• 제목/요약/키워드: Nuclear and non-nuclear group

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An empirical study of the risk-benefit perceptions between the nuclear and non-nuclear groups towards the nuclear power plant in Bangladesh

  • Md Shafiqul Islam;Swapnil Roy;Sadia Lena Alfee;Animesh Pal
    • Nuclear Engineering and Technology
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    • 제55권12호
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    • pp.4617-4627
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    • 2023
  • Public perception of benefit over risk is the de facto factor in planning, construction, operation, halting, or phase-out of a nuclear power plant in any country. Even if there are multiple pathways of perceiving risk/benefit among different stakeholders, the perception of nuclear and non-nuclear groups needs to be individually tracked to help understand sectoral influence. Related studies were basically performed between the STEM (Science, Technology, Engineering, and Mathematics) and non-STEM groups. However, there are no such studies between the nuclear and non-nuclear groups. This study investigated the risk-benefit perceptions between the nuclear group (N = 102) and the non-nuclear group (N = 467) using survey data to measure their stake and identify the underlying factors by validating the hypotheses, through descriptive analysis, and structural equation modeling (SEM). Results showed that risk perception is significantly high in the non-nuclear group (as the P-value is > 0.001 to <0.01) while the benefit perception is slightly low in the nuclear group (as the P-value is > 0.01 to <0.05). The non-nuclear group was significantly influenced by risk perception due to a lack of involvement in nuclear activities. Notably, the nuclear group is less interactive in disseminating nuclear energy benefits to the non-nuclear group. Surprisingly, misperceptions and lack of confidence about the benefits of nuclear energy also exist in the nuclear group. The study emphasizes debunking nuclear myths in the nuclear and non-nuclear groups through meaningful interactions and demands effective public awareness-building programs by competent authorities for the growth of the nuclear industry.

RADIATION DOSE TO HUMAN AND NON-HUMAN BIOTA IN THE REPUBLIC OF KOREA RESULTING FROM THE FUKUSHIMA NUCLEAR ACCIDENT

  • Keum, Dong-Kwon;Jun, In;Lim, Kwang-Muk;Choi, Yong-Ho
    • Nuclear Engineering and Technology
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    • 제45권1호
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    • pp.1-12
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    • 2013
  • This paper describes the radiation doses to human and non-human biota in the Republic of Korea, as a result of the Fukushima nuclear accident. By using the measured airborne activity and ground deposition, the effective and thyroid doses of five human age groups (infant, 5 years, 10 years, 15 years and adult) were estimated by the ECOSYS code, and the whole body absorbed dose rate of the eight Korean reference animals and plants (RAPs) was estimated by the K-BIOTA (the Korean computer code to assess the risk of radioactivity to wildlife). The first-year effective and thyroid human doses ranged from 5.7E-5 mSv in the infant group to 2.0E-4 mSv in the 5 years group, and from 5.0E-4 mSv in the infant group to 3.4E-3 mSv in the 5 years group, respectively. The life-time (70 years) effective and thyroid human doses ranged from 1.5E-4 mSv in the infant group to 3.0E-4 mSv in the 5 years group, and from 6.0E-4 mSv in the infant group to 3.5E-3 mSv in the 5 years group, respectively. The estimated maximum whole body absorbed dose rate to the Korean RAPs was 6.7E-7 mGy/d for a snake living in soil (terrestrial biota), and 2.0E-5 mGy/d for freshwater fish (aquatic biota), both of which were far less than the generic dose criteria to protect biota from ionizing radiation. Also, the screening level assessment for ERICA's (Environmental Risks from Ionizing Contaminants: Assessments and management) limiting organisms showed that the risk quotient (RQ) for the estimated maximum soil and water activity was significantly less than unity for both the terrestrial and freshwater organisms. Conclusively, the radiological risk of the radioactivity released into the environment by the Fukushima nuclear accident to the public and the non-human biota in the republic of Korea is considered negligible.

