System Administrator, Filip Bojko, Giorge Gemisis, James Mitchell, Christopher Parker
Polymer Electrolyte Fuel Cells (PEFCs) are an increasingly significant facet of modern renewable energy and transportation, providing an electrochemical method of energy generation with high power density, thermal properties, and efficiency. PEFCs tend to increase in efficiency as temperature increases but detrimental effects begin to occur, including membrane degradation and dehydration. These effects are unfavourable in the design of optimised fuel cells as they can result in reduced efficiency and lifetime. Current PEFCs are in a state where they are commercially viable but have a very limited temperature operation region (<80°C). This meta-study analysis presents research around expanding the operational temperatures of PEFCs through a parametric analysis of active cell area, phosphonic acid content, and organic/inorganic fillers. This analysis finds an increase in proton conductivity for PEFCs at higher temperature by using phosphonic acid functionalised membranes with maximised degree of phosphonation (up to 1.5 DP). It was also found that using ionic liquid functionalised carbon materials as fillers was an effective strategy to enhance the proton conductivity of PEFCs in a higher temperature environment while also providing increased thermal stability of the membrane. Additionally, higher thermal efficiency and power density may be achieved by increasing temperature and humidity to maximise proton conductivity towards theoretical maxima dictated by the active cell area, which was found to peak at 36 cm2.
{"title":"A parametric analysis on PEFCs for high-temperature applications","authors":"System Administrator, Filip Bojko, Giorge Gemisis, James Mitchell, Christopher Parker","doi":"10.5130/pamr.v7i0.1594","DOIUrl":"https://doi.org/10.5130/pamr.v7i0.1594","url":null,"abstract":"Polymer Electrolyte Fuel Cells (PEFCs) are an increasingly significant facet of modern renewable energy and transportation, providing an electrochemical method of energy generation with high power density, thermal properties, and efficiency. PEFCs tend to increase in efficiency as temperature increases but detrimental effects begin to occur, including membrane degradation and dehydration. These effects are unfavourable in the design of optimised fuel cells as they can result in reduced efficiency and lifetime. Current PEFCs are in a state where they are commercially viable but have a very limited temperature operation region (<80°C). This meta-study analysis presents research around expanding the operational temperatures of PEFCs through a parametric analysis of active cell area, phosphonic acid content, and organic/inorganic fillers. This analysis finds an increase in proton conductivity for PEFCs at higher temperature by using phosphonic acid functionalised membranes with maximised degree of phosphonation (up to 1.5 DP). It was also found that using ionic liquid functionalised carbon materials as fillers was an effective strategy to enhance the proton conductivity of PEFCs in a higher temperature environment while also providing increased thermal stability of the membrane. Additionally, higher thermal efficiency and power density may be achieved by increasing temperature and humidity to maximise proton conductivity towards theoretical maxima dictated by the active cell area, which was found to peak at 36 cm2.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"29 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79105671","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2019-10-22DOI: 10.1504/ijnest.2019.10024814
Nazira Guerrero-Jezzini, A. Nuñez-carrera, A. Vázquez-Rodríguez, Zaira I. Jiménez-Balbuena, P. Ibargüengoytia, L. Sucar
The aim of this paper is the neutronic flux prognosis in a nuclear reactor for faults in the measurement of local power range monitors (LPRMs) in real time using differential probabilistic space-temporal model (DPSTM). The LPRMs provide inputs to the average power range monitor (APRM). The LPRM houses a fission chamber and their associated signal cables. The failure of one or more chains of LPRMs is common during the operational cycle. The circuit averages only LPRM signals that are operational and the output from the averaging circuit for each APRM channel is the route to the process computer. The DPSTM allows a reliable reconstruction in real time signal of those LPRMs that are out of order. The DPSTM is evaluated in terms of predictive accuracy for different time horizons and compared to a time series. The DPSTM based prognosis methodology was developed and validated with real signals of Ringhals stability benchmarks.
