Chromosome analysis of nuclear power plant workers using fluorescence in situ hybridization and Giemsa assay

International Nuclear Information System (INIS)

Hristova, Rositsa; Hadjidekova, Valeria; Grigorova, Mira; Nikolova, Teodora; Bulanova, Minka; Popova, Ljubomira; Staynova, Albena; Benova, Donka

2013-01-01

The aim of this study was to evaluate the genotoxic effects of ionizing radiation in vivo in exposed Bulgarian nuclear power plant workers by using classical cytogenetic and molecular cytogenetic analyses of peripheral lymphocytes. Chromosome analysis using fluorescence in situ hybrydization (FISH) and Giemsa techniques was undertaken on 63 workers and 45 administrative staff controls from the Bulgarian Nuclear Power Plant. Using the Giemsa method, the frequencies of cells studied with chromosome aberrations, dicentrics plus rings and chromosome fragments in the radiation workers were significantly higher compared with the control group (P=0.044, P=0.014, and P=0.033, respectively). A significant association between frequencies of dicentrics plus rings and accumulated doses was registered (P<0.01). In the present study, a FISH cocktail of whole chromosome paints for chromosomes 1, 4 and 11 was used. A significant association between frequency of translocations and accumulated doses was also observed (P<0.001). Within the control group, a correlation was found between age and the spontaneous frequency of translocations. No correlation was found between smoking status and frequency of translocations. When compared with the control group, workers with accumulated doses up to 100 mSv showed no increase in genome translocation frequency, whereas workers with accumulated doses from 101 to 200 mSv showed a statistically significant doubling of genome translocation frequency (P=0.009). Thus, in cases of chronic exposure and for purposes of retrospective dosimetry, the genome frequency of translocations is a more useful marker for evaluation of genotoxic effects than dicentric frequency. (author)

Risk perception of workers at nuclear power plants from Angra dos Reis, Rio de Janeiro State: preliminary study of a reality on health

International Nuclear Information System (INIS)

Scliar, Claudio; Vasconcelos, Ana S.F.; Rodrigues, Anacely S.; Santos, Gloria R.R.; Albuquerque, Patricia O.; Carvalho, Sirlene L.A.; Oliveira, Simone

1999-01-01

The present paper analyses some social and occupational parameters that may have an influence on the risk perception levels of the workers in Brazilian Nuclear Power pLants, emphasizing possible relationship between the specificity of job tasks/literacy and risk perception. This study was based on two findings from the scientific literature: risk perception increases proportionally with literacy; risk perception decreases proportionally with the specificity of job tasks. The results of this pilot study indicates that risk perception levels of the workers in Brazilian Nuclear Power Plants increases proportionally with the literacy and specificity of their job tasks, contrasting with the american and european profiles. These results appears as a singular reality of those workers and the possibility of a new regard over the management and decision making process in the Brazilian Nuclear Power Plants. (author)

Dose-reduction techniques for high-dose worker groups in nuclear power plants

International Nuclear Information System (INIS)

Khan, T.A.; Baum, J.W.; Dionne, B.J.

1991-03-01

This report summarizes the main findings of a study of the extent of radiation dose received by special work groups in the nuclear power industry. Work groups which chronically get large doses were investigated, using information provided by the industry. The tasks that give high doses to these work groups were examined and techniques described that were found to be particularly successful in reducing dose. Quantitative information on the extent of radiation doses to various work groups shows that significant numbers of workers in several critical groups receive doses greater than 1 and even 2 rem per year, particularly contract personnel and workers at BWR-type plants. The number of radiation workers whose lifetime dose is greater than their age is much less. Although the techniques presented would go some way in reducing dose, it is likely that a sizeable reduction to the high-dose work groups may require development of new dose-reduction techniques as well as major changes in procedures. 10 refs., 26 tabs

Images of nuclear power plants

International Nuclear Information System (INIS)

Hashiguchi, Katsuhisa; Misumi, Jyuji; Yamada, Akira; Sakurai, Yukihiro; Seki, Fumiyasu; Shinohara, Hirofumi; Misumi, Emiko; Kinjou, Akira; Kubo, Tomonori.

1995-01-01

This study was conducted to check and see, using Hayashi's quantification method III, whether or not the respondents differed in their images of a nuclear power plant, depending on their demographic variables particularly occupations. In our simple tabulation, we compared subject groups of nuclear power plant employees with general citizens, nurses and students in terms of their images of a nuclear power plant. The results were that while the nuclear power plant employees were high in their evaluations of facts about a nuclear power plant and in their positive images of a nuclear power plant, general citizens, nurses and students were overwhelmingly high in their negative images of a nuclear power plant. In our analysis on category score by means of the quantification method III, the first correlation axis was the dimension of 'safety'-'danger' and the second correlation axis was the dimension of 'subjectivity'-'objectivity', and that the first quadrant was the area of 'safety-subjectivity', the second quadrant was the area of 'danger-subjectivity', the third quadrant as the area of 'danger-objectivity', and the forth quadrant was the area of 'safety-objectivity'. In our analysis of sample score, 16 occupation groups was compared. As a result, it was found that the 16 occupation groups' images of a nuclear power plant were, in the order of favorableness, (1) section chiefs in charge, maintenance subsection chiefs, maintenance foremen, (2) field leaders from subcontractors, (3) maintenance section members, operation section members, (4) employees of those subcontractors, (5) general citizens, nurses and students. On the 'safety-danger' dimension, nuclear power plant workers on the one hand and general citizens, nurses and students on the other were clearly divided in terms of their images of a nuclear power plant. Nuclear power plant workers were concentrated in the area of 'safety' and general citizens, nurses and students in the area of 'danger'. (J.P.N.)

Chromosome aberrations in workers of ignalina nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Griciene, B.; Januskeviciute, I.; Mierauskiene, J.; Slapsyte, G. [Vilnius Univ. (Lithuania)

2006-07-01

Full text of publication follows: The Ignalina Nuclear Power Plant (I.N.P.P.) workers and outside workers including visitors constitute the largest occupational group exposed to low doses of ionizing radiation in Lithuania. In 2004, the annual collective dose to these workers (4392 persons) was 6,83 man Sv. The maximum annual individual dose of I.N.P.P. workers was 19,16 mSv, and of outside workers was 29,41 mSv. However, according to calculations performed by the Lithuanian Radiation Protection Centre, the decommissioning of I.N.P.P. (the I.N.P.P. is to be shut down by 2009) will result in collective dose of 35 man Sv. Therefore, a special attention should be given to implementation of radiation protection programme. The importance of cytogenetic studies in the medical surveillance of radiation-exposed persons is generally acknowledged. The aim of the present study was to analyse chromosome aberration frequencies in lymphocytes of I.N.P.P. workers. The blood sampling of 27 male workers was performed in October 2004, after planned outage of I.N.P.P.. It was estimated that outages of I.N.P.P. Units contributed 84% to all annual occupational collective dose. Average cumulative dose of 18 workers was 290,7 mSv (group A), and of 9 workers - 71,7 mSv (group B). The mean annual doses averaged over the three-year-period were 15,2 mSv and 0,76 mSv, respectively. None of the exposed workers had ever exceeded the permissible dose limit. The average age of group A workers was 45,2 years, and group B 48,2 years. A questionnaire form with details on age, occupational history, smoking habit and alcohol intake, medication, history of recent illness was completed for each person at the time of blood collection. 64 non-exposed male donors approximately matched by age were used as controls (group C). Heparinized venous blood samples were taken and cultures were initiated within 24 h according to the standard procedures. At least 500 first cycle metaphases were analysed from each

Chromosome aberrations in workers of ignalina nuclear power plant

International Nuclear Information System (INIS)

Griciene, B.; Januskeviciute, I.; Mierauskiene, J.; Slapsyte, G.

