduce DC power supply ripple, but this method has problems such as insufficient suppression accuracy, response delay, and large switchgear loss. In view of the above problems, this paper compares the main circuit topology of current-type and voltage-type active power filters, investigates the pulse width modulation technology and control strategies of current-type and voltage-type active power filters, and analyzes the performance of different active power filters in the accelerator system to suppress the output current ripple of magnet power supply. Through simulation analysis and experimental verification, it is found that the current-type active power filter has a significant suppression effect on the output current ripple of the magnet power supply, and the current-type active power filter can directly control the output ripple current, and the ripple accuracy is suppressed more highly. With the CSAPF put into use, the load current ripple is significantly reduced, and the current ripple coefficient reaches 1.6×10–5.
Due to the existence of a large number of nonlinear devices in the accelerator system, a large number of ripples are generated, which seriously affects the control of the accelerator magnetic field on the particle trajectory. In order to realize the suppression of accelerator DC power supply ripple, related researches mainly focused on using voltage-type active power filter to reduce DC power supply ripple, but this method has problems such as insufficient suppression accuracy, response delay, and large switchgear loss. In view of the above problems, this paper compares the main circuit topology of current-type and voltage-type active power filters, investigates the pulse width modulation technology and control strategies of current-type and voltage-type active power filters, and analyzes the performance of different active power filters in the accelerator system to suppress the output current ripple of magnet power supply. Through simulation analysis and experimental verification, it is found that the current-type active power filter has a significant suppression effect on the output current ripple of the magnet power supply, and the current-type active power filter can directly control the output ripple current, and the ripple accuracy is suppressed more highly. With the CSAPF put into use, the load current ripple is significantly reduced, and the current ripple coefficient reaches 1.6×10–5.
2021, 38(2): 175-181.
doi: 10.11804/NuclPhysRev.38.2020063
Abstract:
High-purity and low-background nitrogen plays an important role in the low-background experiments, and it is necessary to study radioactive impurities removal technology and low-background radon measurement in nitrogen. The research uses low-temperature adsorption technology to remove radioactive impurities in nitrogen. At the same time, electrostatic collection and low-temperature enrichment methods are combined to measure ~10 μBq/m3 radon in nitrogen. The result shows that the purification system can reduce the radon background in nitrogen by 20 mBq/m3 to (25.2±5) μBq/m3, namely, can reduce the radon background by 800 times. It is also found that the purification capacity is related to the radon background in nitrogen. In the range of radon background from dozens of mBq/m3 to dozens of μBq/m3, the purification capacity decreases with the lower radon background. The main reason is that the adsorption capacity decreases with the lower partial pressure of radon. In addition, the influence of radon pollution caused by system background and leakage increases significantly under very low background.
High-purity and low-background nitrogen plays an important role in the low-background experiments, and it is necessary to study radioactive impurities removal technology and low-background radon measurement in nitrogen. The research uses low-temperature adsorption technology to remove radioactive impurities in nitrogen. At the same time, electrostatic collection and low-temperature enrichment methods are combined to measure ~10 μBq/m3 radon in nitrogen. The result shows that the purification system can reduce the radon background in nitrogen by 20 mBq/m3 to (25.2±5) μBq/m3, namely, can reduce the radon background by 800 times. It is also found that the purification capacity is related to the radon background in nitrogen. In the range of radon background from dozens of mBq/m3 to dozens of μBq/m3, the purification capacity decreases with the lower radon background. The main reason is that the adsorption capacity decreases with the lower partial pressure of radon. In addition, the influence of radon pollution caused by system background and leakage increases significantly under very low background.
