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Numerical calculation for the equivalent surface source of the thermal neutron duct of in-hospital neutronirradiator mark 1 reactor

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

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

Abstract:

Numerical calculation for the equivalent surface source of the thermalneutron duct of in-hospital neutron irradiator mark 1(IHNI-1) reactor is carried out using MCNP MonteNeutron 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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Analysis of the core thermal-hydraulic characteristics of in-hospital neutron irradiatormark 1 reactor

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

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 51-55

Abstract:

According to the characteristics and operation condition of IHNI-1 reactorIt also has been verified that the model is reasonable and effective in IHNI-1's thermal hydraulicUsing the model, some thermal parameters of IHNI-1reactor are calculated.;s coolant inlet flux and outlet temperature is analyzed, and the variation of rod temperature with reactor

Keywords： IHNI-1 reactor     thermal-hydraulic     subchannel     safety analysis    

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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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Influence evaluation of loading conditions during pressurized thermal shock transients based on thermal-hydraulics

Jinya KATSUYAMA, Shumpei UNO, Tadashi WATANABE, Yinsheng LI

Frontiers of Mechanical Engineering 2018, Volume 13, Issue 4,   Pages 563-570 doi: 10.1007/s11465-018-0487-9

Abstract:

The thermal hydraulic (TH) behavior of coo-lant water is a key factor in the structural integrityassessments on reactor pressure vessels (RPVs) of pressurized water reactors (PWRs) under pressurizedthermal shock (PTS) events, because the TH behavior may affect the loading conditions in the assessmentanalysis with different operator action times, we also performed structural analyses for evaluating thermal-stress

Keywords： structural integrity     reactor pressure vessel     pressurized thermal shock     thermal hydraulic analysis     pressurizedwater reactor     weld residual stress    

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The effect of group structure on calculation of kinetic parameters of in-hospital neutron irradiatormark 1 reactor

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（calculatingTo verify the accuracy of the method, Xi’an Pulsed Reactor is benchmarked and the result is corresponded

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

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The physics scheme design for In-Hospital Neutron Irradiator Mark 1 reactor loaded low enrichment fuel

Jiang Xinbiao,Zhang Wenshou,Gao Jijin,Li Yiguo,Zhou Yongmao

Strategic Study of CAE 2009, Volume 11, Issue 11,   Pages 17-21

Abstract:

The core physics properties of 30 kW In-Hospital Neutron Irradiator-Mark1(IHNI-1) reactor loaded low-enrichment fuel are simulated by using MCNP/4B Monte Carlo code.The results show that the physics scheme of IHNI-1 reactor which possesses some particular characteristicslow-enrichment UO2 fuel, has been discovered in the paper and it will provide theoretic basis for reactorengineering design and neutron beam design for Boron Neutron Capture Therapy in the future.

Keywords： IHNI-1 reactor     boron neutron capture therapy     reactivity    

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Study on the transient behaviours of in-hospital neutron irradiator mark 1 reactor in accident condition

Zhu Lei,Chen Lixin,Jiang Xinbiao,Zhao Zhumin,Zhouyongmao

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 60-63

Abstract: justify;">RELAP5/SCDAP/MOD3.4 is used to simulate and analyze the transient proceeding of in-hospital neutronirradiator mark 1(IHNI-1) reactor in accident condition.Large reactivity insertion accident and lossof coolent of pool accident are calculated and analyzed.The results show that IHNI-1 reactor is characterizedThe negative coolant temperature feedback limits the nuclear power to an stable level and the reactor

Keywords： IHNI-1 reactor     accident condition     transient behaviours     RELAP5    

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Application of WIMS/CITATION in the calculation of IHNI-1 reactor core physics

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

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 38-41

Abstract: justify;">Using WIMS & CITATION program, the neutronic parameters calculating model of in-hospital neutronirradiator mark 1(IHNI-1) reactor is presented in this paper.The power distribution, reactivity worthconsistent with the literature values and the method is appropriate to physical calculation of IHIN-1 reactor

Keywords： IHNI-1 reactor     reactor core     neutron     WIMS     CITATION    

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Research on Technology Directions and Development Roadmap of Nuclear Energy

Du Xiangwan,Ye Qizhen,Xu Mi,Wan Yuanxi,Peng Xianjue,Su Gang,Yang Yong,Gao Xiang and Shi Xueming

Strategic Study of CAE 2018, Volume 20, Issue 3,   Pages 17-24 doi: 10.15302/J-SSCAE-2018.03.003

Abstract: ., thermal neutron reactors, fast neutron reactors and generation IV reactors, and controlled nuclearFirst, China should promote its independent advanced pressurized water reactor to enlarge the nuclearconstruction in 2030 and there will be a harmonious development of pressurized water reactors and fast neutron

Keywords： nuclear energy     thermal neutron reactor     generation IV nuclear system     controlled nuclear fusion     development    

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Analysis of radiation heat transfer and temperature distributions of solar thermochemical reactor for

Bachirou GUENE LOUGOU, Yong SHUAI, Xiang CHEN, Yuan YUAN, Heping TAN, Huang XING

Frontiers in Energy 2017, Volume 11, Issue 4,   Pages 480-492 doi: 10.1007/s11708-017-0506-2

Abstract: This paper investigated radiation heat transfer and temperature distributions of solar thermochemical reactorthermal performance were sufficiently investigated.big temperature difference which increased with an increase in the radiation emissivity due to the thermalthat the temperature drop caused by the boundary radiation heat loss should not be neglected for the thermalperformance analysis of solar thermochemical reactor.

