Hesham Shahbunder | Kyoto University (original) (raw)

Papers by Hesham Shahbunder

Kyoto University (京都大学)0048新制・課程博士博士(エネルギー科学)甲第15738号エネ博第229号新制||エネ||50(附属図書館)28283京都大学大学院エネルギー科学... more Kyoto University (京都大学)0048新制・課程博士博士(エネルギー科学)甲第15738号エネ博第229号新制||エネ||50(附属図書館)28283京都大学大学院エネルギー科学研究科エネルギー基礎科学専攻(主査)教授 三澤 毅, 教授 宇根﨑 博信, 教授 中島 健学位規則第4条第1項該

Annals of Nuclear Energy, 2016

Abstract Plutonium (Pu) and minor actinides (MAs) are responsible for the majority of radiotoxici... more Abstract Plutonium (Pu) and minor actinides (MAs) are responsible for the majority of radiotoxicity, heat generation, and proliferation risk of nuclear spent fuel. Accelerator driven system (ADS) reactors can employ Pu and MA for transmutation and power generation within improved safety scheme. Pu and MA can be loaded in ADS reactor core in a variety of distributions. In this study, the effects of uniform and nonuniform distributions of Pu and MA samples loaded within enriched uranium fuel elements inside UT-TRIGA Mark II ADS reactor on neutron flux, neutron spectrum, fission rate, and subcritical multiplication parameters were numerically investigated using Monte Carlo MCNPX transport code. The type of distribution producing higher subcritical multiplication and source efficiency will contribute in minimizing the accelerator current requirements for ADS operation.

International Journal of Nuclear Energy Science and Technology, 2015

The study of the neutronic safety parameters in reactors is very important since it provides a gu... more The study of the neutronic safety parameters in reactors is very important since it provides a guide for future study in reactor design. Also, it is considered as the basic step for reactor waste transmutation. In the present work, some of the basic neutronic parameters that characterised the MINERVE reactor in the different core configurations R1-UO 2 , R2-UO 2 , and R1-MOX, are calculated. The calculations were performed using Monte Carlo N Transport code MCNPX with the recent nuclear data library ENDF/B-VII.1. These parameters are the neutron spectrum, and the total, fast and thermal flux for both radial and axial distributions for the three core configurations. The calculation model is validated by the previous REBUS results. The effect of the neutron flux distribution on the power peaking is discussed.

Annals of Nuclear Energy, 2015

The accelerator driven system (ADS) is a very interesting option to improve the safety of nuclear... more The accelerator driven system (ADS) is a very interesting option to improve the safety of nuclear power reactor and for transmutation of spent fuel. The Texas phase of the reactor-accelerator coupling experiment (RACE), completed in March 2006, demonstrated the feasibility of operating a training research isotopes general atomic (TRIGA) research reactor in a subcritical configuration driven to a significant power by an electron LINAC neutron source (photoneutron). In the present study, the effects of changing the source cylindrical target material, radius, position and the electron beam energy on the final neutron production, fission probability, and the subcritical system multiplication of TRIGA Mark II research reactor, have been numerically investigated. Three target materials are used: Tungsten, Lead and Tungsten-Copper alloy, while varying the target radius from 2 to 8 cm, the source position at three locations, and the beam energy from 10 to 55 MeV. The investigation is based on the numerical calculation of the subcritical multiplication factor and the external source efficiency using Monte Carlo MCNPX code. Through the comparison of the studied cases results, the favorable target material and radius, source position, and beam energy can be obtained.

Annals of Nuclear Energy, 2015

Improving neutronic prediction is a very important step in designing advanced reactors and reacto... more Improving neutronic prediction is a very important step in designing advanced reactors and reactor fuel. There are three main critical reactor facilities of the CEA Cadarache. These reactor facilities are EOLE, MINERVE and MASURCA. The MINERVE reactor is used within the frame work of what is known as OSMOSE project. The OSMOSE program aims at improving neutronic predictions of advanced nuclear fuels through measurements in the MINERVE reactor on samples containing separated actinides. In the present work, the reactivity worth of OSMOSE samples have been calculated using the most recent Monte Carlo N Transport code MCNPX using the most recent nuclear cross-section data library ENDF/B-VII. The calculations are applied to the three core configurations R1-UO 2 , R2-UO 2 and R1-MOX. The present work is performed to improve and/or measure the degree of validity of the previous obtained results of the REBUS and DRAGON codes. Also, our study is extended to include the experimental results for the sake of comparison. The comparison between the previously calculated values using DRAGON and the present results for the effective multiplication factor k eff has a deviation less than ±0.3% for the three core configurations. Furthermore, the results of the reactivity worth of the present work show a good agreement with the experimental results within a relative error less than ±8.2%.