2006-01-01

Full text of publication follows: The Ignalina Nuclear Power Plant (I.N.P.P.) workers and outside workers including visitors constitute the largest occupational group exposed to low doses of ionizing radiation in Lithuania. In 2004, the annual collective dose to these workers (4392 persons) was 6,83 man Sv. The maximum annual individual dose of I.N.P.P. workers was 19,16 mSv, and of outside workers was 29,41 mSv. However, according to calculations performed by the Lithuanian Radiation Protection Centre, the decommissioning of I.N.P.P. (the I.N.P.P. is to be shut down by 2009) will result in collective dose of 35 man Sv. Therefore, a special attention should be given to implementation of radiation protection programme. The importance of cytogenetic studies in the medical surveillance of radiation-exposed persons is generally acknowledged. The aim of the present study was to analyse chromosome aberration frequencies in lymphocytes of I.N.P.P. workers. The blood sampling of 27 male workers was performed in October 2004, after planned outage of I.N.P.P.. It was estimated that outages of I.N.P.P. Units contributed 84% to all annual occupational collective dose. Average cumulative dose of 18 workers was 290,7 mSv (group A), and of 9 workers - 71,7 mSv (group B). The mean annual doses averaged over the three-year-period were 15,2 mSv and 0,76 mSv, respectively. None of the exposed workers had ever exceeded the permissible dose limit. The average age of group A workers was 45,2 years, and group B 48,2 years. A questionnaire form with details on age, occupational history, smoking habit and alcohol intake, medication, history of recent illness was completed for each person at the time of blood collection. 64 non-exposed male donors approximately matched by age were used as controls (group C). Heparinized venous blood samples were taken and cultures were initiated within 24 h according to the standard procedures. At least 500 first cycle metaphases were analysed from each

Associations between disaster exposures, peritraumatic distress, and posttraumatic stress responses in Fukushima nuclear plant workers following the 2011 nuclear accident: the Fukushima NEWS Project study.

Directory of Open Access Journals (Sweden)

Jun Shigemura

Full Text Available BACKGROUND: The 2011 Fukushima Daiichi Nuclear Power Plant accident was the worst nuclear disaster since Chernobyl. The nearby Daini plant also experienced substantial damage but remained intact. Workers for the both plants experienced multiple stressors as disaster victims and workers, as well as the criticism from the public due to their company's post-disaster management. Little is known about the psychological pathway mechanism from nuclear disaster exposures, distress during and immediately after the event (peritraumatic distress; PD, to posttraumatic stress responses (PTSR. METHODS: A self-report questionnaire was administered to 1,411 plant employees (Daiichi, n = 831; Daini, n = 580 2-3 months post-disaster (total response rate: 80.2%. The socio-demographic characteristics and disaster-related experiences were assessed as independent variables. PD and PTSR were measured by the Japanese versions of Peritraumatic Distress Inventory and the Impact of Event Scale-Revised, respectively. The analysis was conducted separately for the two groups. Bivariate regression analyses were performed to assess the relationships between independent variables, PD, and PTSR. Significant variables were subsequently entered in the multiple regression analyses to explore the pathway mechanism for development of PTSR. RESULTS: For both groups, PTSR highly associated with PD (Daiichi: adjusted β, 0.66; p<0.001; vs. Daini: adjusted β, 0.67; p<0.001. PTSR also associated with discrimination/slurs experience (Daiichi: 0.11; p<0.001; vs. Daini, 0.09; p = 0.005 and presence of preexisting illness(es (Daiichi: 0.07; p = 0.005; vs. Daini: 0.15; p<.0001. Other disaster-related variables were likely to be associated with PD than PTSR. CONCLUSION: Among the Fukushima nuclear plant workers, disaster exposures associated with PD. PTSR was highly affected by PD along with discrimination/slurs experience.

The status of contractors workers operating in US nuclear power plants

International Nuclear Information System (INIS)

Lochard, J.

1985-01-01

The status of contractors operating in PWRs in the United States is described. The statistics concerning the trends of both the individual and collective exposures of these workers were analysed as well as their main demographic and sociological features. The data relative to the particular group of ''transient'' workers, i.e. those operating in several different power plants during the same year were also examined. The results presented show that the dosimetric and sociological profiles of contractors' workers, in US power plants, do not differ fundamentally from that of permanent workers [fr

Development of Work Verification System for Cooperation between MCR Operators and Field Workers in Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Seung Min; Seong, Poong Hyun; Lee, Hyun Chul

2014-01-01

In this work, as an application of digital devices to NPPs, a cooperation support system to aid communication between MCR operators and field workers in Nuclear Power Plants (NPPs), NUclear COoperation Support and MObile document System (Nu-COSMOS), is suggested. It is not easy for MCR operators to estimate whether field workers conduct their work correctly because MCR operators cannot monitor field workers at a real time, and records on paper procedure written by field workers do not contain the detailed information about work process and results. Thus, for safety operation without any events induced by misunderstand and miscommunication between MCR operators and field workers, the Nu-COSMOS is developed and it will be useful from the supporting cooperation point of view. To support the cooperation between MCR operators and field workers in NPPs, the cooperation support and mobile documentation system Nu-COSMOS is suggested in this work. To improve usability and applicability of the suggested system, the results of using existed digital device based support systems were analyzed. Through the analysis, the disincentive elements of using digital device-based developments and the recommendations for developing new mobile based system were derived. Based on derived recommendations, two sub systems, the mobile device based in-formation storing system and the large screen based information sharing system were suggested. The usability of the suggested system will be conducted by a survey with questionnaires. Field workers and operators, and nuclear-related person who had experiences as an operator, graduate students affiliated in nuclear engineering department will use and test the functions of the suggested system. It is expected that the mobile based information storing system can reduce the field workers' work load and enhance the understanding of MCR operators about field operators work process by monitoring all work results and work processes stored in devices

Development of Work Verification System for Cooperation between MCR Operators and Field Workers in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Seung Min; Seong, Poong Hyun [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Lee, Hyun Chul [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

In this work, as an application of digital devices to NPPs, a cooperation support system to aid communication between MCR operators and field workers in Nuclear Power Plants (NPPs), NUclear COoperation Support and MObile document System (Nu-COSMOS), is suggested. It is not easy for MCR operators to estimate whether field workers conduct their work correctly because MCR operators cannot monitor field workers at a real time, and records on paper procedure written by field workers do not contain the detailed information about work process and results. Thus, for safety operation without any events induced by misunderstand and miscommunication between MCR operators and field workers, the Nu-COSMOS is developed and it will be useful from the supporting cooperation point of view. To support the cooperation between MCR operators and field workers in NPPs, the cooperation support and mobile documentation system Nu-COSMOS is suggested in this work. To improve usability and applicability of the suggested system, the results of using existed digital device based support systems were analyzed. Through the analysis, the disincentive elements of using digital device-based developments and the recommendations for developing new mobile based system were derived. Based on derived recommendations, two sub systems, the mobile device based in-formation storing system and the large screen based information sharing system were suggested. The usability of the suggested system will be conducted by a survey with questionnaires. Field workers and operators, and nuclear-related person who had experiences as an operator, graduate students affiliated in nuclear engineering department will use and test the functions of the suggested system. It is expected that the mobile based information storing system can reduce the field workers' work load and enhance the understanding of MCR operators about field operators work process by monitoring all work results and work processes stored in devices.

Methodology for modular nuclear plant design and construction

International Nuclear Information System (INIS)

Lapp, C.W.; Golay, M.

1992-01-01

During the past decade, the rising cost of nuclear power plant construction has caused the cancellation of many projects and has forced some utilities into bankruptcy. Many factors have contributed to capital cost increases, including regulatory changes, the absence of standard designs, and low worker productivity. Low worker productivity can be attributed to the conventional building process, which is not conductive to productive labor. This study presents innovative ways to reduce the capital cost of nuclear plants through more efficient construction processes designed to increase worker productivity. A major portion of the plant capital cost is the interest paid during construction on borrowed capital. Modular fabrication could potentially reduce interest payments by compressing the construction schedule of nuclear facilities. Additional cost savings expected from modular designs arise from improved quality, productivity, and schedule control in fabrication of plant elements within a factory environment

Trend of collective dose and dose reduction measures of Mitsubishi Electric Corporation workers in nuclear power plants

International Nuclear Information System (INIS)

Yamato, I.; Nakayama, T.; Shimokawa, F.; Yamamoto, T.

1996-01-01

MELCO has supplied the reactor instrumentation control system, reactor coolant pump motors, turbine generator and central control system for the pressurized water type nuclear power plant. For the legal periodical inspection and repair work, MELCO has also received orders for the periodical inspection for 23 power plants (including 4 plants under construction) of 5 electric power companies, and executed the inspection work from the view point of preventive maintenance. The annual dose for MELCO's workers is liable to be decreased in spite of increased number of plants. The dose for new plant in particular is 50, or less as compared with that for conventional plant. This is because the measures taken for the conventional plant against the dose reduction is reflected upon the new plant. The dose reduction measures are taken for each system for which order was received. Such measures are mainly intended to improve the work procedures and equipment for reduction of work time in the radioactive area and to arrange the working process, so as to perform the work in such period when the dose level at the working environment is low. To enhance the workers' consciousness for reduction of dose, MELCO provided the workers with dose predictive training, and let them aware of such items known at the tool box briefing (TBX), which could realize the dose reduction for workers. MELCO has been positively promoting the activity to arrange the desirable work environment for extermination of 3Ks (giken, gitsui, titanai) or 3Ds (dangerous, difficult, dirty) including protection against radiation in corporation with electric power companies. (author)

Occupational dose control in Nuclear Power Plants

International Nuclear Information System (INIS)

Viktorsson, C.; Lochard, J.; Benedittini, M.; Baum, J.; Khan, T.A.