2021, 38(2): 182-189.
doi: 10.11804/NuclPhysRev.38.2020062
Abstract:
The Back-n White Neutron Source is located in China Spallation Neutron Source(CSNS). It aims to measure nuclear data under different neutron energies. The neutron’s energy is obtained by the Time Of Flight(TOF) of neutron. In experiment, the time when proton bunches hit the thick tungsten target is considered as the start point of TOF(T0), and the corresponding electronic signal is used to trigger the whole electronic system. The accuracy fan-out of T0 signal will have a significant influence on the accuracy of the TOF measurement and the synchronization of each channel of electronic system. A two-stage accuracy fan-out method of back-n T0 signal is proposed. The T0 signal from CSNS proton accelerator is fanned out by T0 fan-out module to two underground experiment station through long cable. The fan-out module uses signal pre-emphasis technology to improve the signal transmission quality of T0 signal through more than 100 m long cable and guarantee that the T0 signal has a very fast signal leading edge, so as to ensure the accuracy of time timing. The electronic system takes the advantage of the high-performance backplane resources of the chassis by PXIe, so as to realize the global precision and synchronous fan-out of T0 signal. The experimental results show that the leading edge jitter of the T0 signal distributed by the fan-out module reaches 25 ps, the multi-channel accuracy of the chassis reaches 45 ps, and the measurement accuracy of the TOF can reach 248 ps, which meets the requirements of the measurement accuracy of the neutron time of flight of the white light neutron source.
The Back-n White Neutron Source is located in China Spallation Neutron Source(CSNS). It aims to measure nuclear data under different neutron energies. The neutron’s energy is obtained by the Time Of Flight(TOF) of neutron. In experiment, the time when proton bunches hit the thick tungsten target is considered as the start point of TOF(T0), and the corresponding electronic signal is used to trigger the whole electronic system. The accuracy fan-out of T0 signal will have a significant influence on the accuracy of the TOF measurement and the synchronization of each channel of electronic system. A two-stage accuracy fan-out method of back-n T0 signal is proposed. The T0 signal from CSNS proton accelerator is fanned out by T0 fan-out module to two underground experiment station through long cable. The fan-out module uses signal pre-emphasis technology to improve the signal transmission quality of T0 signal through more than 100 m long cable and guarantee that the T0 signal has a very fast signal leading edge, so as to ensure the accuracy of time timing. The electronic system takes the advantage of the high-performance backplane resources of the chassis by PXIe, so as to realize the global precision and synchronous fan-out of T0 signal. The experimental results show that the leading edge jitter of the T0 signal distributed by the fan-out module reaches 25 ps, the multi-channel accuracy of the chassis reaches 45 ps, and the measurement accuracy of the TOF can reach 248 ps, which meets the requirements of the measurement accuracy of the neutron time of flight of the white light neutron source.
2021, 38(2): 190-195.
doi: 10.11804/NuclPhysRev.38.2020058
Abstract:
Since neutron sensitive microchannel plates (nMCP) has high detection efficiency and the spatial resolution, combined with advanced readout electronics it can be a better choice for energy-resolved neutron imaging detectors. Compared with the matrix-doped nMCP, the nMCP based on Atomic Layer Deposition(ALD) has the advantages of less neutron sensitive material consumption and high secondary electron emission coefficient on the inner wall of the channel. Firstly, the typical neutron and gamma signal of natGd-doped nMCP were studied experimentally. Geant4 simulation and theoretical calculation were performed to optimize the pore diameter, wall thickness, bias angle and coating thickness of the coated 10B2O3 nMCP. It was shown that the thermal neutron detection efficiency was about 56% and the spatial resolution was about 22 μm when the coating thickness was 1 μm, the pore diameter was 10 μm, the wall thickness was 1 μm and the bias angle was 3°. The results are of great significance to the geometric parameter design of nMCP used as energy-resolved neutron imaging detectors at CSNS.
Since neutron sensitive microchannel plates (nMCP) has high detection efficiency and the spatial resolution, combined with advanced readout electronics it can be a better choice for energy-resolved neutron imaging detectors. Compared with the matrix-doped nMCP, the nMCP based on Atomic Layer Deposition(ALD) has the advantages of less neutron sensitive material consumption and high secondary electron emission coefficient on the inner wall of the channel. Firstly, the typical neutron and gamma signal of natGd-doped nMCP were studied experimentally. Geant4 simulation and theoretical calculation were performed to optimize the pore diameter, wall thickness, bias angle and coating thickness of the coated 10B2O3 nMCP. It was shown that the thermal neutron detection efficiency was about 56% and the spatial resolution was about 22 μm when the coating thickness was 1 μm, the pore diameter was 10 μm, the wall thickness was 1 μm and the bias angle was 3°. The results are of great significance to the geometric parameter design of nMCP used as energy-resolved neutron imaging detectors at CSNS.