다자간 원자력 협력: 요소와 현안 (Multilateral Nuclear Approaches (MNAs), Factors and Issues Lessons from IAEA Study to Regional Cooperation)

  • Hwang Yong-Soo
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2005년도 춘계 학술대회
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    • pp.56-66
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    • 2005
  • In response to the increasing emphasis being placed on the importance of international cooperation as part of global efforts to cope with growing non proliferation, and security, concerns in the nuclear field, the Director General of the International Atomic Energy Agency (IAEA), Mohamed ElBaradei, appointed an international group of experts to consider possible multilateral approaches to the nuclear fuel cycle. The mandate of the Expert Group was three fold: ${\bullet}$ To identify and provide an analysis of issues and options relevant to multilateral approaches to the front and back ends of the nuclear fuel cycle; ${\bullet}$ To provide an overview of the policy, legal, security, economic, institutional and technological incentives and disincentives for cooperation in multilateral arrangements for the front and back ends of the nuclear fuel cycle; and ${\bullet}$ To provide a brief review of the historical and current experiences and analyses relating to multilateral fuel cycle arrangements relevant to the work of the Expert Group. The overall purpose was to assess MNAs in the framework of a double objective: strengthening the international nuclear non proliferation regime and making the peaceful uses of nuclear energy more economical and attractive. The Group identifies options for MNAs - options in terms of policy, institutional and legal factors - for those parts of the nuclear fuel cycle of greatest sensitivity from the point of view of proliferation risk. It also reflects the Groups deliberations on the corresponding benefits and disadvantages (pros and cons) of the various options and approaches. Although the Expert Group was able to agree to forward the resulting report to the Director General, it is important to note that the report does not reflect agreement by all of the experts on any of the options, nor a consensus assessment of their respective value. It is intended only to present options for MNAs, and to reflect on the range of considerations which could impact on the desirability and feasibility of those options.

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OVERVIEW OF RECENT EFFORTS THROUGH ROSA/LSTF EXPERIMENTS

  • Nakamura, Hideo;Watanabe, Tadashi;Takeda, Takeshi;Maruyama, Yu;Suzuki, Mitsuhiro
    • Nuclear Engineering and Technology
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    • 제41권6호
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    • pp.753-764
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    • 2009
  • JAEA started the LSTF experiments in 1985 for the fourth stage of the ROSA Program (ROSA-IV) for the LWR thermal-hydraulic safety research to identify and investigate the thermal-hydraulic phenomena and to confirm the effectiveness of ECCS during small-break LOCAs and operational transients. The LSTF experiments are underway for the ROSA-V Program and the OECD/NEA ROSA Project that intends to resolve issues in thermal-hydraulic analyses relevant to LWR safety. Six types of the LSTF experiments have been done for both the system integral and separate-effect experiments among international members from 14 countries. Results of four experiments for the ROSA Project are briefly presented with analysis by a best-estimate (BE) code and a computational fluid dynamics (CFD) code to illustrate the capability of the LSTF and codes to simulate the thermal-hydraulic phenomena that may appear during SBLOCAs and transients. The thermal-hydraulic phenomena dealt with are coolant mixing and temperature stratification, water hammer up to high system pressure, natural circulation under high core power condition, and non-condensable gas effect during asymmetric SG depressurization as an AM action.

Finite element analysis of high-density polyethylene pipe in pipe gallery of nuclear power plants

  • Shi, Jianfeng;Hu, Anqi;Yu, Fa;Cui, Ying;Yang, Ruobing;Zheng, Jinyang
    • Nuclear Engineering and Technology
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    • 제53권3호
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    • pp.1004-1012
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    • 2021
  • High density polyethylene (HDPE) pipe has many advantages over metallic pipe, and has been used in non-safety related application for years in some nuclear power plants (NPPs). Recently, HDPE pipe was introduced into safety related applications. The main difference between safety-related and non-safety-related pipes in NPPs is the design method of extra loadings such as gravity, temperature, and earthquake. In this paper, the mechanical behavior of HDPE pipe under various loads in pipe gallery was studied by finite element analysis (FEA). Stress concentrations were found at the fusion regions on inner surface of mitered elbows of HDPE pipe system. The effects of various factors were analyzed, and the influence of various loads on the damage of HDPE pipe system were evaluated. The results of this paper provide a reference for the design of nuclear safety-related Class 3 HDPE pipe. In addition, as the HDPE pipes analyzed in this paper were suspended in pipe gallery, it can also serve as a supplementary reference for current ASME standard on Class 3 HDPE pipe, which only covers the application for buried pipe application.