{"title":"Differential probabilistic space-temporal model for real-time power prognosis in failures in a nuclear reactor","authors":"Nazira Guerrero-Jezzini, A. Nuñez-carrera, A. Vázquez-Rodríguez, Zaira I. Jiménez-Balbuena, P. Ibargüengoytia, L. Sucar","doi":"10.1504/ijnest.2019.10024814","DOIUrl":"https://doi.org/10.1504/ijnest.2019.10024814","url":null,"abstract":"The aim of this paper is the neutronic flux prognosis in a nuclear reactor for faults in the measurement of local power range monitors (LPRMs) in real time using differential probabilistic space-temporal model (DPSTM). The LPRMs provide inputs to the average power range monitor (APRM). The LPRM houses a fission chamber and their associated signal cables. The failure of one or more chains of LPRMs is common during the operational cycle. The circuit averages only LPRM signals that are operational and the output from the averaging circuit for each APRM channel is the route to the process computer. The DPSTM allows a reliable reconstruction in real time signal of those LPRMs that are out of order. The DPSTM is evaluated in terms of predictive accuracy for different time horizons and compared to a time series. The DPSTM based prognosis methodology was developed and validated with real signals of Ringhals stability benchmarks.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-10-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"48683271","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2019-10-22DOI: 10.1504/ijnest.2019.103238
R. Akbari, D. R. Ochbelagh, A. Gharib
The main purpose of this study is a core neutronic parameter evaluation via the Monte Carlo method, for the SMART reactor which is a certified design Small Modular Reactor (SMR). The SMART neutronic parameters such as axial and radial distributions of neutron fluxes, Power Peaking Factors (PPFs), effective delayed neutron fraction, xenon and samarium effects, burnup calculation and neutron flux energy spectrum have been assessed. Daily load follow operation in soluble-boron-free with control regulating banks is one of the best SMART reactor core advantages. Accordingly, the effects of main regulating bank insertion in SMART core have been evaluated. For developed model verification, some of the neutronic parameters have been compared with the SMART Standard Safety Analysis (SSAR) and show proper match. Then other neutronic parameters of the SMART core as a pioneer SMR have been calculated and evaluated.
{"title":"Small modular reactor core neutronic evaluation via Monte Carlo method","authors":"R. Akbari, D. R. Ochbelagh, A. Gharib","doi":"10.1504/ijnest.2019.103238","DOIUrl":"https://doi.org/10.1504/ijnest.2019.103238","url":null,"abstract":"The main purpose of this study is a core neutronic parameter evaluation via the Monte Carlo method, for the SMART reactor which is a certified design Small Modular Reactor (SMR). The SMART neutronic parameters such as axial and radial distributions of neutron fluxes, Power Peaking Factors (PPFs), effective delayed neutron fraction, xenon and samarium effects, burnup calculation and neutron flux energy spectrum have been assessed. Daily load follow operation in soluble-boron-free with control regulating banks is one of the best SMART reactor core advantages. Accordingly, the effects of main regulating bank insertion in SMART core have been evaluated. For developed model verification, some of the neutronic parameters have been compared with the SMART Standard Safety Analysis (SSAR) and show proper match. Then other neutronic parameters of the SMART core as a pioneer SMR have been calculated and evaluated.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-10-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1504/ijnest.2019.103238","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47807425","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2019-10-22DOI: 10.1504/ijnest.2019.103237
F. A. Majeed, F. M. Hussain, Yousif A. Abdul-Hussien
The effects of coupled-channels in heavy-ion fusion reaction for the system 40Ca + 192Os, 40Ca + 194Pt, and 48Ca + 197Au are discussed. The fusion cross-section σfus, the fusion barrier distribution Dfus and fusion probability Pfus are also discussed. The fusion barrier distribution is calculated using numerical three point, five point and Wong methods. Full quantum coupled-channels calculations are performed using CCFULL code with all order coupling to compare and with available experimental data. The χ² values for the case of no-coupling and coupling effects included shows clearly that the present calculations are in agreement with the experimental.
{"title":"Enhanced calculations of fusion barrier distribution for heavy-ion fusion reactions using Wong formula","authors":"F. A. Majeed, F. M. Hussain, Yousif A. Abdul-Hussien","doi":"10.1504/ijnest.2019.103237","DOIUrl":"https://doi.org/10.1504/ijnest.2019.103237","url":null,"abstract":"The effects of coupled-channels in heavy-ion fusion reaction for the system 40Ca + 192Os, 40Ca + 194Pt, and 48Ca + 197Au are discussed. The fusion cross-section σfus, the fusion barrier distribution Dfus and fusion probability Pfus are also discussed. The fusion barrier distribution is calculated using numerical three point, five point and Wong methods. Full quantum coupled-channels calculations are performed using CCFULL code with all order coupling to compare and with available experimental data. The χ² values for the case of no-coupling and coupling effects included shows clearly that the present calculations are in agreement with the experimental.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-10-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1504/ijnest.2019.103237","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45515998","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2019-10-22DOI: 10.1504/ijnest.2019.10024819
K. S. Jassim, Aqeel I. Faris
The nuclear structure of 58,62Ni nuclei has been calculated using F5PVH as effective interaction for 1f5/2 2p3/2 2p1/2 shell model wave functions. Skyrme-Hartree Fock (SKX), Harmonic Oscillator (HO) and Woods-Saxon (WS) potentials were used to calculate the single particle wave function. The core-polarisation effects have been adopted using the shape of Tassie model. The level schemes are compared with the experimental data up to 3.42 MeV and 4.018 MeV for 58Ni and 62Ni, respectively. In this study, very good agreements are obtained for all nuclei. Results from C2 form factor and Charge Density Distribution (CDD) calculations give good agreement with the experimental data with no adjustable parameters.
