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Neutron Diffraction Investigation of the DyFe11Ti Magnetic Structure and Its Spin Reorientations Article

Olivier Isnard, Eder J. Kinast

Engineering 2020, Volume 6, Issue 2,   Pages 153-157 doi: 10.1016/j.eng.2019.11.009

Abstract: , we report on the magnetic structure of DyFe11Ti and its thermal evolution as probed by neutronpowder diffraction.

Keywords： Neutron diffraction     Magnetic phase diagram     Crystal structure    

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lipophilic penetration enhancers on the nano-structure of stratum corneum model membranes studied using neutrondiffraction

Annett SCHROETER, Tanja ENGELBRECHT, Reinhard H. H. NEUBERT

Frontiers of Chemical Science and Engineering 2013, Volume 7, Issue 1,   Pages 29-36 doi: 10.1007/s11705-013-1302-0

Abstract: The influence of the enhancer molecules were studied using specifically deuterated OA and IPM and neutrondiffraction.

Keywords： nano-structure of the stratum corneum     ceramide     penetration enhancer     model membrane     neutron diffraction    

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Optimization design for the epithermal neutron duct of in-hospital neutron irradiator mark 1 reactor

Jiang Xinbiao,Zhu Yangni,Zhao Zhumin,Chen Lixin,Zhou Yongmao

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 33-37

Abstract: text-align: justify;">Optimization design for the moderation layer and reflection layer of the epithermal neutronduct at in-hospital neutron irradiator mark 1(IHNI-1) reactor is carried out by using MCNP in this papercompared with Al materials, and two moderation optimization schemes which can obtain intensive epithermal neutronFinally, based on the moderation layer and reflection layer optimization schemes, the neutron and gammaspace distribution of the epithermal neutron beam at exit of this duct are detailed calculated.

Keywords： IHNI-1 reactor     epithermal neutron beam     neutron flux density    

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Air bearing center cross gap of neutron stress spectrometer sample table support system

Yang LI,Yunxin WU,Hai GONG,Xiaolei FENG

Frontiers of Mechanical Engineering 2016, Volume 11, Issue 4,   Pages 403-411 doi: 10.1007/s11465-016-0405-y

Abstract:

A support system is the main load-bearing component of sample table for neutron stress spectrometerThe neutron stress spectrometer sample table was introduced, and the scheme for air bearing combination

Keywords： neutron stress spectrometer     sample table     support system     air bearing     center cross gap     simulation     experiment    

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Preliminary characterization of radiation fields of IHNI-1 for BNCT

Chen Jun,Li Chunjuan,Song Mingzhe,Li Wei,Yao Shunhe,Diao Lijun,Yao Yanling,Zhang Zizhu,Gao Jijin,Zhang Yifan

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 106-112

Abstract:

The characteristic parameters of the neutron radiation fields producedby an in-hospital neutron irradiatior for boron neutron capture therapy(BNCT), such as neutron energyspectra, neutron flux density and neutron absorbed dose rate and their spatial distributions in freeimprove the energy resolution in epithermal energy range and the ability to discriminate different neutronThe preliminary results show that the neutron flux densities of the irradiators achieve the expected

Keywords： in-hospital neutron irradiatior for BNCT     neutron enengy spectrum     neutron flux density     absorbed doserate of neutron and γ ray    

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Transmission probability method based on triangle meshes for solving the unstructured geometry neutron

WU Hongchun, LIU Pingping, ZHOU Yongqiang, CAO Liangzhi

Frontiers in Energy 2007, Volume 1, Issue 2,   Pages 158-166 doi: 10.1007/s11708-007-0020-z

Abstract: The fuel assembly or core with unstructured geometry is frequently used in the advanced reactor. To calculate the fuel assembly, the transmission probability method (TPM) is widely used. However, the rectangular or hexagonal meshes are mainly used in the TPM codes for the normal core structure. The triangle meshes are most useful for expressing the complicated unstructured geometry. Even though the finite element method and Monte-Carlo method are well suited for solving the unstructured geometry problem, they are very time-consuming. Therefore, a TPM code based on the triangle meshes is developed here. This code was applied to the hybrid fuel geometry, and compared with the results of the MCNP code and other codes. The results of the comparison were consistent with each other. The TPM with triangle meshes can thus be applied to the two-dimensional arbitrary fuel assembly.