Research on non-uniform pressure pulsation of the diffuser in a nuclear reactor coolant pump

  • Zhou, Qiang;Li, Hongkun;Pei, Lin;Zhong, Zuowen
    • Nuclear Engineering and Technology
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    • 제53권3호
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    • pp.1020-1028
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    • 2021
  • The nuclear reactor coolant pump transferring heat energy inherently brings with it the unsteady flow and inevitably threatens to the safe operation of the pump unit, especially with the pressure pulsation induced by the rotor-stator interaction. In this paper, the characteristics of pressure pulsation of the diffuser in a nuclear reactor coolant pump were investigated by the numerical simulation with experimental validation. Pressure pulsation signals measured synchronously from sensors mounted on the radial diffuser of a model pump were analyzed via Welch's method. Frequency components induced by the rotor-stator interaction can be revealed by the diameter mode analysis method. The pressure pulsation of the diffuser is dominated by the blade passing frequency and its harmonics, which are free from the effect of flow rate and rotational speed while the corresponding amplitudes are easily affected by different operational conditions and measuring positions. The non-uniformity is much more affected by the rotational speed than the flow rate. This research is helpful for further work to reduce the pressure pulsation for the reactor coolant pump.

Developmental Potential of Interspecies Nuclear Transferred Embryos using Mouse Embryonic Fibroblast In Vitro

  • B.S.Koo;Yoon, J.I.;Son, H.Y.;Kim, M.G.;Park, C.H.;Lee, S.G.;Lee, Y.I.;Lee, C.K.
    • 한국발생생물학회:학술대회논문집
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    • 한국발생생물학회 2003년도 제3회 국제심포지움 및 학술대회
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    • pp.109-109
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    • 2003
  • Even though success in birth of live offspring from nuclear transfer(NT) using somatic cells in many species, detailed information on processes or mechanisms of development are not well known. Cytoplasm of bovine oocyte has been known to support the development of nuclear transferred embryos using nuclear donor cells from different species. Therefore, interspecies NT might be used to find answers of some questions in basic aspect of nuclear transfer In this study, we examined the developmental potential of reconstructed embryos when bovine oocyte as a cytoplasm recipient and mouse embryonic fibroblast as a nuclear donor were used. The nuclear transfer units were aliocated in Group 1 (murine block media and normal media) and Group 2. (bovine block media and normal media). NT units were not blocked at 2-cell stage regardless of types of medium. On mouse media, poor development of interspecies NT units was observed compared to bovine media. However, as NT units cultured in bovine normal medium, embryos developed over 8-cell stage. Further studies performed to increase the developmental rate in condition of antioxidant treatment. Despite low development, bovine-murine interspecies nuclear transferred embryos could develop to blastocysts and they showed that blastocyts rate of antioxidant group was superior to those of non-antioxidant group. Next, we investigated gene expression pattern which is carried out for zygotic activation. The Xist gene is expressed in female mouse embryo after zygotic activation of 4-cell stage. But interspecies nuclear transferred embryos do not express Xist gene at 4-cell stage. As a result, it is suggested that the bovine cytoplasm controls the early preimplantation development in interspecies NT However, the development of later stages might require genomic control from transferred donor nucleus. Therefore, even though the involvement of several other factors such as mitochondrial incompatibility, effective development of embryos produced by interspecies NT requires proper genomic activation of donor nucleus after overcoming the cytoplasmic control of recipient oocytes.

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Epidermal Growth Factor(EGF)와 Transforming Growth Factor-$\alpha$(TGF-$\alpha$)가 돼지 난포란의 체외성숙에 미치는 영향 (Effect of Epidermal Growth Factor and Transforming Growth Factor-$\alpha$ on In Vitro Maturation of Porcine Oocytes)