1990-01-01

Reduction in occupational exposure at nuclear power plants is desirable not only in the interest of the health and safety of plant personnel, but also because it enhances the safety and reliability of the plants. This report summarises the current trends of doses to workers at nuclear power plants and the achievements and developments regarding methods for their reduction

Ionizing radiation dose control for workers in a nuclear plant working with unsealed sources

International Nuclear Information System (INIS)

Gerulis, Eduardo

2006-01-01

With the liberation of the use of the nuclear energy for peaceful applications, International Commission Radiological Protection, ICRP, founded in 1928, created a system of protection of the undesirable doses of ionizing radiation in 1958. This has been received by workers, members of the public and environment and hence it became possible for the introduction of these applications. This protection system is adopted by the International Agency of Energy Atomic, IAEA, that publishes recommendations in safety series, 88 and by the Comissao Nacional de Energia Nuclear, CNEN, which publishes these regulations. The international recommendations and national regulations were adapted and they need to be applied in this way. The present paper uses recommendations of the publication 75 from ICRP, of the publication 115 from 88 and regulations of the regulation NN 3.01 from CNEN to present, through radiological protection measures, the ionizing radiation dose control for workers in a nuclear plant that works in the research, production, division and packing of unsealed sources to be used in clinical applications. In that way it is possible to prevent appropriately the undesirable doses and to confirm the received doses. (author)

Robotics for nuclear power plants

International Nuclear Information System (INIS)

Shiraiwa, Takanori; Watanabe, Atsuo; Miyasawa, Tatsuo

1984-01-01

Demand for robots in nuclear power plants is increasing of late in order to reduce workers' exposure to radiations. Especially, owing to the progress of microelectronics and robotics, earnest desire is growing for the advent of intellecturized robots that perform indeterminate and complicated security work. Herein represented are the robots recently developed for nuclear power plants and the review of the present status of robotics. (author)

Robotics for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Shiraiwa, Takanori; Watanabe, Atsuo; Miyasawa, Tatsuo

1984-10-01

Demand for robots in nuclear power plants is increasing of late in order to reduce workers' exposure to radiations. Especially, owing to the progress of microelectronics and robotics, earnest desire is growing for the advent of intellecturized robots that perform indeterminate and complicated security work. Herein represented are the robots recently developed for nuclear power plants and the review of the present status of robotics.

Doses to worker groups in the nuclear industry

International Nuclear Information System (INIS)

Khan, T.; Baum, J.W.

1992-01-01

This article presents some of the results of a study carried out at the Brookhaven National Laboratory's ALARA Center on doses to various worker groups in the U.S. nuclear industry. In this study, data from workers in the industry were divided into male and female groups; the average radiation dose of these tow groups and the correlation of dose with age are presented. The male and female workers were further considered in the various sectors of the industry, and correlations of dose with age for each sector were investigated. For male workers, a downward correlation with age was observed, while for women there appeared to be a slight upward correlation. Data form 13 PWR and 9 BWR plants shows that a small, but important, group of workers would be affected by the NCRP proposed constraint of workers' lifetime dose in rem being maintained less than their ages. Various techniques proposed by the plants to reduce dose to this critical group of workers are also presented

Estimation of impact from natural sources of radiation sources in two non nuclear plant workers and nearby residents

International Nuclear Information System (INIS)

Sousa, Wanderson de Oliveira

2005-09-01

Naturally occurring radioactive materials, often referred to as NORM, are and always have been a part of our world. Our planet 'Earth' and its atmosphere contain many different types of naturally occurring radioactive species , mainly minerals containing radionuclides of uranium and thorium decay series. Human activities for e x p l o i t a t i o n of mineral resources as mining, necessarily, do not enhance the concentration of NORM in products , by-products or residues, but can be a concern, simply due to the increased potential for human exposure. The goal of this work is to assess the impact of the presence of two non-nuclear plants (coal mining and monazite extraction plant) to workers and general population living in the vicinities of plants, by calculating their internal exposure to natural radionuclides . Excreta samples (urine and feces) were collected from workers and inhabitants of the two small towns where workers reside. The activities of 238 U, 234 U ( o n l y in feces), 226 Ra , 210 Pb and 210 Po (only in urine),- present in the samples were determined. The results of daily excretion in urine and feces of the groups, indicate that workers from coal mining, are exposed to natural radionuclides by inhalation and ingestion. The intake of some radionuclides ( 238 U and 210 Po ) are influenced by the professional activity . The results also indicate a chronic intake of 226 Ra by workers of the coal mining and their neighbors. Workers from the monazite extraction plant and inhabitants of the vicinity of the plant are exposed, mainly by ingestion. The intake through diet is the major source of incorporation of natural radionuclides. (author)

Study of Epidemiology Conducted in Indian Nuclear Power Plants-Occupational Workers and Family Members

International Nuclear Information System (INIS)

Ramamirtham, B.; Shringi, K.; Wagh, P. M.

2004-01-01

At present in India, a nuclear generation capacity of 2720 MWe is in operation with 12 units of pressurised heavy water reactors (PHWRs) and 2 units of boiling water reactors (BWRs). The nature of the effects of the low-doses from ionizing radiation has been the subject considerable interest in the scientific community. The radiation exposures due to the operation of the NPPs are small and at low dose rates. The specific objective of the study were to compute the morbidity (prevalence) of cancer among the radiation occupational workers and their families and to compare with suitable controls and to study prevalence of congenital anomalies among the offspring of the employees of the nuclear power plants in India and to determine, if any, their causal relation with radiation exposure. The data collection work was carried out for survey by the local academic medical institutions near the NPP sites under the guidance of Tata Memorial Hospital, Mumbai. The distribution of the confounding factors among the radiation and non-radiation workers did not show any significant difference and thus the possibility of biased results was minimized. The cross-sectional survey has shown that there was no difference in the prevalence of malignancies in the radiation workers as compared to non-radiation workers, nor was there any difference in the prevalence of malignancies in the radiation workers as compared to non-radiation workers, nor was there any difference in the prevalence of malignancies in spouses and offspring. The study did not show any excess cancers among the study population. The congenital abnormalities observed in the offspring of the employees were much less than the reported values among the newborn children. The study has provided useful indicators and generated reliable baseline data for carrying out further work. Scientific thematic Area: 1) Radiation Effects. (Author)

Risk perception among nuclear power plant personnel: A survey

International Nuclear Information System (INIS)

Kivimaeki, M.; Kalimo, R.

1993-01-01

This study investigated risk perception, well-being, and organizational commitment among nuclear power plant personnel. The study group, 428 employees from a nuclear power plant, completed a questionnaire which included the same questions as those in previous surveys on risk perception of lay persons and industrial workers. Hazards at work were not seen as a sizable problem by nuclear power plant personnel. The study group estimated the safety of nuclear power plants better and the possibility of a serious nuclear accident as more unlikely than the general public. Compared to employees in other industrial companies, the overall perceived risks at work among plant personnel did not exceed the respective perceptions of the reference groups. Risk-related attitudes did not explain well-being among plant personnel, but the relationship between the perceived probability of a serious nuclear accident at work and organizational commitment yielded to a significant correlation: Those plant workers who estimated the likelihood of an accident higher were less committed to the organization. 21 refs., 2 tabs

Medical surveillance of nuclear power plant workers during reactor shutdown using whole-body counting and excretion analysis

International Nuclear Information System (INIS)

Le Roux-Desmis, C.

1987-01-01

After a review of radioactivity basis and radiation protection principles, the various aspects of medical surveillance of nuclear power plant workers during reactor shutdown, are presented. Internal contamination incidents that happened during 1986-1987 shutdown of Paluel reactor are exposed. Internal contamination levels are evaluated using whole-body counting and radionuclide determination in feces and urine and compared with dose limits [fr

Risk perception among nuclear power plant employees

International Nuclear Information System (INIS)

Fields, C.D.