2021, 38(2): 196-202.
doi: 10.11804/NuclPhysRev.38.2021003
Abstract:
The model of Active-Well Coincidence Counter(AWCC) was established by MCNPX, meanwhile, with two types of induced neutron source (Am-Li and Am-Be), the neutron coincidence count rate of low enriched uranium was simulated, and the comparison of the measurement accuracy between the two simulations was also demonstrated. It was found that the coincidence count rate induced by Am-Be source was lower than that induced by Am-Li source, and the fitting degree of scaled mass curve under Am-Be source was better than that under Am-Li source, the corresponding relative error was also lower than that of under Am-Li source. The relative error range of uranium mass corresponding to the inspection point under Am-Li source is 0.3%~13%. The relative error range under Am-Be source is 0.1%~4.5%. According to the results, for the measurement of the mass of low enriched uranium by AWCC, it could be better to choose Am-Be source for reducing measurement relative error.
The model of Active-Well Coincidence Counter(AWCC) was established by MCNPX, meanwhile, with two types of induced neutron source (Am-Li and Am-Be), the neutron coincidence count rate of low enriched uranium was simulated, and the comparison of the measurement accuracy between the two simulations was also demonstrated. It was found that the coincidence count rate induced by Am-Be source was lower than that induced by Am-Li source, and the fitting degree of scaled mass curve under Am-Be source was better than that under Am-Li source, the corresponding relative error was also lower than that of under Am-Li source. The relative error range of uranium mass corresponding to the inspection point under Am-Li source is 0.3%~13%. The relative error range under Am-Be source is 0.1%~4.5%. According to the results, for the measurement of the mass of low enriched uranium by AWCC, it could be better to choose Am-Be source for reducing measurement relative error.
2021, 38(2): 203-209.
doi: 10.11804/NuclPhysRev.38.2020052
Abstract:
The irradiation hardening and embrittlement behavior of three kinds of Oxide Dispersion Strengthened(ODS) steel (MA956, 16Cr-4Al, 16Cr-0.1Ti) are investigated by using the HIRFL(Heavy Ion Research Facility in Lanzhou). The main motivation is to find the relation between diameter and density of the oxides and irradiation hardening/embrittlement behavior of different ODS steels. These three kind of materials are irradiated by Ne and Ni ions, and get a uniform damage layer by using the energy degrader. The Nano-hardness and elongation of the materials are obtained by Nano-indentation and small punch test. The sink strength was calculated with the mean diameter and density of the materials. Then followed by nano-indentation test and small punch test to get the irradiation hardening and ductility loss. Results show that irradiation resistance of the materials rise with sink strength(S) increasing.
The irradiation hardening and embrittlement behavior of three kinds of Oxide Dispersion Strengthened(ODS) steel (MA956, 16Cr-4Al, 16Cr-0.1Ti) are investigated by using the HIRFL(Heavy Ion Research Facility in Lanzhou). The main motivation is to find the relation between diameter and density of the oxides and irradiation hardening/embrittlement behavior of different ODS steels. These three kind of materials are irradiated by Ne and Ni ions, and get a uniform damage layer by using the energy degrader. The Nano-hardness and elongation of the materials are obtained by Nano-indentation and small punch test. The sink strength was calculated with the mean diameter and density of the materials. Then followed by nano-indentation test and small punch test to get the irradiation hardening and ductility loss. Results show that irradiation resistance of the materials rise with sink strength(S) increasing.