Keywords： unstructured geometry     assembly     transmission probability     TPM     rectangular    

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High-Throughput Powder Diffraction Using White X-Ray Beam and a Simulated Energy-Dispersive Array Detector Article

Xiaoping Wang, Weiwei Dong, Peng Zhang, Haoqi Tang, Lanting Zhang, Tieying Yang, Peng Liu, Hong Wang, X.-D. Xiang

Engineering 2022, Volume 10, Issue 3,   Pages 81-88 doi: 10.1016/j.eng.2021.05.023

Abstract:

High-throughput powder X-ray diffraction (XRD) with white X-ray beam and an energy-dispersive detectorCareful analysis and corrections are applied to account for various experimental hardware-related and diffractionThe resulting diffraction patterns show that the relative strength between different diffraction peaksXRF counts from all pixels are integrated directly by energy, while the diffraction spectra are integratedIn comparison with ARXRD, the diffraction signal generated by a white X-ray beam over monochromic light

Keywords： High-throughput experiment     White beam X-ray diffraction     Energy-dispersive array detector     Energy-dispersiveX-ray diffraction     Angle-resolved X-ray diffraction    

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Numerical calculation for the equivalent surface source of the thermal neutron duct of in-hospital neutron

Zhu Yangni,Jiang Xinbiao,Zhao Zhumin,Zhang Liang,Zhou Yongmao

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 56-59

Abstract: style="text-align: justify;">Numerical calculation for the equivalent surface source of the thermal neutronduct of in-hospital neutron irradiator mark 1(IHNI-1) reactor is carried out using MCNP Monte CarloNeutron beam parameters at the exit of thermal neutron duct are calculated.Equivalent neutron and γ surface sources for BNCT are built using equivalent surface source model

Keywords： IHNI－1 reactor     thermal neutron duct     equivalent neutron surface source     equivalent γ surface source    

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Studies on preparation of folate-targeted boron liposomes as potential delivery agents for neutron capture

Wang Zhihui,Qin Linxue,Liu Dong

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 78-81

Abstract: liposomes with high encapsulation efficiency is an effective targeted drug delivery agent for boron neutron

Keywords： boron neutron capture therapy     liposomes     folate-targeted     encapsulation efficiency    

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The boron neutorn capture therapy (BNCT) status to go into the new era

Zhou Yongmao

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 4-13

Abstract: boron concentration quantifed detecting, the targeting boron compound composing and the in hospitor neutron

Keywords： neutron capture therapy     clinical trial     tumour recurrence     boron concentration detect     targeting boroncompound     in hospital neutron irradiator    

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Discrete ordinates method for three-dimensional neutron transport equation based on unstructured-meshes

JU Haitao, WU Hongchun, YAO Dong, XIAN Chunyu

Frontiers in Energy 2008, Volume 2, Issue 2,   Pages 179-182 doi: 10.1007/s11708-008-0024-3

Abstract: A discrete ordinates method for a three-dimensional first-order neutron transport equation based on unstructured-meshesthat avoids the singularity of the second-order neutron transport equation in void regions was derivedThe numerical results of some benchmark problems demonstrated that this method can solve neutron transport
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Performance and characteristic of in-hospital neutron irradiator

Li Yiguo,Xia Pu,Peng Dan,Zou Shuyun,Wu Xiaobo,Zhang Jinhua,Zhang Zizhu,Gao Jijin,Wang Liyu,Fu Jinshu,Liu Tong,Zhou Yongmao

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 20-22

Abstract:

The design of in hospital neutron irradiator (IHNI) and its systems were

Keywords： in-hospital neutron irradiator(IHNI)     boron neutron capture therapy(BNCT)     inherent safety    

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The effect of group structure on calculation of kinetic parameters of in-hospital neutron irradiator

Zhang LIang,Zhao Zhumin,Jiang Xinbiao,Chen Wei,Zhou Yongmao

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 47-50

Abstract:

The kinetic parameters of in-hospital neutron irradiator mark 1 (IHNI-1) reactor, effective delayed neutron fraction and neutron generation time are calculated by CKPWC（calculating

Keywords： IHNI-1 reactor     kinetic parameter     effective delayed neutron fraction     neutron generation time    

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Development of MCBurn and its application in the analysis of SCWR physical characteristics

Ganglin YU , Kan WANG ,

Frontiers in Energy 2009, Volume 3, Issue 3,   Pages 348-352 doi: 10.1007/s11708-009-0031-z

Abstract: reactor physical design and analysis, such as criticality, power distribution, nuclide burn up, and neutronsupercritical water reactor (SCWR) physical calculations, the calculation conditions such as the geometry, the neutronIn this paper, several update functions of the MCBurn in new neutron cross-section lib, code interface, and neutron flux distribution were described.