1989-01-01

Radiation protection training and general employee training within the nuclear industry are designed to reduce workers' concerns about radiation and to develop skills that will protect against unwarranted exposures. Inaccurate perceptions about radiation by workers can cause a lack of adequate concern or exaggerated fears, which in turn can result in unnecessary radiation exposure to the worker or co-workers. The purpose of the study is threefold: (a) to identify health and safety concerns among nuclear power plant employees, (b) to discover variables that influence the perception of risk among employees, and (c) to ascertain if attitudes of the family, community, and the media affect workers' perception of risk. Workers identified five areas of concern: shift work, radiation, industrial safety, stress, and sabotage

Anatomy of event and human performance management in nuclear power plants

International Nuclear Information System (INIS)

Wang Jinhua

2014-01-01

This article analyzes the occurrence mechanism of events in nuclear power plants, and explains the four factors of human errors and the relations among them, then probes into the occurrence mechanism and characteristics of human errors in nuclear power plants. Moreover, the article clarifies that the principle of human performance training in nuclear power plants is all-member training, and that the implementation approach is to develop different human performance tools for different staff categories as workers, knowledge workers and supervisors, which are categorized based on characteristics of work of different staff. (author)

Social and economic implications of the installation of nuclear plants

International Nuclear Information System (INIS)

Olivetti, F.A.

1981-01-01

This chapter summarizes the Italian experience with the evaluation, control, and containment of the social and economic impacts of nuclear power plant installations. Social and economic impact is defined as a set of causal relationships, direct and indirect, which are established between a nuclear plant and a surrounding territory. A nuclear plant imposes certain permanent restrictions in the use of the surrounding territory. The utilization of particularly dangerous substances requires that the plants be sited at a due distance from large urban centers and industrial areas. Therefore they are located in rural areas where the social and economic equilibria are less stable and more easily subjected to disturbances from outside factors. Essential services which must be provided for nonresident workers during the construction phase result in massive impacts which are compensated by the inflow of economic resources into the community. Social tension is also a likely consequence of importing workers into a community. There are disruptive effects induced by the high salaries paid to the construction workers such as local inflation. During the operating phase, the impacts will be smaller in proportion to the construction phase. Examples of social and economic impacts of nuclear plants in Italy are cited

Present situation of occupational radiation exposure in nuclear power plants

International Nuclear Information System (INIS)

Imabori, Akira

1979-01-01

The present situation of the radiation exposure of workers, including both employes and subcontractors, in the nuclear power plants in Japan, is presented. Twenty seven nuclear power reactors in operation and under construction are tabulated with the name, the owner, the electric output and the commissioning year of each plant. The results of exposure of the workers in these plants are shown, classifying the dose rate into less than 0.5 rem, 0.5 - 1.5 rem, 1.5 - 2.5 rem, 2.5 - 5 rem and more than 5 rem, and the workers into employes and subcontractors. It is noted that the exposure dose of the subcontractors occupies about 88% of all exposure dose, and the exposure is concentrated during regular inspection period. The exposure dose of about 80% of the workers is less than 0.5 rem, and no one was irradiated more than 5 rem in a year. The total exposure dose, which has especially the tendency of increasing with extended maintenance period and decreasing during plant operation period, shows also the trend of increasing with the lapse of operation years. As for the point of view of whole exposure dose, the value is 0.06 -- 0.43 man-rem/10 6 kWh in 1976 FY. It is considered to be necessary to grasp the total exposure dose of each worker wandering from one plant to another, and the central registration center for the workers in radioactive environment was established in 1978. The whole exposure dose data of each worker are stored in the central computer in this center. This system is highly appreciated in radiation exposure management. The total exposure dose is related to the rate of utilization of nuclear plants, and it is expected to decrease with the decrease of plant outage. (Nakai, Y.)

Monitoring of occupational exposure at nuclear power plants

International Nuclear Information System (INIS)

1997-01-01

The regulations concerning the monitoring of radiation doses of nuclear power plant workers and the reporting of radiation doses to the Finnish Centre for Radiation and Nuclear Safety (STUK) are specified in the guide. (10 refs.)

The Robots for Nuclear Power Plants

International Nuclear Information System (INIS)

Choi, Chang Hwan; Kim, Seung Ho; Kim, Chang Hoi; Seo, Yong Chil; Shin, Ho Cheol; Lee, Sung Uk; Jung, Kyung Min; Jung, Seung Ho; Choi, Young So

2005-01-01

Nuclear energy becomes a major energy source worldwide even though the debating environmental and safety dispute. In order to cope with the issues related to the nuclear power plant, the uncertain human factors need to be minimized by automating the inspection and maintenance work done by human workers. The demands of robotic system in nuclear industry have been growing to ensure the safety of nuclear facilities, to detect early unusual condition of it through an inspection, to protect the human workers from irradiation, and to maintain it efficiently. NRL (Nuclear Robotics Laboratory) in KAERI has been developing robotic systems to inspect and maintain nuclear power plants in stead of human workers for over thirteen years. In order to carry out useful tasks, a nuclear robot generally requires the followings. First, the robot should be protected against radiation. Second, a mobile system is required to access to the work place. Third, a kind of manipulator is required to complete the tasks such as handling radioactive wastes and other contaminated objects, etc. Fourth, a sensing system such as cameras, ultrasonic sensors, temperature sensors, dosimetry equipments etc., are required for operators to observe the work place. Lastly, a control system to help the operators control the robots. The control system generally consists of a supervisory control part and remote control part. The supervisory control part consists of a man-machine interface such as 3D graphics and a joystick. The remote control part manages the robot so that it follow the operator's command

Radiation dose to construction workers at operating nuclear power plant sites. Volume 2. Appendices A--F. Final report, September 1975--September 1978

International Nuclear Information System (INIS)

Endres, G.W.R.; Shipler, D.B.

1978-12-01

These appendices contain the dosimetry procedures and details of the personnel and environmental dosimeters used for the Radiation Dose to Construction Workers at Operating Nuclear Power Plant Sites Study. A printout of the computer codes used to analyze dosimeter data is included along with all the raw data obtained. Appendices C through F contain computer output and log-normal plots of dosimetry data for environmental location and construction worker groups

Health check on radiation workers in the nuclear energy industry using Todai Health Index

International Nuclear Information System (INIS)

Tsuchiya, Takehiko; Norimura, Toshiyuki; Kumashiro, Masaharu; Sudo, Seiji; Hashimoto, Tetsuaki.

1986-01-01

In the nuclear energy industry, the plants are located far from urban areas and the working environments are generally separate from each other for radiation protection purposes. The health investigation on radiation workers in the nuclear energy industry was carried out using the Todai Health Index questionnaire in 1982, 1983 and 1984. As a control study non-radiation workers on the other several working fields were investigated in the same manner. The results showed that the status of radiation workers in the nuclear energy industry is similar to that of the workers in the other working fields and the THI questionnaire is useful to know health and working status of a group of workers. (author)

Research and development of advanced robots for nuclear power plants

International Nuclear Information System (INIS)

Tsukune, Hideo; Hirukawa, Hirohisa; Kitagaki, Kosei; Liu, Yunhui; Onda, Hiromu; Nakamura, Akira

1994-01-01

Social and economic demands have been pressing for automation of inspection tasks, maintenance and repair jobs of nuclear power plants, which are carried out by human workers under circumstances with high radiation level. Since the plants are not always designed for introduction of automatic machinery, sophisticated robots shall play a crucial role to free workers from hostile environments. We have been studying intelligent robot systems and regarded nuclear industries as one of the important application fields where we can validate the feasibility of the methods and systems we have developed. In this paper we firstly discuss on the tasks required in nuclear power plants. Secondly we introduce current status of R and D on special purpose robots, versatile robots and intelligent robots for automatizing the tasks. Then we focus our discussions on three major functions in realizing robotized assembly tasks under such unstructured environments as in nuclear power plants; planning, vision and manipulation. Finally we depict an image of a prototype robot system for nuclear power plants based on the advanced functions. (author) 64 refs

Radioepidemiological studies on the occupational exposure of workers in nuclear industry of China

International Nuclear Information System (INIS)

Sun Shiquan; Li Suyun; Yuan Liyun; Wang Yinzhang

1993-11-01

The results of retrospective-cohort radioepidemiological studies on the workers exposed to occupational radiation in the uranium and nuclear plants and uranium mines governed by China National Nuclear Corporation is reported. Period of follow-up is 1971 ∼ 1985, total number of observation 40122, person years of follow-up 575411. The per caput dose of external radiation in workers of reactor, nuclear fuel reprocessing plants and research units was 57 mSv. For fuel element fabrication and gaseous diffusion plants, it was less than 5 mSv and about 3/4 of which came from the committed effective dose of internal radiation. SMR of total death and cancer death was generally less than 1.0 in exposure group of nuclear plants. There was no evidence of increment of the risk of radiogenic cancer. 31786 offsprings of workers in nuclear plants were subjected to the study on hereditary effects. The results was also negative. The only exception was uranium mines. Owing to the high concentration of radon before the 1960's, the average cumulative exposure of radon daughters of uranium miner was about 80 WLM, relative risk of miner lung cancer was about 2.0. the absolute risk coefficient was about 1/10 to 1/3 of the results of Western countries because of the low baseline rate of lung cancer in China. The excess relative risk coefficient was similar to the value presented by other countries. Radon contamination and increment of miner lung cancer encountered prominently in some non-uranium mines in China