Prompt γ-neutron activation analysis (PGNAA) using the k0 method by employing the 1951.1 keV γ-li... more Prompt γ-neutron activation analysis (PGNAA) using the k0 method by employing the 1951.1 keV γ-line of the 35Cl(n, γ)36Cl thermal neutron reaction as monostandard comparator was described. The method has been applied and evaluated using the anti-Compton prompt γ-ray neutron activation analysis facility using 252Cf neutron source with a neutron flux of 6.16 · 106 n · cm-2 · s-1. A well-type HPGe detector as the main detector surrounded by NaI(Tl) guard detector has been arranged to investigate the performance of the Compton suppression spectrometer using the simplified slow circuit. The properties of neutron flux were determined by MCNP code calculations. In order to determine the efficiency curve of an HPGe detector, the prompt γ-rays from chlorine were used and an exponential curve was fitted. AC-PGNAA method has been used for the determination of high neutron absorbing elements like Cd, Sm and Gd as well as 20 light and heavy elements (Na, Mg, Al, Si, P, K, Ca, Ti, V, Mn, Sc, Fe, ...

Journal of Applied Mathematics and Physics, 2016

In the present work the nuclear structure properties and the backbending phenomena of eveneven is... more In the present work the nuclear structure properties and the backbending phenomena of eveneven isotopes at A ≈ 70 mass region are analyzed using two simultaneous theoretical models based on a simple modified version of the collective model predictions besides an improved version of exponential model with the inclusion of pairing correlation. In general, both models successfully describe the backbending phenomena in that region. From the comparison between the predictions of the two proposed models a firm conclusion is obtained concerning the superiority of the simple improved version of the exponential model in describing the forward and downbending region of the φ-ω 2 plots.

IOP Conference Series: Materials Science and Engineering

Progress in Nuclear Energy

Progress in Nuclear Energy

Arab Journal of Nuclear Sciences and Applications

The evaluation of nuclear data libraries is an important tool to develop nuclear technology. To a... more The evaluation of nuclear data libraries is an important tool to develop nuclear technology. To achieve this goal, OSMOSE program utilized samples that are composed of separated actinides which contain isotopes of americium, plutonium, uranium, and thorium. By inserting those samples in the core configuration of MINERVE reactor, they can be used for improvement of nuclear cross-section databases by cross checking their calculated reactivity worth per each sample using several nuclear data library versions and experimental measurements. The present study investigated the effect of the used nuclear data library on the calculated reactivity of MINERVE reactor with several OSMOSE samples employed in R1-UO2, R1-UO2, and R1-MOX core configurations. The study performed a comparison between the calculated effective multiplication factor using MCNPX code with ENDF/BVI.8 and ENDF/BVII.0 nuclear data libraries. Moreover, the relative difference between the calculated reactivity worth by ENDF/BVI.8 and ENDF/BVII.0 was examined and discussed using available experimental results of the relevant core.

Annals of Nuclear …, Jan 1, 2010

The subcritical multiplication factor k s and the external neutron source efficiency u à are impo... more The subcritical multiplication factor k s and the external neutron source efficiency u à are important parameters in the accelerator-driven system (ADS) performance assessment. The theoretical relation between k s and the effective multiplication factor k eff in a subcritical system is discussed in different cases of subcritical system. On the basis of the theoretical background, the dependence of k s and u à on subcriticality, source position, and energy is numerically investigated using a simple thermal subcritical model.

Annals of Nuclear Energy, Jan 1, 2010

Basic experiments are carried out in the Kyoto University Critical Assembly (KUCA) to study the n... more Basic experiments are carried out in the Kyoto University Critical Assembly (KUCA) to study the nuclear characteristics of the accelerator-driven systems (ADS) and to establish a new neutron source for research. A method for measuring the neutron multiplication in the subcritical system is proposed by utilizing the reaction rate distribution obtained by the optical fiber detector. A comparison between the measured and calculated neutron multiplication shows agreement within a relative difference of 5% in most cases, through introducing certain correction factors.

Annals of Nuclear …, Jan 1, 2010

The neutron multiplication parameters: neutron multiplication M, subcritical multiplication facto... more The neutron multiplication parameters: neutron multiplication M, subcritical multiplication factor k s , external source efficiency φ * , play an important role for numerical assessment and reactor power evaluation of an accelerator-driven system (ADS). Those parameters can be ...