Classical Electron Capture in Collisions of Ions with H, He Atoms at Low and Intermediate Velocities
2021, 38(2): 210-214.
doi: 10.11804/NuclPhysRev.38.2021007
Abstract:
The Bohr-Lindhard (B-L) model is used to describe the classical electron-capture process. The impact-parameter dependence of the capture probability is derived by considering the impact-parameter dependence of the collision time between ion and atom. This model limits the impact parameter to be less than the capture radius. In the framework of the B-L model, although the contribution from all impact parameters may be studied through the spatial distribution function of electrons, the multiple numerical integral has to be carried out. In this work, it is proposed that the impact-parameter dependence of the electron-capture probability can be given by a simple exponential decay function based on the (B-L) model. Electron-capture cross sections for Aq+(q=2~6)-H collisions, and double-electron-capture cross sections for Aq+(q=3~6)-He collisions are calculated at low and intermediate velocities. The calculated results are in good agreement with the existing experimental data. The energy and charge-state dependences of the electron-capture process are well described. This work can also be used to calculate the cross sections of electron capture from He and H targets by other ions with different charge states.
The Bohr-Lindhard (B-L) model is used to describe the classical electron-capture process. The impact-parameter dependence of the capture probability is derived by considering the impact-parameter dependence of the collision time between ion and atom. This model limits the impact parameter to be less than the capture radius. In the framework of the B-L model, although the contribution from all impact parameters may be studied through the spatial distribution function of electrons, the multiple numerical integral has to be carried out. In this work, it is proposed that the impact-parameter dependence of the electron-capture probability can be given by a simple exponential decay function based on the (B-L) model. Electron-capture cross sections for Aq+(q=2~6)-H collisions, and double-electron-capture cross sections for Aq+(q=3~6)-He collisions are calculated at low and intermediate velocities. The calculated results are in good agreement with the existing experimental data. The energy and charge-state dependences of the electron-capture process are well described. This work can also be used to calculate the cross sections of electron capture from He and H targets by other ions with different charge states.
2021, 38(2): 215-220.
doi: 10.11804/NuclPhysRev.38.2020066
Abstract:
In heavy-ion cancer therapy, Compton camera is a promising tool for online monitoring of the range of ions. Compton camera uses crystal detectors to determine the positions and deposited energies of the\begin{document}$\gamma$\end{document} ![]()
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In heavy-ion cancer therapy, Compton camera is a promising tool for online monitoring of the range of ions. Compton camera uses crystal detectors to determine the positions and deposited energies of the
2021, 38(2): 221-228.
doi: 10.11804/NuclPhysRev.38.2020075
Abstract:
Based on the influence "hydrogen bubbles" and "helium bubbles", which are produced by the neutron induced reactions on Fe, of the new nuclear energy utilization system, the 56,54Fe(n, α)53,51Cr, 56,54Fe(n, p)56,54Mn cross sections are calculated in this work. The physical model (including energy level density, Correction, nuclear temperature, optical potential parameters, etc.) parameters were adjusted according to the existing experimental data and evaluation data of 56,54Fe(n, α)53,51Cr, 56,54Fe(n, p)56,54Mn cross sections, and a set of universal parameters were obtained. Based on the adjusted parameters, the TALYS program is used for calculating 56,54Fe(n, α)53,51Cr, 56,54Fe(n, p)56,54Mn reaction datas, including energy differential cross section and double differential cross section. Furthermore, the results are all in good agreement with the experimental data and evaluation data in the region of incident neutron energy from 0 to 175 MeV. By obtaining the universal parameters, new method was added to our nuclear reaction theory and laid the foundation for the nuclear data evaluation.
Based on the influence "hydrogen bubbles" and "helium bubbles", which are produced by the neutron induced reactions on Fe, of the new nuclear energy utilization system, the 56,54Fe(n, α)53,51Cr, 56,54Fe(n, p)56,54Mn cross sections are calculated in this work. The physical model (including energy level density, Correction, nuclear temperature, optical potential parameters, etc.) parameters were adjusted according to the existing experimental data and evaluation data of 56,54Fe(n, α)53,51Cr, 56,54Fe(n, p)56,54Mn cross sections, and a set of universal parameters were obtained. Based on the adjusted parameters, the TALYS program is used for calculating 56,54Fe(n, α)53,51Cr, 56,54Fe(n, p)56,54Mn reaction datas, including energy differential cross section and double differential cross section. Furthermore, the results are all in good agreement with the experimental data and evaluation data in the region of incident neutron energy from 0 to 175 MeV. By obtaining the universal parameters, new method was added to our nuclear reaction theory and laid the foundation for the nuclear data evaluation.
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