Survey on maintenance skills required for nuclear power plant periodic inspections

International Nuclear Information System (INIS)

Hamasaki, Kenichi

2008-01-01

In this study, we conducted a trend survey regarding the problem of passing on senior workers' skills and knowledge to young employees in industries in general, and an interview survey of skilled workers engaged in maintenance work during periodic inspections at a nuclear power plant. These surveys aimed to obtain useful information for maintaining and improving the quality of future maintenance work during nuclear power plant periodic inspections. The trend survey of industries found that the 'Year 2007 Problem (difficulties associated with the start of mass retirements of baby-boomers)' was often takenup in various fields and that many companies were concerned about losing their accumulated skills and know-how. To ensure that skills are smoothly passed on to the younger generation, companies have taken various measures, such as development of plans for passing on skills and knowledge, introduction of the Meister system and implementation of workshops by skilled workers. The interview survey of skilled workers engaged in maintenance work of mechanical equipment during periodic inspections at Nuclear Power Plant A found that various skills were required in maintenance work. Regarding perceived differences between skilled and unskilled maintenance workers, many respondents believed that the largest difference was in terms of time taken to carry out specific procedures. Some maintenance companies have increasingly fewer skilled workers than before or face aging of skilled personnel. As future concerns, respondents cited the loss of skills that have been acquired through experience in construction and in handling of troubles and failures. Differences were observed among companies in the degree to which skills have been passed on to the younger generation. As a reason why skills are not successfully passed on, respondents cited communication problems due to age differences between senior and young workers and other problems that were also observed in other industries

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-08-01

In the Quarterly Reports on the operation of the Finnish nuclear power plants such events and observations are described relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The report also includes a summary of the radiation safety of the plants' workers and the environment, as well as tabulated data on the production and load factors of the plants. The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in commercial operation during the whole first quarter of 1991. The load factor average was 99.1 %. Failures have been detected in the uppermost spacing lattices of nuclear fuel bundles removed from the Loviisa nuclear reactors. Further investigations into the significance of the failures have been initiated. In this quarter, renewed cooling systems for the instrumentation area were introduced at Loviisa 1. The modifications made in the systems serve to ensure reliable cooling of the area even during the hottest summer months when the possibility exists that the temperature of the automation equipment could rise too high causing malfunctions which could endanger plant safety. Occupational radiation doses and external releases of radioactivity were below prescribed limits in this quarter. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

Analysis of color environment in nuclear power plants

International Nuclear Information System (INIS)

Natori, Kazuyuki; Akagi, Ichiro; Souma, Ichiro; Hiraki, Tadao; Sakurai, Yukihiro.

1996-01-01

This article reports the results of color and psychological analysis of the outlook of nuclear power plants and the visual environments inside of the plants. Study one was the color measurements of the outlook of nuclear plants and the visual environment inside of the plants. Study two was a survey of the impressions on the visual environments of nuclear plants obtained from observers and interviews of the workers. Through these analysis, we have identified the present state of, and the problems of the color environments of the nuclear plants. In the next step, we have designed the color environments of inside and outside of the nuclear plants which we would recommend (inside designs were about fuel handling room, operation floor of turbine building, observers' pathways, central control room, rest room for the operators). Study three was the survey about impressions on our design inside and outside of the nuclear plants. Nuclear plant observers, residents in Osaka city, residents near the nuclear plants, the operators, employees of subsidiary company and the PR center guides rated their impressions on the designs. Study four was the survey about the design of the rest room for the operators controlling the plants. From the results of four studies, we have proposed some guidelines and problems about the future planning about the visual environments of nuclear power plants. (author)

Perceived Workplace Interpersonal Support Among Workers of the Fukushima Daiichi Nuclear Power Plants Following the 2011 Accident: The Fukushima Nuclear Energy Workers' Support (NEWS) Project Study.

Science.gov (United States)

Takahashi, Sho; Shigemura, Jun; Takahashi, Yoshitomo; Nomura, Soichiro; Yoshino, Aihide; Tanigawa, Takeshi

2017-10-10

The 2011 Fukushima Daiichi nuclear accident was the worst nuclear disaster since Chernobyl. The Daiichi workers faced multiple stressors (workplace trauma, victim experiences, and public criticism deriving from their company's post-disaster management). Literatures suggest the importance of workplace interpersonal support (WIS) in enhancing psychological health among disaster workers. We sought to elucidate the role of their demographics, disaster-related experiences, and post-traumatic stress symptoms on perceived WIS. We analyzed self-report questionnaires of 885 workers 2-3 months post-disaster. We used sociodemographic and disaster exposure-related variables and post-traumatic stress symptoms (measured by the Impact of Event Scale-Revised) as independent variables. We asked whether WIS from colleagues, supervisors, or subordinates was perceived as helpful, and used yes or no responses as a dependent variable. Logistic regression analyses were performed to assess correlates of WIS. Of the participants, one-third (34.7%) reported WIS. WIS was associated with younger age (20-28 years [vs 49-], adjusted odds ratio [aOR]: 3.25, 95% CI: 1.99-5.32), supervisory work status (aOR: 2.30, 95% CI: 1.35-3.92), and discrimination or slur experience (aOR: 1.65, 95% CI: 1.08-2.53). Educational programs focusing on WIS might be beneficial to promote psychological well-being among nuclear disaster workers, especially younger workers, supervisors, and workers with discrimination experiences. (Disaster Med Public Health Preparedness. 2017; page 1 of 4).

A review of cancer mortality data of radiation workers of Nuclear Power Plant, Paks, Hungary, in the light the international radiation epidemiology study

International Nuclear Information System (INIS)

Turai, I.; Kerekes, A.; Otos, M.; Veress, K.

2007-01-01

Complete text of publication follows. Objective: To give a review of cancer mortality data among Hungarian radiation workers in nuclear industry in comparison with the results of the international nuclear workers' study prevailing the size of the study group of all former studies. Methods: Retrospective cohort study including 598,068 workers of 154 nuclear establishments in 15 countries (AUS, BEL, CAN, FIN, FRA, GER, HUN, JAP, LIT, ROK, SLK, SPA, SWE, UK, USA) coordinated by the International Agency for Research on Cancer (IARC, Lyon, France). The national study was extended for an additional 4-year period. Results: In the international study 407,391 persons in 13 years of average employment received 19.4 mSv mean cumulative dose, while in the national study 3322 radiation workers of Nuclear Power Plant (NPP) Paks, Hungary, in 14 years of follow-up period accumulated in average 5.13 mSv, only. There were 5233 cancer deaths registered in the international study, associated with an estimated ERR of 0.97 per Sv. Thus, 19.4 mSv recorded cumulative dose can explain 1 to 2% of cancer death cases. In radiation workers of NPP, Paks, during the period of 1985-1998 there were 40 cancer deaths observed against the expected 58.8 cases. In a further four year period (1999-2002) 29 cancer death cases were identified vs. the expected 65.5 cases. The SMR for the cancer death cases registered in recent and former radiation workers of NPP, Paks in the 18-year follow-up period is 56%. The SMR from all causes was even lower, 40% only. Conclusions: In the international study the mean accumulated radiation dose received by nuclear workers in 13 years is below of the recent annual dose limit (20 mSv/yr of the effective dose). The average value for the whole of radiation workers in 15 countries is almost 4-times higher of that registered in Hungary. The 'healthy worker effect' in the nuclear industry, and particularly in Hungary has been proven, once again. Nevertheless, the results

Cancer mortality among nuclear workers in Belgium

International Nuclear Information System (INIS)

Engels, H.; Holmstock, L.; Mieghem, E. Van; Swaen, G.M.; Wambersie, A.