{"title":"Study of nuclear structure of 58,62Ni isotopes using the F5PVH effective interaction","authors":"K. S. Jassim, Aqeel I. Faris","doi":"10.1504/ijnest.2019.10024819","DOIUrl":"https://doi.org/10.1504/ijnest.2019.10024819","url":null,"abstract":"The nuclear structure of 58,62Ni nuclei has been calculated using F5PVH as effective interaction for 1f5/2 2p3/2 2p1/2 shell model wave functions. Skyrme-Hartree Fock (SKX), Harmonic Oscillator (HO) and Woods-Saxon (WS) potentials were used to calculate the single particle wave function. The core-polarisation effects have been adopted using the shape of Tassie model. The level schemes are compared with the experimental data up to 3.42 MeV and 4.018 MeV for 58Ni and 62Ni, respectively. In this study, very good agreements are obtained for all nuclei. Results from C2 form factor and Charge Density Distribution (CDD) calculations give good agreement with the experimental data with no adjustable parameters.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-10-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47239460","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2019-10-22DOI: 10.1504/ijnest.2019.103240
Z. Tabadar, G. Ansarifar, K. Hadad, M. Jabbari
Global core calculations use the diffusion equation to predict theoretically the nuclear reactor behaviour. However, this equation is not valid in strong absorbing media where the neutron spectrum is a rapidly varying function of the position, such as control rods or burnable poisons. In this paper, to overcome this misleading, the Monte Carlo simulation has been performed and the VVER-1000 reactor core in the MCL (Reactor Minimally Controlled Power Level) condition is modelled using the MCNPX code to calculate the reactivity worth of the control rod groups. The calculations in this model are divided into four steps. At first, the integral and differential worth are calculated for control groups 8, 9 and 10 with 50% overlapping and shadowing effect is considered. And in three other steps the integral and differential reactivity worths of control groups 8, 9 and 10 are calculated separately (without overlapping). In each step, the core is maintained critical by variation of the boron concentration. In these processes, the boric acid coefficient is achieved while the core is critical. The results are compared with experimental values and are in good agreement with them.
{"title":"Reactivity worth calculation for control rods groups of the VVER-1000 nuclear reactor core considering shadowing effect using Monte Carlo method","authors":"Z. Tabadar, G. Ansarifar, K. Hadad, M. Jabbari","doi":"10.1504/ijnest.2019.103240","DOIUrl":"https://doi.org/10.1504/ijnest.2019.103240","url":null,"abstract":"Global core calculations use the diffusion equation to predict theoretically the nuclear reactor behaviour. However, this equation is not valid in strong absorbing media where the neutron spectrum is a rapidly varying function of the position, such as control rods or burnable poisons. In this paper, to overcome this misleading, the Monte Carlo simulation has been performed and the VVER-1000 reactor core in the MCL (Reactor Minimally Controlled Power Level) condition is modelled using the MCNPX code to calculate the reactivity worth of the control rod groups. The calculations in this model are divided into four steps. At first, the integral and differential worth are calculated for control groups 8, 9 and 10 with 50% overlapping and shadowing effect is considered. And in three other steps the integral and differential reactivity worths of control groups 8, 9 and 10 are calculated separately (without overlapping). In each step, the core is maintained critical by variation of the boron concentration. In these processes, the boric acid coefficient is achieved while the core is critical. The results are compared with experimental values and are in good agreement with them.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-10-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1504/ijnest.2019.103240","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45293175","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2019-10-20DOI: 10.7538/YZK.2019.53.10.1729
Weiping Liu, Zhihong Li, Jianjun He, Xiaodong Tang, G. Lian, B. Guo, Jun Su, Yunju Li, B. Cui, Liangting Sun, Qi Wu, Z. An, Qinghao Chen, Xiongjun Chen, Yangping Chen, Zhijun Chen, X. Du, C. Fu, Lin Gan, Guozhu He, A. Heger, S. Hou, Hanxiong Huang, N. Huang, B. Jia, Liyang Jiang, S. Kubono, Jianmin Li, Kuo-Ang Li, Tao Li, M. Lugaro, X. Luo, Shaobo Ma, D. Mei, Y. Qian, J. Qin, Jie Ren, Wanpeng Tan, I. Tanihata, Peng Wang, Shuo Wang, Y. Wang, Shi-wei Xu, Shengquan Yan, Litao Yang, Xiangqing Yu, Qianyu Yue, S. Zeng, Huanyu Zhang, Hui Zhang, Li-yong Zhang, N. Zhang, Qi Zhang, Tao Zhang, Xiaodong Fang, Xiao Zhang, X. Zhang, Zhimin Zhang, Wei Zhao, Zhuo Zhao, Chao Zhou, Yunhua Chen, Ningchun Qi, Shi-ying Wu, Xuyuan Guo, Jifang Zhou, Sheng-Dong He, J. Ning, Jianfeng Yue