京都大学原子炉実験所学術講演 …, Jan 1, 2009

Kyoto University (京都大学)0048新制・課程博士博士(エネルギー科学)甲第15738号エネ博第229号新制||エネ||50(附属図書館)28283京都大学大学院エネルギー科学... more Kyoto University (京都大学)0048新制・課程博士博士(エネルギー科学)甲第15738号エネ博第229号新制||エネ||50(附属図書館)28283京都大学大学院エネルギー科学研究科エネルギー基礎科学専攻(主査)教授 三澤 毅, 教授 宇根﨑 博信, 教授 中島 健学位規則第4条第1項該

Annals of Nuclear Energy, 2016

Abstract Plutonium (Pu) and minor actinides (MAs) are responsible for the majority of radiotoxici... more Abstract Plutonium (Pu) and minor actinides (MAs) are responsible for the majority of radiotoxicity, heat generation, and proliferation risk of nuclear spent fuel. Accelerator driven system (ADS) reactors can employ Pu and MA for transmutation and power generation within improved safety scheme. Pu and MA can be loaded in ADS reactor core in a variety of distributions. In this study, the effects of uniform and nonuniform distributions of Pu and MA samples loaded within enriched uranium fuel elements inside UT-TRIGA Mark II ADS reactor on neutron flux, neutron spectrum, fission rate, and subcritical multiplication parameters were numerically investigated using Monte Carlo MCNPX transport code. The type of distribution producing higher subcritical multiplication and source efficiency will contribute in minimizing the accelerator current requirements for ADS operation.

International Journal of Nuclear Energy Science and Technology, 2015

The study of the neutronic safety parameters in reactors is very important since it provides a gu... more The study of the neutronic safety parameters in reactors is very important since it provides a guide for future study in reactor design. Also, it is considered as the basic step for reactor waste transmutation. In the present work, some of the basic neutronic parameters that characterised the MINERVE reactor in the different core configurations R1-UO 2 , R2-UO 2 , and R1-MOX, are calculated. The calculations were performed using Monte Carlo N Transport code MCNPX with the recent nuclear data library ENDF/B-VII.1. These parameters are the neutron spectrum, and the total, fast and thermal flux for both radial and axial distributions for the three core configurations. The calculation model is validated by the previous REBUS results. The effect of the neutron flux distribution on the power peaking is discussed.

Annals of Nuclear Energy, 2015

The accelerator driven system (ADS) is a very interesting option to improve the safety of nuclear... more The accelerator driven system (ADS) is a very interesting option to improve the safety of nuclear power reactor and for transmutation of spent fuel. The Texas phase of the reactor-accelerator coupling experiment (RACE), completed in March 2006, demonstrated the feasibility of operating a training research isotopes general atomic (TRIGA) research reactor in a subcritical configuration driven to a significant power by an electron LINAC neutron source (photoneutron). In the present study, the effects of changing the source cylindrical target material, radius, position and the electron beam energy on the final neutron production, fission probability, and the subcritical system multiplication of TRIGA Mark II research reactor, have been numerically investigated. Three target materials are used: Tungsten, Lead and Tungsten-Copper alloy, while varying the target radius from 2 to 8 cm, the source position at three locations, and the beam energy from 10 to 55 MeV. The investigation is based on the numerical calculation of the subcritical multiplication factor and the external source efficiency using Monte Carlo MCNPX code. Through the comparison of the studied cases results, the favorable target material and radius, source position, and beam energy can be obtained.

Annals of Nuclear Energy, 2015

Improving neutronic prediction is a very important step in designing advanced reactors and reacto... more Improving neutronic prediction is a very important step in designing advanced reactors and reactor fuel. There are three main critical reactor facilities of the CEA Cadarache. These reactor facilities are EOLE, MINERVE and MASURCA. The MINERVE reactor is used within the frame work of what is known as OSMOSE project. The OSMOSE program aims at improving neutronic predictions of advanced nuclear fuels through measurements in the MINERVE reactor on samples containing separated actinides. In the present work, the reactivity worth of OSMOSE samples have been calculated using the most recent Monte Carlo N Transport code MCNPX using the most recent nuclear cross-section data library ENDF/B-VII. The calculations are applied to the three core configurations R1-UO 2 , R2-UO 2 and R1-MOX. The present work is performed to improve and/or measure the degree of validity of the previous obtained results of the REBUS and DRAGON codes. Also, our study is extended to include the experimental results for the sake of comparison. The comparison between the previously calculated values using DRAGON and the present results for the effective multiplication factor k eff has a deviation less than ±0.3% for the three core configurations. Furthermore, the results of the reactivity worth of the present work show a good agreement with the experimental results within a relative error less than ±8.2%.