2000-01-01

To investigate long term health effects of chronic exposure to low doses of ionising radiation, the Nuclear Research Center (SCK.CEN) in Mol set up a retrospective cohort study in 5 nuclear facilities in Belgium (SCK.CEN, Belgonucleaire, Belgoprocess, 2 Electrabel nuclear power plants). Cancer mortality among nuclear workers is studied in relation to occupational exposure to ionising radiation. This study is part of the 'International Collaborative Study on Cancer Risk among Radiation Workers', coordinated by the International Agency for Research on Cancer (IARC/WHO), pooling data of 14 countries. During the period 1953-1994, all workers registered in one of the participating facilities were included in the study (n=7361). Data have been collected from different information sources: personnel registries (identification, occupational history), dosimetry records (e.g. annual effective dose), National Population Registry and local authorities (vital status). National Institute of Statistics (causes of death from the death certificates), National Radiation Registry/Ministry of Labour (transfer doses), questionnaires (e.g. smoking habits). Retrospective collection of data and privacy protection regulations specific to Belgium hampered the conduct of this study, causing labour intensive and time consuming procedures. Written informed consent of next-of-kin is required to obtain information from the death certificates. Before 1969 only family reported causes of death are available. Despite the above mentioned constraints, first results of Standardised Mortality Ratio (SMR) calculations are now available for SCK.CEN workers for the period 1969-1994 (n=3270, vital status ascertainment: 95%, underlying cause of death ascertainment: 80%). Available SMR's can be summarised as follows: male workers, no measurable dose (n=785): SMR all causes=75% (95%CI: 61-91), SMR all tumours=64% (95%CI: 42-93), 2 leukemia deaths were observed, whereas 1 is expected, male workers, measurable

Enhancing nuclear power plant safety via on-site mental fatigue management

Directory of Open Access Journals (Sweden)

Tsai Ming-Kuan

2017-01-01

Full Text Available Nuclear incidents and accidents have occurred at various nuclear power plants. Since some of these incidents and accidents caused by human errors might be preventable, numerous researchers argue that fatigue management for on-site workers is the key, especially for mental fatigue. Thus, this study proposes an approach consisting of two mechanisms. A fatigue monitor could identify the mentally fatigued workers by detecting their brain wave rhythms through a brain-computer interface. For such workers, a fatigue alert would awaken them. If the status of the mentally fatigued workers becomes worse, based on a positioning technique (i.e., wireless networks, this mechanism would alert the nearby workers and managers to deal with this condition. The test results indicate that the proposed approach enhanced the capacity to examine the mentally fatigued workers, ensured the accuracy in locating these workers, and avoided possible nuclear incidents. This study is a useful reference for similar applications in the nuclear industry.

Radiation dose registration and epidemiological study for workers of nuclear institutions in Japan

International Nuclear Information System (INIS)

Kumatori, T.

1992-01-01

The first nuclear reactor was operated in 1957 at Tokai-mura in Japan. Since then radiation dose of workers has been controlled by nuclear institutions according to the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors. However, many nuclear power plants and other nuclear facilities were built, resulting in the remarkable increase of workers in controlled areas. Further, periodical inspection and repair work at nuclear facilities were carried out by employees of subcontractors, who were engaged in such work at many different facilities, so that it was getting more and more difficult to obtain accurate information of radiation dose on these workers. In order to meet this situation, the open-quotes Radiation Dose Registration Center for Workersclose quotes (RADREC) was established in November 1977 within the open-quotes Radiation Effects Associationclose quotes (REA), which was founded in September 1960 for the purpose of supporting the research on radiation effects and radiation protection. In January 1978, RADREC was designated by the Government as an organization to preserve the records on exposure of radiation workers, which was linked up with the registration system

Worker in nuclear activity

International Nuclear Information System (INIS)

Goes Fischer, M.D. de; Associacao Brasileira de Direito Nuclear, Rio de Janeiro)

1984-01-01

Juridical aspects with respect to the workers in nuclear activity are presented. Special emphasis is given to the clauses of the statute of workers (Consolidacao das Leis do Trabalho) the rules of the Ministerio do Trabalho and the rules of the Comissao Nacional de Energia Nuclear. The performance of the international authorities is also emphasized such as the International Labour Organization, the International Atomic Energy Agency and the International Radiological Protection Commission. (Author) [pt

Administrative procedures for regulating construction and operation of nuclear power plants

International Nuclear Information System (INIS)

Cochaud, J.P.

1981-01-01

This article first explains that nuclear power plants in France are governed by a complex system of regulations within the framework of different laws concerning, in particular, protection of the environment, public health and workers. It then examines the administrative procedures and the licensing regime for nuclear power plants. (NEA) [fr

Experiences in limiting radiation exposure to the embryo/fetus in nuclear power plants

International Nuclear Information System (INIS)

Kelly, J.J.

1991-01-01

This paper presents the results of a survey of operating nuclear reactors and nuclear fuel fabrication facilities in the US. The survey obtained information on the number of women radiation workers in those plants over the last ten years and the number of workers potentially exposed to radiation while pregnant. Information on plant exposure limits for pregnant workers practiced at these plants and whether these limits comply with NCRP guidance and proposed NRC regulatory limits will also be presented. The discussion will include the effects of unions, labor arbitration, and legal actions on these policies. The unique problems of fuel manufacturers in addressing the proposed NRC regulations for embryo/fetus exposure will also be presented

New research discovery may mean less radioactive contamination, safer nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Murph, S. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-06-20

Murph has now made another nanoparticle breakthrough that could benefit various work environments such as nuclear power plants. Murph and her team have created nanoparticle treated stainless steel filters that are capable to capturing radioactive vapor materials. Just like air filters capture dust and dirt, these filters are capable of capturing large amounts of radioactive vapors. The new research may one day mean that nuclear power plant workers, and other workers in related fields, will have a safer working environment.

Concerning control of radiation exposure to workers in nuclear reactor facilities for testing and nuclear reactor facilities in research and development phase (fiscal 1987)

International Nuclear Information System (INIS)

1988-01-01

A nuclear reactor operator is required by the Nuclear Reactor Control Law to ensure that the radiation dose to workers engaged in the operations of his nuclear reactor is controlled below the permissible exposure doses that are specified in notifications issued based on the Law. The present note briefly summarizes the data given in the Reports on Radiation Control, which have been submitted according to the Nuclear Reactor Control Law by the operators of nuclear reactor facilities for testing and those in the research and development phase, and the Reports on Control of Radiation Exposure to Workers submitted in accordance with the applicable administrative notices. According to these reports, the measured exposure to workers in 1987 were below the above-mentioned permissible exposure doses in all these nuclear facilities. The 1986 and 1987 measurements of radiation exposure dose to workers in nuclear reactor facilities for testing are tabulated. The measurements cover dose distribution among the facilities' personnel and workers of contractors. They also cover the total exposure dose for all workers in each of four plants operated under the Japan Atomic Energy Research Institute and the Power Reactor and Nuclear Fuel Development Corporation. (N.K.)

Development of digital device based work verification system for cooperation between main control room operators and field workers in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Seung Min, E-mail: jewellee@kaeri.re.kr [Korea Atomic Energy Research Institute, 305-353, 989-111 Daedeok-daero, Yuseong-gu, Daejeon (Korea, Republic of); Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Lee, Hyun Chul, E-mail: leehc@kaeri.re.kr [Korea Atomic Energy Research Institute, 305-353, 989-111 Daedeok-daero, Yuseong-gu, Daejeon (Korea, Republic of); Ha, Jun Su, E-mail: junsu.ha@kustar.ac.ae [Department of Nuclear Engineering, Khalifa University of Science Technology and Research, Abu Dhabi P.O. Box 127788 (United Arab Emirates); Seong, Poong Hyun, E-mail: phseong@kaist.ac.kr [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

2016-10-15

Highlights: • A digital device-based work verification and cooperation support system was developed. • Requirements were derived by interviewing field operators having experiences with mobile-based work support systems. • The usability of the proposed system was validated by conducting questionnaire surveys. • The proposed system will be useful if the manual or the set of guidelines is well constructed. - Abstract: Digital technologies have been applied in the nuclear field to check task results, monitor events and accidents, and transmit/receive data. The results of using digital devices have proven that these devices can provide high accuracy and convenience for workers, allowing them to obtain obvious positive effects by reducing their workloads. In this study, as one step forward, a digital device-based cooperation support system, the nuclear cooperation support and mobile documentation system (Nu-COSMOS), is proposed to support communication between main control room (MCR) operators and field workers by verifying field workers’ work results in nuclear power plants (NPPs). The proposed system consists of a mobile based information storage system to support field workers by providing various functions to make workers more trusted by MCR operators; also to improve the efficiency of meeting, and a large screen based information sharing system supports meetings by allowing both sides to share one medium. The usability of this system was estimated by interviewing field operators working in nuclear power plants and experts who have experience working as operators. A survey to estimate the usability of the suggested system and the suitability of the functions of the system for field working was conducted for 35 subjects who have experience in field works or with support system development-related research. The usability test was conducted using the system usability scale (SUS), which is widely used in industrial usability evaluation. Using questionnaires

Development of digital device based work verification system for cooperation between main control room operators and field workers in nuclear power plants

International Nuclear Information System (INIS)

