• Title/Summary/Keyword: Nuclear Education

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Failure analysis of prestressed concrete containment vessels under internal pressure considering thermomechanical coupling

  • Yu-Xiao Wu;Zi-Jian Fei;De-Cheng Feng;Meng-Yan Song
    • Nuclear Engineering and Technology
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    • v.55 no.12
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    • pp.4504-4517
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    • 2023
  • After a loss of coolant accident (LOCA) in the prestressed concrete containment vessels (PCCVs) of nuclear power plants, the coupling of temperature and pressure can significantly affect the mechanical properties of the PCCVs. However, there is no consensus on how this coupling affects the failure mechanism of PCCVs. In this paper, a simplified finite element modeling method is proposed to study the effect of temperature and pressure coupling on PCCVs. The experiment results of a 1:4 scale PCCV model tested at Sandia National Laboratory (SNL) are compared with the results obtained from the proposed modeling approach. Seven working conditions are set up by varying the internal and external temperatures to investigate the failure mechanism of the PCCV model under the coupling effect of temperature and pressure. The results of this paper demonstrate that the finite element model established by the simplified finite element method proposed in this paper is highly consistent with the experimental results. Furthermore, the stress-displacement curve of the PCCV during loading can be divided into four stages, each of which corresponds to the damage to the concrete, steel liner, steel rebar, and prestressing tendon. Finally, the failure mechanism of the PCCV is significantly affected by temperature.

Initiatives in Expanding Horizons of Nuclear Science in Secondary Education: The Critical Support of the IAEA Technical Cooperation Programme

  • Sabharwal, Sunil;Gerardo-Abaya, Jane
    • Journal of Radiation Protection and Research
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    • v.44 no.3
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    • pp.90-96
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    • 2019
  • The contributions of nuclear science and technology in enhancing prosperity and quality of life all over the world and its potential to achieve many important Sustainable Developments Goals (SDGs) of the United Nations are well recognized. It also is now recognized that with fewer students getting attracted to Science, Technology, Engineering and Mathematics (STEM) in general and nuclear science and technology (NST) in particular; hence, there is a vital need to reach out to young students to provide the crucial human resources needed for these endeavours to continue in this highly specialized area. The success of a recently completed IAEA project related to introducing NST during 2012-2016 in secondary schools in the Asia-Pacific region countries encouraged the formulation of a new IAEA TC project RAS0079 entitled "Educating Secondary Students and Science Teachers on Nuclear Science and Technology" for 2018-2021, focusing on enhancing existing educational approaches through training and development opportunities both for teachers and students. The project aims at reaching a million students during the project duration while keeping the depth of learning between teacher and student. The strategy of executing the project, implementation status and its impact so far is presented in this paper.

Study on the irradiation effect of mechanical properties of RPV steels using crystal plasticity model

  • Nie, Junfeng;Liu, Yunpeng;Xie, Qihao;Liu, Zhanli
    • Nuclear Engineering and Technology
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    • v.51 no.2
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    • pp.501-509
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    • 2019
  • In this paper a body-centered cubic(BCC) crystal plasticity model based on microscopic dislocation mechanism is introduced and numerically implemented. The model is coupled with irradiation effect via tracking dislocation loop evolution on each slip system. On the basis of the model, uniaxial tensile tests of unirradiated and irradiated RPV steel(take Chinese A508-3 as an example) at different temperatures are simulated, and the simulation results agree well with the experimental results. Furthermore, crystal plasticity damage is introduced into the model. Then the damage behavior before and after irradiation is studied using the model. The results indicate that the model is an effective tool to study the effect of irradiation and temperature on the mechanical properties and damage behavior.

Adaptive second-order nonsingular terminal sliding mode power-level control for nuclear power plants

  • Hui, Jiuwu;Yuan, Jingqi
    • Nuclear Engineering and Technology
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    • v.54 no.5
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    • pp.1644-1651
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    • 2022
  • This paper focuses on the power-level control of nuclear power plants (NPPs) in the presence of lumped disturbances. An adaptive second-order nonsingular terminal sliding mode control (ASONTSMC) scheme is proposed by resorting to the second-order nonsingular terminal sliding mode. The pre-existing mathematical model of the nuclear reactor system is firstly described based on point-reactor kinetics equations with six delayed neutron groups. Then, a second-order sliding mode control approach is proposed by integrating a proportional-derivative sliding mode (PDSM) manifold with a nonsingular terminal sliding mode (NTSM) manifold. An adaptive mechanism is designed to estimate the unknown upper bound of a lumped uncertain term that is composed of lumped disturbances and system states real-timely. The estimated values are then added to the controller, resulting in the control system capable of compensating the adverse effects of the lumped disturbances efficiently. Since the sign function is contained in the first time derivative of the real control law, the continuous input signal is obtained after integration so that the chattering effects of the conventional sliding mode control are suppressed. The robust stability of the overall control system is demonstrated through Lyapunov stability theory. Finally, the proposed control scheme is validated through simulations and comparisons with a proportional-integral-derivative (PID) controller, a super twisting sliding mode controller (STSMC), and a disturbance observer-based adaptive sliding mode controller (DO-ASMC).