{"title":"锦屏深地核天体物理实验(JUNA)进展","authors":"Weiping Liu, Zhihong Li, Jianjun He, Xiaodong Tang, G. Lian, B. Guo, Jun Su, Yunju Li, B. Cui, Liangting Sun, Qi Wu, Z. An, Qinghao Chen, Xiongjun Chen, Yangping Chen, Zhijun Chen, X. Du, C. Fu, Lin Gan, Guozhu He, A. Heger, S. Hou, Hanxiong Huang, N. Huang, B. Jia, Liyang Jiang, S. Kubono, Jianmin Li, Kuo-Ang Li, Tao Li, M. Lugaro, X. Luo, Shaobo Ma, D. Mei, Y. Qian, J. Qin, Jie Ren, Wanpeng Tan, I. Tanihata, Peng Wang, Shuo Wang, Y. Wang, Shi-wei Xu, Shengquan Yan, Litao Yang, Xiangqing Yu, Qianyu Yue, S. Zeng, Huanyu Zhang, Hui Zhang, Li-yong Zhang, N. Zhang, Qi Zhang, Tao Zhang, Xiaodong Fang, Xiao Zhang, X. Zhang, Zhimin Zhang, Wei Zhao, Zhuo Zhao, Chao Zhou, Yunhua Chen, Ningchun Qi, Shi-ying Wu, Xuyuan Guo, Jifang Zhou, Sheng-Dong He, J. Ning, Jianfeng Yue","doi":"10.7538/YZK.2019.53.10.1729","DOIUrl":"https://doi.org/10.7538/YZK.2019.53.10.1729","url":null,"abstract":"","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"42 1","pages":"1729-1741"},"PeriodicalIF":0.0,"publicationDate":"2019-10-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85836190","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2019-07-08DOI: 10.1504/IJNEST.2019.10022532
Amit Bindra, H. M. Mittal
The systematic dependence of Grodzins product E(2+1)*B(E2)↑ on the nucleonic promiscuity factor, i.e. P-factor = (Np Nn)/(Np + Nn), is studied in the Z = 50−82, N = 82−126 major shell space. The anomalous behaviour is noticed at N = 88−90, where the Grodzins product fails to maintain the constancy corresponding to P ≥ 4. The nuclei for P ≥ 4 region are recognised for enhanced collectivity, where p−n interaction is of the order of ~250 keV and it begins to dominate the pairing interaction of ~1 MeV. The P-factor also resolves the anomaly of not obtaining smooth universal Casten curve in Np Nn scheme. The approximate constancy in Grodzins product is noticed for well deformed nuclear region. The relation between Grodzins product and P-factor has been studied for the first time.
{"title":"Study of Grodzins product in collective nuclear structure","authors":"Amit Bindra, H. M. Mittal","doi":"10.1504/IJNEST.2019.10022532","DOIUrl":"https://doi.org/10.1504/IJNEST.2019.10022532","url":null,"abstract":"The systematic dependence of Grodzins product E(2+1)*B(E2)↑ on the nucleonic promiscuity factor, i.e. P-factor = (Np Nn)/(Np + Nn), is studied in the Z = 50−82, N = 82−126 major shell space. The anomalous behaviour is noticed at N = 88−90, where the Grodzins product fails to maintain the constancy corresponding to P ≥ 4. The nuclei for P ≥ 4 region are recognised for enhanced collectivity, where p−n interaction is of the order of ~250 keV and it begins to dominate the pairing interaction of ~1 MeV. The P-factor also resolves the anomaly of not obtaining smooth universal Casten curve in Np Nn scheme. The approximate constancy in Grodzins product is noticed for well deformed nuclear region. The relation between Grodzins product and P-factor has been studied for the first time.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46918964","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2019-07-08DOI: 10.1504/IJNEST.2019.10022540
A. Galahom
This article discusses the effect of different Integral Burnable Absorber numbers (IBAs) on the neutronic characteristics of a Pressurised Water Reactor (PWR) to provide a suitable safety level. MCNPX code version 2.6 was used to design a three dimensional model for PWR assembly. The designed model has been validated by comparing the output values of the infinity multiplication factor (Kinf) with a previously published value. The designed MCNPX model was used to analyse the radial distribution of thermal neutrons and the power through PWR assembly with and without IBA. Due to the high absorption cross-section of gadolinium, it has been used as a burnable absorber material in the IBA rods. The gadolinium isotopes suppressed the power in the regions where they were distributed. The existence of IBA rods has a large effect on the Kinf. This effect decreases gradually with burnup due to the degradation of gadolinium. The gadolinium isotopes degradation was analysed with burnup. Different numbers of IBA rods were investigated to optimise the suitable number that can be used in the PWR assembly. The reactivity has been investigated at different numbers of IBAs. The gadolinium effect on the concentration of 135Xe and 149Sm resulting from the fission process was analysed.