Keywords： Monte Carlo method     MCBurn     SCWR     neutron cross-section lib    

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Wave Interaction with a Partial Porous Double-Wall Cylinder

Teng Bin,Li Yucheng,Sun Lu

Strategic Study of CAE 2001, Volume 3, Issue 10,   Pages 41-47

Abstract:

A linear analytic solution is derived for wave interaetion with a combined cylinder with a solid interior column surrounded by a coaxial porous exterior column. The solution is established on an eigenfunction expansion of velocity potential and a linear model between the fluid velocity inside a porous wall and the pressure difference between two sides of the wall. Numerical experiments have been carried out to examine the wave force and wave run-up on combined porous cylinders with different porous coefficient, porous section, and ratio between the radii of the interior and exterior columns. It is found that the porous rate of the exterior wall and the size of the porous section have a significant influence on the wave run-up and wave loads on cylinders. Cylinders with whole porous section on the outer column are more suitable for reducing wave loads and wave run-up on cylinders.

Keywords： wave diffraction     wave force     wave run-up     porous structure     cylinder    

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Title Author Date Type Operation

Neutron Diffraction Investigation of the DyFe11Ti Magnetic Structure and Its Spin Reorientations

Olivier Isnard, Eder J. Kinast

Journal Article

lipophilic penetration enhancers on the nano-structure of stratum corneum model membranes studied using neutrondiffraction

Annett SCHROETER, Tanja ENGELBRECHT, Reinhard H. H. NEUBERT

Journal Article

Optimization design for the epithermal neutron duct of in-hospital neutron irradiator mark 1 reactor

Jiang Xinbiao,Zhu Yangni,Zhao Zhumin,Chen Lixin,Zhou Yongmao

Journal Article

Air bearing center cross gap of neutron stress spectrometer sample table support system

Yang LI,Yunxin WU,Hai GONG,Xiaolei FENG

Journal Article

Preliminary characterization of radiation fields of IHNI-1 for BNCT

Chen Jun,Li Chunjuan,Song Mingzhe,Li Wei,Yao Shunhe,Diao Lijun,Yao Yanling,Zhang Zizhu,Gao Jijin,Zhang Yifan

Journal Article

Transmission probability method based on triangle meshes for solving the unstructured geometry neutron

WU Hongchun, LIU Pingping, ZHOU Yongqiang, CAO Liangzhi

Journal Article

High-Throughput Powder Diffraction Using White X-Ray Beam and a Simulated Energy-Dispersive Array Detector

Xiaoping Wang, Weiwei Dong, Peng Zhang, Haoqi Tang, Lanting Zhang, Tieying Yang, Peng Liu, Hong Wang, X.-D. Xiang

Journal Article

Numerical calculation for the equivalent surface source of the thermal neutron duct of in-hospital neutron

Zhu Yangni,Jiang Xinbiao,Zhao Zhumin,Zhang Liang,Zhou Yongmao

Journal Article

Studies on preparation of folate-targeted boron liposomes as potential delivery agents for neutron capture

Wang Zhihui,Qin Linxue,Liu Dong

Journal Article

The boron neutorn capture therapy (BNCT) status to go into the new era

Zhou Yongmao

Journal Article

Discrete ordinates method for three-dimensional neutron transport equation based on unstructured-meshes

JU Haitao, WU Hongchun, YAO Dong, XIAN Chunyu

Journal Article

Performance and characteristic of in-hospital neutron irradiator

Li Yiguo,Xia Pu,Peng Dan,Zou Shuyun,Wu Xiaobo,Zhang Jinhua,Zhang Zizhu,Gao Jijin,Wang Liyu,Fu Jinshu,Liu Tong,Zhou Yongmao

Journal Article

The effect of group structure on calculation of kinetic parameters of in-hospital neutron irradiator

Zhang LIang,Zhao Zhumin,Jiang Xinbiao,Chen Wei,Zhou Yongmao

Journal Article

Development of MCBurn and its application in the analysis of SCWR physical characteristics

Ganglin YU , Kan WANG ,

Journal Article

Wave Interaction with a Partial Porous Double-Wall Cylinder

Teng Bin,Li Yucheng,Sun Lu

Journal Article