Facilitation of SUMO (Small Ubiquitin-like Modifier) Modification at Tau 340-Lys Residue (a Microtubule-associated Protein) through Phosphorylation at 214-Ser Residue

  • Lee, Eun-Jeoung;Hyun, Sung-Hee;Chun, Jae-Sun;Ahn, Hye-Rim;Kang, Sang-Sun
    • Animal cells and systems
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    • v.11 no.1
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    • pp.39-50
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    • 2007
  • Tau plays a role in numerous neuronal processes, such as vesicle transport, microtubule-plasma membrane interaction and intracellular localization of proteins. SUMO (Small Ubiquitin-like Modifier) modification (SUMOylation) appears to regulate diverse cellular processes including nuclear transport, signal transduction, apoptosis, autophagy, cell cycle control, ubiquitin-dependent degradation, as well as gene transcription. We noticed that putative SUMOylation site is localized at $^{340}K$ of $Tau(^{339}VKSE^{342})$ with the consensus sequence information (${\Phi}KxE$ ; where ${\Phi}$ represents L, I, V or F and x is any amino acid). In this report, we demonstrated that $^{340}K$ of Tau is the SUMOylation site and that a point mutant of Tau S214E (an analog of the phospho $^{214}S$ Tau) promotes its SUMOylation at $^{340}K$ and its nuclear or nuclear vicinity localization, by co-immunoprecipitation and confocal microscopy analysis. Further, we demonstrate that the Tau S214E (neither Tau S214A nor Tau K340R) mutant increases its protein stability. However, the SUMOylation at $^{340}K$ of Tau did not influence cell survival, as determined by FACS analysis. Therefore, our results suggested that the phosphorylation of Tau on $^{214}S$ residue promotes its SUMOylation on $^{340}K$ residue and nuclear vicinity localization, and increases its stability, without influencing cell survival.

BEHAVIORAL CHANGES IN KOREAN ELEMENTARY, MIDDLE, AND HIGH SCHOOL STUDENTS FOLLOWING BASIC EDUCATION IN MEDICAL RADIATION

  • Han, Eun Ok;Kim, Jae Rok;Kye, Suh Youn;Choi, Yoon Seok
    • Journal of Radiation Protection and Research
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    • v.40 no.1
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    • pp.36-45
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    • 2015
  • by providing objective information regarding medical radiation for elementary, middle, and high school students in Korea, who are expected to have a high ripple effect in education, and by analyzing behavioral changes in the selection of medical radiation, this study aimed to deduce the basis for educational intervention. The tools used in the study were a questionnaire, including questions about perception, knowledge, attitude, and behavior toward medical radiation; video and Power-point materials for the lesson; simulated radiation diagnosis selection form; and radiation treatment selection form to find out about behavior. A post-test demonstrated that the objective knowledge about medical radiation of all the students turned out to be significantly higher (p<0.000) after the lesson compared to before the lesson. However, there were no statistically significant behavioral changes. Rather, for high school students, the behavior of selecting medical radiography and treatment was significantly lower (p<0.000) after the lesson. For the more impressionable children in the lower grades, the lesson must not only provide an opportunity to understand and pay attention to diverse viewpoints, but also encourage them to make ethical decisions based on value. Since it can be predicted that attitude or behavioral changes through education or publicity can be expected from adults older than high school students, issues regarding dangers like radiation exposure must be treated as an issue of value judgment predicated on multifaceted considerations.