Lee, Seung Min; Lee, Hyun Chul; Ha, Jun Su; Seong, Poong Hyun

2016-01-01

Highlights: • A digital device-based work verification and cooperation support system was developed. • Requirements were derived by interviewing field operators having experiences with mobile-based work support systems. • The usability of the proposed system was validated by conducting questionnaire surveys. • The proposed system will be useful if the manual or the set of guidelines is well constructed. - Abstract: Digital technologies have been applied in the nuclear field to check task results, monitor events and accidents, and transmit/receive data. The results of using digital devices have proven that these devices can provide high accuracy and convenience for workers, allowing them to obtain obvious positive effects by reducing their workloads. In this study, as one step forward, a digital device-based cooperation support system, the nuclear cooperation support and mobile documentation system (Nu-COSMOS), is proposed to support communication between main control room (MCR) operators and field workers by verifying field workers’ work results in nuclear power plants (NPPs). The proposed system consists of a mobile based information storage system to support field workers by providing various functions to make workers more trusted by MCR operators; also to improve the efficiency of meeting, and a large screen based information sharing system supports meetings by allowing both sides to share one medium. The usability of this system was estimated by interviewing field operators working in nuclear power plants and experts who have experience working as operators. A survey to estimate the usability of the suggested system and the suitability of the functions of the system for field working was conducted for 35 subjects who have experience in field works or with support system development-related research. The usability test was conducted using the system usability scale (SUS), which is widely used in industrial usability evaluation. Using questionnaires

Review of health issues of workers engaged in operations related to the accident at the Fukushima Daiichi Nuclear Power Plant.

Science.gov (United States)

Hiraoka, Koh; Tateishi, Seiichiro; Mori, Koji

2015-01-01

The aim of this review was to summarize the lessons learned from the experience in protecting the health of workers engaged in operations following the accident at the Fukushima Daiichi Nuclear Power Plant (NPP). We reviewed all types of scientific papers examining workers' health found in Medline and Web of Sciences as well as some official reports published by the Ministry of Health, Labour and Welfare of Japan and other governmental institutes. The papers and reports were classified into those investigating workers at the Fukushima Daiichi and Daini NPPs, workers engaged in decontamination operations in designated areas, and other workers. Regarding workers at the NPPs, many efforts were made to establish an emergency-care and occupational health system. Risk management efforts were undertaken for radiation exposure, heat stress, psychological stress, outbreak of infectious diseases, and fitness for work. Only a few reports dealt with decontamination workers and others; however, the health management of these workers was clearly weaker than that for workers at the NPPs. Many lessons can be learned from what occurred. That knowledge can be applied to ongoing decommissioning work and to future disasters. In addition, it is necessary to study the long-term health effects of radiation exposure and to accumulate data about the health of workers engaged in decontamination work and other areas.

Perceived nuclear risk, organizational commitment, and appraisals of management: A study of nuclear power plant personnel

International Nuclear Information System (INIS)

Kivimaeki, M.; Kalimo, R.; Salminen, S.

1995-01-01

This study examined to what extent nuclear risk perceptions, organizational commitment (OC), and appraisals of management are associated with each other among nuclear power plant personnel. The sample consisted of 428 nuclear power plant workers who completed a questionnaire at their workplace. Perceived nuclear risk and OC were most closely related to the appraisals of the top management of the organization. As the trust in and satisfaction with the top management increased, perceived nuclear safety and acceptance of the organizational goals and values heightened. This result is discussed in the context of industrial safety management. 29 refs., 2 tabs

The classification of knowledge and expertise in Finnish nuclear power plants

International Nuclear Information System (INIS)

Kuronen, T.; Rintala, N.

2006-01-01

The difficulties in sharing tacit knowledge may compromise the safe performance of high-reliability organisations. This threat has been recognised in nuclear power plants worldwide, owing to the risk of simultaneous retirements. In this study, the nature of tacit knowledge in Finnish nuclear power plants was examined and the expertise of nuclear workers modelled. The results of this interview study showed that the tacit nuclear knowledge can be classified in two dimensions: technical and contextual. According to this classification, the employees in plants can be categorised in four categories: the experts; the novices; the technical specialists; the context sensitives. (author)

Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident

Energy Technology Data Exchange (ETDEWEB)

Sadeghi, Nahid; Ahangari, Rohollah; Kasesaz, Yaser; Noori-kalkhoran, O. [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of). Reactor Research School

2017-11-15

In the case of Fukushima Daiichi nuclear power plant (FNP) accident, the radioactive material was released from reactor units 1-3 and transported to short and long distances due to the atmospheric pathways-motions. Power sources for monitoring posts were lost due to earthquake and tsunami. Based on air dose rates and other data measured by monitoring cars, the amount of radioactive material released to the atmosphere from the power station was obtained. The atmospheric dispersion and the transport model used in the RASCAL code, estimate the radionuclide concentrations downwind, both in the air and on the ground due to deposition. The calculated concentrations are then used to estimate the projected doses for workers in vicinity of the accident area in the first minutes of accident time. For dose modeling, we assumed that each worker was 15 min in vicinity of FNP in accident situation, once without and once with protective clothes or respirator. According to Tokyo Electric Power Company (TEPCO) report six workers had received doses over 250 mSv (309 to 678 mSv) apparently due to inhaling Iodine-131 fume. In this paper the calculated dose results using RASCAL code shows that, if emergency workers who work in early phase of accident had not used protective equipment, for 15 min, inhalation doses from iodine in their thyroid gland up to 12 March afternoon would have been 520 mSv. A comparison between calculation results and TEPCO report shows that dose calculated virtually is nearly equal to TEPCO measurement results.

Human Performance at the Perry Nuclear Power Plant

International Nuclear Information System (INIS)

Rabe, Alan W.

1998-01-01

Provides a description of human performance training for plant workers as implemented at the Perry Nuclear Power Plant. Practical concepts regarding the training are presented as well as a demonstration of some of the training material. Concepts are drawn from INPO, Reason and Deming. The paper encourages the use of site-wide and individual organizational unit training in human performance management techniques. (author)

Radiation occupational health interventions offered to radiation workers in response to the complex catastrophic disaster at the Fukushima Daiichi Nuclear Power Plant

International Nuclear Information System (INIS)

Shimura, Tsutomu; Yamaguchi, Ichiro; Terada, Hiroshi; Kunugita, Naoki; Okuda, Kengo; Svendsen, E.R.

2015-01-01

The Fukushima Daiichi Nuclear Power Plant (NPP) 1 was severely damaged from the chain reaction of the Great East Japan Earthquake and Tsunami on 11 March 2011, and the consequent meltdown and hydrogen gas explosions. This resulted in the worst nuclear accident since the Chernobyl accident of 1986. Just as in the case of Chernobyl, emergency workers were recruited to conduct a wide range of tasks, including disaster response, rescuing activities, NPP containment, and radiation decontamination. This paper describes the types and efficacy of the various occupational health interventions introduced to the Fukushima NPP radiation workers. Such interventions were implemented in order to prevent unnecessary radiation overexposure and associated adverse health effects and work injuries. Less than 1% of all emergency workers were exposed to external radiation of >100 mSv, and to date no death or health adversities from radiation have been reported for those workers. Several occupational health interventions were conducted, including setting of new regulatory exposure limits, improving workers' radiation dosimetry, administration of stable iodine, running an occupational health tracking system, and improving occupational medicine and preventative care. Those interventions were not only vital for preventing unnecessary radiation, but also for managing other general health issues such as mental health, heat illness and infectious disease. Long-term administration of the aforementioned occupational health interventions is essential to ensure the ongoing support and care for these workers, who were put under one of the most severe occupational health risk conditions ever encountered. (author)

Health effects study of the nuclear industry workers in Japan

International Nuclear Information System (INIS)

Tamiko Iwasaki

1997-01-01

To clarify the effects of low-dose and low-dose-rate exposure to the human body, study on the health effects of the nuclear industry workers in Japan was conducted since 1990 by the Institute of Radiation Epidemiology, the Radiation Effects Association, which had been entrusted by the Science and Technology Agency of the Japanese Government. In the first phase analysis between 1986 and 1992, the study population was selected from among persons who were engaged in radiation work at nuclear power plants and associated facilities, and registered in the Radiation Dose Registration Center for Workers. The cohort consisted of 114,900 persons who satisfied the criteria of nationality, age, sex, etc. The average follow-up period was 4.6 years, and the average cumulative dose per person was 13.9 mSv. The total number of deaths among the study population was 1,758, including 661 deaths due to all malignant neoplasms. The Standardized Mortality Ratio of various death causes was compared. Furthermore, the cohort was grouped by five different dose levels, and the O/E was calculated to test whether there is a trend for the death rate to increase with dose. Among nuclear workers no significant increase in deaths nor any relationship with radiation dose was found, except the pancreatic cancer with 10-years lag. Since many previous studies of nuclear industry workers have demonstrated no significant association between exposure dose and pancreatic cancer, we cannot immediately conclude a causal relationship between with radiation. (author)

Radiation exposure of workers in nuclear medicine

International Nuclear Information System (INIS)

Bujnova, A.