Keywords： solar thermochemical reactor     incident radiation flux     temperature distribution     radiation absorptivity     radiation emissivity     thermal performance analysis    

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Study on neutron cross-section library generated for MCNP in in-hospital neutron irradiator mark 1 reactor

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

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 42-46

Abstract:

A temperature-dependent neutron cross-section library for MCNP in in-hospitalneutron irradiator mark 1 reactor was generated using NJOY software.Accounting for the temperature range for reactor operation, a compact ENDF (ACE) data library was createdlibrary produced in this paper was correct and could be used reliably for physics design at IHNI-1 reactor

Keywords： NJOY     ENDF/B VII.0     MCNP     ACE format    

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CFD Simulation of thermal hydraulic characteristics in a typical upper plenum of RPV

Mingjun WANG, Lianfa WANG, Yingjie WANG, Wenxi TIAN, Jian DENG, Guanghui SU, Suizheng QIU

Frontiers in Energy 2021, Volume 15, Issue 4,   Pages 930-945 doi: 10.1007/s11708-021-0728-1

Abstract: computational fluid dynamics (CFD) study was conducted on the three different types of pressurized water reactorcollected, simplified, and adopted into the BORA facility, which is a 1/5 scale system of the four-loop PWR reactorAfter that, an unsteady calculation to simulate the reactor balance operation at hot full power scenario

Keywords： pressurized water reactor (PWR)     upper plenum     internal structures     temperature distribution     computational    

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The burnup calculation for in-hospital neutron irradiator mark 1 reactor based on coupled code of WIMS

Guo Hewei,Jiang Xinbiao,Zhao Zhumin,Chen Lixin,Zhang Xinyi,Zhou Yongmao

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 64-68

Abstract: Through the calculation results of cells and the comparison of burnup experiments of Xi’an pulsed reactorThe article utilized the coupled code to compute and analyze the burnup of in hospital neutron irradiatormark 1(IHNI-1) reactor at last.

Keywords： IHNI－1 reactor     coupled code     burnup    

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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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Title Author Date Type Operation

Numerical calculation for the equivalent surface source of the thermal neutron duct of in-hospital neutronirradiator mark 1 reactor

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

Journal Article

Analysis of the core thermal-hydraulic characteristics of in-hospital neutron irradiatormark 1 reactor

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

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

Influence evaluation of loading conditions during pressurized thermal shock transients based on thermal-hydraulics

Jinya KATSUYAMA, Shumpei UNO, Tadashi WATANABE, Yinsheng LI

Journal Article

The effect of group structure on calculation of kinetic parameters of in-hospital neutron irradiatormark 1 reactor

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

Journal Article

The physics scheme design for In-Hospital Neutron Irradiator Mark 1 reactor loaded low enrichment fuel

Jiang Xinbiao,Zhang Wenshou,Gao Jijin,Li Yiguo,Zhou Yongmao

Journal Article

Study on the transient behaviours of in-hospital neutron irradiator mark 1 reactor in accident condition

Zhu Lei,Chen Lixin,Jiang Xinbiao,Zhao Zhumin,Zhouyongmao

Journal Article

Application of WIMS/CITATION in the calculation of IHNI-1 reactor core physics

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

Journal Article

Research on Technology Directions and Development Roadmap of Nuclear Energy

Du Xiangwan,Ye Qizhen,Xu Mi,Wan Yuanxi,Peng Xianjue,Su Gang,Yang Yong,Gao Xiang and Shi Xueming

Journal Article

Analysis of radiation heat transfer and temperature distributions of solar thermochemical reactor for

Bachirou GUENE LOUGOU, Yong SHUAI, Xiang CHEN, Yuan YUAN, Heping TAN, Huang XING

Journal Article

Study on neutron cross-section library generated for MCNP in in-hospital neutron irradiator mark 1 reactor

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

Journal Article

CFD Simulation of thermal hydraulic characteristics in a typical upper plenum of RPV

Mingjun WANG, Lianfa WANG, Yingjie WANG, Wenxi TIAN, Jian DENG, Guanghui SU, Suizheng QIU

Journal Article

The burnup calculation for in-hospital neutron irradiator mark 1 reactor based on coupled code of WIMS

Guo Hewei,Jiang Xinbiao,Zhao Zhumin,Chen Lixin,Zhang Xinyi,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