Prompt γ-neutron activation analysis (PGNAA) using the k0 method by employing the 1951.1 keV γ-li... more Prompt γ-neutron activation analysis (PGNAA) using the k0 method by employing the 1951.1 keV γ-line of the 35Cl(n, γ)36Cl thermal neutron reaction as monostandard comparator was described. The method has been applied and evaluated using the anti-Compton prompt γ-ray neutron activation analysis facility using 252Cf neutron source with a neutron flux of 6.16 · 106 n · cm-2 · s-1. A well-type HPGe detector as the main detector surrounded by NaI(Tl) guard detector has been arranged to investigate the performance of the Compton suppression spectrometer using the simplified slow circuit. The properties of neutron flux were determined by MCNP code calculations. In order to determine the efficiency curve of an HPGe detector, the prompt γ-rays from chlorine were used and an exponential curve was fitted. AC-PGNAA method has been used for the determination of high neutron absorbing elements like Cd, Sm and Gd as well as 20 light and heavy elements (Na, Mg, Al, Si, P, K, Ca, Ti, V, Mn, Sc, Fe, ...

Journal of Applied Mathematics and Physics, 2016

In the present work the nuclear structure properties and the backbending phenomena of eveneven is... more In the present work the nuclear structure properties and the backbending phenomena of eveneven isotopes at A ≈ 70 mass region are analyzed using two simultaneous theoretical models based on a simple modified version of the collective model predictions besides an improved version of exponential model with the inclusion of pairing correlation. In general, both models successfully describe the backbending phenomena in that region. From the comparison between the predictions of the two proposed models a firm conclusion is obtained concerning the superiority of the simple improved version of the exponential model in describing the forward and downbending region of the φ-ω 2 plots.

IOP Conference Series: Materials Science and Engineering

Progress in Nuclear Energy

Progress in Nuclear Energy

Arab Journal of Nuclear Sciences and Applications

The evaluation of nuclear data libraries is an important tool to develop nuclear technology. To a... more The evaluation of nuclear data libraries is an important tool to develop nuclear technology. To achieve this goal, OSMOSE program utilized samples that are composed of separated actinides which contain isotopes of americium, plutonium, uranium, and thorium. By inserting those samples in the core configuration of MINERVE reactor, they can be used for improvement of nuclear cross-section databases by cross checking their calculated reactivity worth per each sample using several nuclear data library versions and experimental measurements. The present study investigated the effect of the used nuclear data library on the calculated reactivity of MINERVE reactor with several OSMOSE samples employed in R1-UO2, R1-UO2, and R1-MOX core configurations. The study performed a comparison between the calculated effective multiplication factor using MCNPX code with ENDF/BVI.8 and ENDF/BVII.0 nuclear data libraries. Moreover, the relative difference between the calculated reactivity worth by ENDF/BVI.8 and ENDF/BVII.0 was examined and discussed using available experimental results of the relevant core.

Annals of Nuclear …, Jan 1, 2010

The subcritical multiplication factor k s and the external neutron source efficiency u à are impo... more The subcritical multiplication factor k s and the external neutron source efficiency u à are important parameters in the accelerator-driven system (ADS) performance assessment. The theoretical relation between k s and the effective multiplication factor k eff in a subcritical system is discussed in different cases of subcritical system. On the basis of the theoretical background, the dependence of k s and u à on subcriticality, source position, and energy is numerically investigated using a simple thermal subcritical model.

Annals of Nuclear Energy, Jan 1, 2010

Basic experiments are carried out in the Kyoto University Critical Assembly (KUCA) to study the n... more Basic experiments are carried out in the Kyoto University Critical Assembly (KUCA) to study the nuclear characteristics of the accelerator-driven systems (ADS) and to establish a new neutron source for research. A method for measuring the neutron multiplication in the subcritical system is proposed by utilizing the reaction rate distribution obtained by the optical fiber detector. A comparison between the measured and calculated neutron multiplication shows agreement within a relative difference of 5% in most cases, through introducing certain correction factors.

Annals of Nuclear …, Jan 1, 2010

The neutron multiplication parameters: neutron multiplication M, subcritical multiplication facto... more The neutron multiplication parameters: neutron multiplication M, subcritical multiplication factor k s , external source efficiency φ * , play an important role for numerical assessment and reactor power evaluation of an accelerator-driven system (ADS). Those parameters can be ...

京都大学原子炉実験所学術講演 …, Jan 1, 2009