{"title":"Searching for the optimum number of integral burnable absorber rods used in PWR assembly","authors":"A. Galahom","doi":"10.1504/IJNEST.2019.10022540","DOIUrl":"https://doi.org/10.1504/IJNEST.2019.10022540","url":null,"abstract":"This article discusses the effect of different Integral Burnable Absorber numbers (IBAs) on the neutronic characteristics of a Pressurised Water Reactor (PWR) to provide a suitable safety level. MCNPX code version 2.6 was used to design a three dimensional model for PWR assembly. The designed model has been validated by comparing the output values of the infinity multiplication factor (Kinf) with a previously published value. The designed MCNPX model was used to analyse the radial distribution of thermal neutrons and the power through PWR assembly with and without IBA. Due to the high absorption cross-section of gadolinium, it has been used as a burnable absorber material in the IBA rods. The gadolinium isotopes suppressed the power in the regions where they were distributed. The existence of IBA rods has a large effect on the Kinf. This effect decreases gradually with burnup due to the degradation of gadolinium. The gadolinium isotopes degradation was analysed with burnup. Different numbers of IBA rods were investigated to optimise the suitable number that can be used in the PWR assembly. The reactivity has been investigated at different numbers of IBAs. The gadolinium effect on the concentration of 135Xe and 149Sm resulting from the fission process was analysed.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"44003096","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2019-07-08DOI: 10.1504/IJNEST.2019.10022536
Firas M. Ali, H. Hadi
The phenomenological formula of Qα-value (α-decay energies) for heavy and super heavy nuclei was presented using modification of a Liquid Drop Model (LDM) which is composed of effects of volume energy, Coulomb energy, symmetry energy and binding energy of α-particle. It can be employed to validate the experimental observation and calculation to a large extent of heaviest nuclei with high accuracy for root mean square deviation (0.54) and standard deviation (0.38) are which useful for future experiments. In comparison of computed Qα-value with experimental data an excellent agreement has been obtained. These results indicate the acceptability of the approach. Furthermore the theoretical quantity (S) has been proposed in order to predict the Qα-value of α-particles. This is done by partial differentiation of both sides of Qα-value with respect to the mass number (A), this quantity describes the Qα-value dependence of (A), and these results show agreement between S and Qα-values behaviours. The separation energy difference (Sp-Sn) increases with increasing mass number (A), on the whole.
{"title":"Improving of phenomenological formula for nuclear energy decay (Qα-value) of heavy and super heavy nuclei","authors":"Firas M. Ali, H. Hadi","doi":"10.1504/IJNEST.2019.10022536","DOIUrl":"https://doi.org/10.1504/IJNEST.2019.10022536","url":null,"abstract":"The phenomenological formula of Qα-value (α-decay energies) for heavy and super heavy nuclei was presented using modification of a Liquid Drop Model (LDM) which is composed of effects of volume energy, Coulomb energy, symmetry energy and binding energy of α-particle. It can be employed to validate the experimental observation and calculation to a large extent of heaviest nuclei with high accuracy for root mean square deviation (0.54) and standard deviation (0.38) are which useful for future experiments. In comparison of computed Qα-value with experimental data an excellent agreement has been obtained. These results indicate the acceptability of the approach. Furthermore the theoretical quantity (S) has been proposed in order to predict the Qα-value of α-particles. This is done by partial differentiation of both sides of Qα-value with respect to the mass number (A), this quantity describes the Qα-value dependence of (A), and these results show agreement between S and Qα-values behaviours. The separation energy difference (Sp-Sn) increases with increasing mass number (A), on the whole.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47065262","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
京公网安备 11010802042870号
京ICP备2023020795号-1
扫码关注我们
求助内容：
应助结果提醒方式：