Mutual Perceptions between Nuclear Plant Employees and General Public on Nuclear Policy Communication Applying the Co-orientation Analysis Model (원자력 관련 정책 커뮤니케이션에 관한 상호인식 연구: 일반 국민과 원전 직원 간의 상호지향성 분석)

  • Kim, Bong Chul;Kim, Ji Hyun;Chung, Woon Kwan
    • Journal of Radiation Industry
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    • v.9 no.1
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    • pp.37-46
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    • 2015
  • This study examines mutual perceptions between general public and nuclear plant employees on understanding nuclear policy communication applying the co-orientation model. The total of 414 responses were analyzed including 211 of the general public and 203 of plant employees. Results indicate that agreement between general public and plant employees is relatively high, in that general public tends to have negative evaluation to nuclear policy communication, but plant employees tends to have positive one. In terms of congruence, general public perceive that plant employees might have more positive evaluation than themselves, and nuclear plant employees perceive that general public might have more negative evaluation than themselves. Finally, in terms of accuracy, general public accurately estimate how nuclear plant employees perceive on policy communication, whereas nuclear plant employees unaccurately estimate how general public perceive on policy communication.

Hydrogen's influence on reduced activation ferritic/martensitic steels' elastic properties: density functional theory combined with experiment

  • Zhu, Sinan;Zhang, Chi;Yang, Zhigang;Wang, Chenchong
    • Nuclear Engineering and Technology
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    • v.49 no.8
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    • pp.1748-1751
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    • 2017
  • Reduced activation ferritic/martensitic (RAFM) steels are widely applied as structural materials in the nuclear industry. To investigate hydrogen's effect on RAFM steels' elastic properties and the mechanism of that effect, a procedure of first principles simulation combined with experiment was designed. Density functional theory models were established to simulate RAFM steels' elastic status before and after hydrogen's insertion. Also, experiment was designed to measure the Young's modulus of RAFM steel samples with and without hydrogen charging. Both simulation and experiment showed that the solubility of hydrogen in RAFM steels would decrease the Young's modulus. The effect of hydrogen on RAFM steels' Young's modulus was more significant in water-quenched steels than it was in tempering steels. This indicated that defects inside martensite, considered to be hydrogen traps, could decrease the cohesive energy of the matrix and lead to a decrease of the Young's modulus after hydrogen insertion.

Radiation induced grain boundary segregation in ferritic/martensitic steels

  • Xia, L.D.;Ji, Y.Z.;Liu, W.B.;Chen, H.;Yang, Z.G.;Zhang, C.;Chen, L.Q.
    • Nuclear Engineering and Technology
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    • v.52 no.1
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    • pp.148-154
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    • 2020
  • The radiation induced segregation of Cr at grain boundaries (GBs) in Ferritic/Martensitic steels was modeled assuming vacancy and interstitialcy diffusion mechanisms. In particular, the dependence of segregation on temperature and grain boundary misorientation angle was analyzed. It is found that Cr enriches at grain boundaries at low temperatures primarily through the interstitialcy mechanism while depletes at high temperatures predominantly through the vacancy mechanism. There is a crossover from Cr enrichment to depletion at an intermediate temperature where the Cr:Fe vacancy and interstitialcy diffusion coefficient ratios intersect. The bell-shape Cr enrichment response is attributed to the decreasing void sinks inside the grains as temperature rises. It is also shown that low angle grain boundaries (LAGBs) and special Σ coincidence-site lattice (CSL) grain boundaries exhibit suppressed radiation induced segregation (RIS) response while high angle grain boundaries (HAGBs) have high RIS segregation. This different behavior is attributed to the variations in dislocation density at different grain boundaries.

MANAGING SPENT NUCLEAR FUEL FROM NONPROLIFERATION, SECURITY AND ENVIRONMENTAL PERSPECTIVES

  • Choi, Jor-Shan
    • Nuclear Engineering and Technology
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    • v.42 no.3
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    • pp.231-236
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    • 2010
  • The growth in global energy demand and the increased recognition of the impacts of carbon dioxide emissions from fossil fuel plants have aroused a renewed interest on nuclear energy. Many countries are looking afresh at building more nuclear power stations to deal with the twin problems of global warming and the need for more generating capacity. Many in the nuclear community are also anticipating a significant growth of new nuclear generation in the coming decades. If there is a nuclear renaissance, will the expansion of nuclear power be compatible with global non-proliferation and security? or will it add to the environmental burden from the large inventory of spent nuclear fuel already produced in existing nuclear power reactors? We learn from past peaceful nuclear activities that significant concerns associated with nuclear proliferation and spent-fuel management have resulted in a decrease in public acceptance for nuclear power in many countries. The terrorist attack in the United States (US) on September 11, 2001 also raised concern for security and worry that nuclear materials may fall into the wrong hands. As we increase the use of nuclear power, we must simultaneously reduce the proliferation, security and environmental risks in managing spent-fuel below where they are today.