  • 임정훈;박병권;이규승
    • 한국가축번식학회지
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    • 제21권2호
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    • pp.177-183
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    • 1997
  • The present study examined the effects of epidermal growth factor(EGF) and transforming growth factor-$\alpha$(TGF-$\alpha$) on in vitro maturation of porcine follicular oocytes. Basic medium used TCM-HEPES, and oocytes cultured for 42 hours in vitro. The results obtained are as follows; 1. The nuclear maturation rates of EGF-treated groups(10ng/ml, 75.9% ; 30ng/ml, 69.2% ; 50ng/ml, 67.2% ; 100ng/ml, 71.0%) on the porcine oocytes cultured in medium without pFF in vitro were significantly(P<0.01) higher than those of non-treated group(57.1%). When the oocytes were cultured in media with 10%(v/v) pFF, the nuclear maturation rates of 30ng EGF/ml(77.1%) treated group were significantly(P<0.01) higher than those of non-(59.2%) and EGF-treated groups(10ng/ml, 65.4% ; 50ng/ml, 65.5% ; 100ng/ml, 70.4%). 2. The nuclear maturation rates of 30ng TGF-$\alpha$/ml treated group(71.9%) in media without pFF in vitro were significatnly(P<0.01) higher than those of non-(57.1%) and TGF-$\alpha$ treated groups(10ng/ml, 60.4% ; 50ng/ml, 65.4% ; 100ng/ml, 60.0%). When the oocytes were cultured in media with 10%(v/v) pFF, the nuclear maturation rates of 30 and 50ng TGF-$\alpha$/ml(77.4% and 79.6%) treated groups(10ng/ml, 64.2% ; 100ng/ml, 61.6%). 3. On the effect of EGF(30ng/ml) and/or TGF-$\alpha$(30ng/ml) treated groups in medium without pFF in vitro, the nuclear maturation rates indicated 57.3, 60.4, 75.9 and 79.7% in media with no EGF & TFG-$\alpha$, TGF-$\alpha$ only, EGF only nad EGF+TGF-$\alpha$ treated groups, respectively. The nuclear maturation rates in medium with EGF only or EGF+TGF-$\alpha$ were significantly(P<0.01) higher than those non- and TGF-$\alpha$ treated groups. When the oocytes were cultured in media with 10%(v/v) pFF, the nuclear maturation ratesof EGF+TGF-$\alpha$ treated group(75.9%) were significantly(P<0.01) higher than those of non-(59.2%), TGF-$\alpha$ only (64.2%) and EGF only(69.4%) treated groups.

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타액선 신티그라피 검사에서 타액선 영상과 타액 제거율의 비교 연구 (The Comparison with Salivary Image and Saliva Clearance Rate in Salivary Scintigraphy)

  • 김영빈;신규설;박연경;김건재
    • 핵의학기술
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    • 제13권1호
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    • pp.15-19
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    • 2009
  • Purpose: The aim of study is to find a correlation between Salivary clearance rate using saliva and blood and Secretion rate and Excretion rate using Salivary gland Scan images. Materials and Methods: Salivary Scan and Stimulate clearance of $^{99m}Tc$-pertechnate was performed in 20 patients with moderate function(group 1), 9 patients with severe function glands (group 2), 3 patients with non function (group 3) and normal 6 controls. Salivay clearance rate was compare with Secretion rate and Excretion rate of Salivary glands' ROI. Result: Stimulate salivary clearance of normal controls was 18.4 ml/min, salivary clearance of group 1 was 10.1 ml/min, salivary clearance of group 2 was 10.4 ml/min and salivary clearance of group 3 was 2.3 ml/min. Significant difference was found between normal controls and group 2,3 (p<0.05, p<0.05). Secretion rate and Excretion rate of normal controls was 21.6%, 24.6%, Secretion rate and Excretion rate of group 1 was 17.6%, 24.0%, Secretion rate and Excretion rate of group 2 was 8.8%, 13.9% and Secretion rate and Excretion rate of group 3 was 5.6%, 2.9%. Significant difference was found between normal controls and group 2,3 (p<0.05, p<0.05). Conclusions: Stimulate salivary clearance using saliva and blood and Secretion rate and Excretion rate using Salivary gland Scan images accord well together.

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AN IN-SITU YOUNG'S MODULUS MEASUREMENT TECHNIQUE FOR NUCLEAR POWER PLANTS USING TIME-FREQUENCY ANALYSIS

  • Choi, Young-Chul;Yoon, Doo-Byung;Park, Jin-Ho;Kwon, Hyun-Sang
    • Nuclear Engineering and Technology
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    • 제41권3호
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    • pp.327-334
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    • 2009
  • Elastic wave is one of the most useful tools for non-destructive tests in nuclear power plants. Since the elastic properties are indispensable for analyzing the behaviors of elastic waves, they should be predetermined within an acceptable accuracy. Nuclear power plants are exposed to harsh environmental conditions and hence the structures are degraded. It means that the Young's modulus becomes unreliable and in-situ measurement of Young's modulus is required from an engineering point of view. Young's modulus is estimated from the group velocity of propagating waves. Because the flexural wave of a plate is inherently dispersive, the group velocity is not clearly evaluated in temporal signal analysis. In order to overcome such ambiguity in estimation of group velocity, Wigner-Ville distribution as the time-frequency analysis technique was proposed and utilized. To verify the proposed method, experiments for steel and acryl plates were performed with accelerometers. The results show good estimation of the Young's modulus of two plates.