2008-01-01

Nuclear medicine is an interdisciplinary department that deals with diagnosis and therapy using open sources. Therefore workers in nuclear medicine are in daily contact with ionizing radiation and thus it is essential to monitor a radiation load. Each work must therefore carry out monitoring of workers. It monitors compliance with the radiation limits set by law, allows an early detection of deviations from normal operation and to demonstrate whether the radiation protection at the workplace is optimized. This work describes the principles of monitoring of workers in nuclear medicine and monitoring methods for personal dosimetry. In the next section the author specifically deals with personal dosimetry at the Department of Nuclear Medicine St. Elizabeth Cancer Institute, Bratislava (KNM-Ba-OUSA). The main part of the work is to evaluate the results of a one-year monitoring of radiation workers KNM-Ba-OUSA. (author)

Skin Dose Assessment by Hot Particles in Domestic Nuclear Power Plant

International Nuclear Information System (INIS)

Choi, Bo Yeol; Cho, Woon Kap; Lee, Jai Ki

2009-01-01

Since a contamination event by hot particles happened due to damaged nuclear fuel at a nuclear power plant (NPP) in the 1980's, skin exposure resulted from hot particles has gotten considerable attention from all the radiation workers in the nuclear industry. In particular, contamination incident caused by hot particles which happened at a NPP in Susquehanna proved that there existed hot particles with the radioactivity of 0.7 GBq, 0.78 GBq, and even 2.78 GBq at maximum. One of these particles was found on a worker's shoe and gave out a dose of 170 mSv. Although there has been no contamination event reported in domestic NPPs which are caused by hot particles, it is hard to conclude that there is no possibility of such contamination for radiation workers. The contaminated samples employed in this study were taken from local NPPs and supposes a case of a worker's skin contaminated by hot particles to evaluate the dose provided to the worker's skin

Occupational exposures and practices in nuclear power plants

International Nuclear Information System (INIS)

Baum, J.W.

1989-01-01

As the first generation of commercial nuclear power comes to a close, it is timely to consider the status of occupational exposure in the power generation industry, that is, the collective occupational radiation doses received by workers in nuclear power plants. The picture is surprising. One might have thought that as newer, larger, and more modern plants came on line, there would be a significant decrease in exposure per unit of electricity generated. There is some indication that this is now happening. One might also have thought that the United States, being a leader in the development of nuclear power, and in the knowledge, experience and technology of nuclear radiation protection, would have the greatest success in controlling exposure. This expectation has not been fulfilled. 32 refs., 4 figs., 5 tabs

Radiation management and health management at the Chernobyl nuclear power plant

International Nuclear Information System (INIS)

Okazaki, Ryuji; Kubo, Tatsuhiko; Tateishi, Seiichiro

2014-01-01

This paper describes the measures taken by the Chernobyl nuclear power plant since the accident in April 1986 to date, compares them with the situation of the current Fukushima nuclear accident, and introduces the contents of the authors' visit and coverage in October 2013, including the report of radiation damage. At the Chernobyl site, a new sarcophagus is under construction since 2012. The health care of the workers working at the new and old sarcophaguses of the Chernobyl nuclear power plant is carried out at a national level of Ukraine, which is an important management for decommissioning work. Health diagnosis is also applied to the workers in the new sarcophagus, and radiation-related disease is not reported at present. The number of the persons who died from acute radiation exposure diseases after the accident was 28. It was reported that chronic lymphocytic leukemia (CLL) appeared significantly when the radiation exceeded 100 mSv. The workers who wish to work at the Chernobyl nuclear power plant must pass the test and obtain national qualifications, and then they are able to work for the first time. In the check-in medical control, about half of applicants were rejected. Workers who work at the new sarcophagus are subject to comprehensive health management under the Ukrainian law. There were 58 people who reached annual exposure dose limit of 20 mSv or more among 7,529 people, the cause of which may be the work at the areas of high radiation dose. Even in Fukushima, it is important to perform high quality management based on centralized medical examination, and to further analyze the effects of low-dose exposure to radiation. (A.O.)

Comparison of p53 levels in lymphocytes and in blood plasma of nuclear power plant workers

International Nuclear Information System (INIS)

Roessner, Pavel; Chvatalova, Irena; Schmuczerova, Jana; Milcova, Alena; Roessner, Pavel; Sram, Radim J.

2004-01-01

p53 levels were assessed in lymphocytes and in blood plasma of workers from two Czech nuclear power plants (NPP): 114 subjects working in Temelin and 108 subjects working in Dukovany. Ionizing radiation (IR) exposure data were available for 64 and 59 subjects working in the monitored zones from the NPP in Temelin and Dukovany, respectively. The short-term doses of IR for these subjects were 0.01 and 0.12 mSv, and the long-term doses were 0.46 and 5.68 mSv, in the Temelin and Dukovany NPP, respectively. As a control group, 46 subjects living in Ceske Budejovice, a city nearby the Temelin NPP, were analyzed. The concentration of p53 in lymphocytes was significantly higher in workers from the monitored zone in the Dukovany NPP (median value 6.4 pg/μg protein, P < 0.001) than in workers from the Temelin NPP (3.2 pg/μg) as well as in the control group (3.5 pg/μg). In contrast, plasma levels of p53 were comparable in the control group (median value 116 pg/ml plasma) and workers from the monitored zone of Dukovany NPP (102 pg/ml), but lower in workers from Temelin NPP (5 pg/ml). Other factors affecting p53 levels were studied. Smoking resulted in increased p53 lymphocyte levels. The effect of polymorphisms in metabolic and DNA repair genes on p53 levels was analyzed. The correlation was found between p53 levels in lymphocytes and p53 codon 72 polymorphism in subjects working in NPPs, but not in the control group. The results of measurement p53 levels in lymphocytes suggest that this biomarker could reflect the short-term as well as long-term effects of low doses IR. Its impact on human health should be further explored

Nuclear: a world without worker?

International Nuclear Information System (INIS)

Fournier, Pierre; Maziere, M.

2014-01-01

After having recalled some characteristics of the electro-nuclear sector in terms of employment (direct and indirect jobs, average age, number of persons controlled on the radiological level, exposure with respect to work location), the author outlines that workers of this sector are seldom evoked whereas investments, incidents and accidents are generally the main evoked and commented topics. He proposes some explanations about this image of the nuclear sector. He reports an incident which occurred in Marcoule and outlines how a set of imperfectly managed events resulted in this incident. He also outlines the importance of the role of workers and the difficulty to make the right choice in such situations. As a conclusion, the author draws some lessons, and particularly outlines that the commitment of workers should be put forward

Nuclear power plants

International Nuclear Information System (INIS)

1985-01-01

Data concerning the existing nuclear power plants in the world are presented. The data was retrieved from the SIEN (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: nuclear plants, its status and type; installed nuclear power plants by country; nuclear power plants under construction by country; planned nuclear power plants by country; cancelled nuclear power plants by country; shut-down nuclear power plants by country. (E.G.) [pt

Radiation occupational health interventions offered to radiation workers in response to the complex catastrophic disaster at the Fukushima Daiichi Nuclear Power Plant.

Science.gov (United States)

Shimura, Tsutomu; Yamaguchi, Ichiro; Terada, Hiroshi; Okuda, Kengo; Svendsen, Erik Robert; Kunugita, Naoki

2015-05-01

The Fukushima Daiichi Nuclear Power Plant (NPP) 1 was severely damaged from the chain reaction of the Great East Japan Earthquake and Tsunami on 11 March 2011, and the consequent meltdown and hydrogen gas explosions. This resulted in the worst nuclear accident since the Chernobyl accident of 1986. Just as in the case of Chernobyl, emergency workers were recruited to conduct a wide range of tasks, including disaster response, rescuing activities, NPP containment, and radiation decontamination. This paper describes the types and efficacy of the various occupational health interventions introduced to the Fukushima NPP radiation workers. Such interventions were implemented in order to prevent unnecessary radiation overexposure and associated adverse health effects and work injuries. Less than 1% of all emergency workers were exposed to external radiation of >100 mSv, and to date no deaths or health adversities from radiation have been reported for those workers. Several occupational health interventions were conducted, including setting of new regulatory exposure limits, improving workers' radiation dosimetry, administration of stable iodine, running an occupational health tracking system, and improving occupational medicine and preventative care. Those interventions were not only vital for preventing unnecessary radiation, but also for managing other general health issues such as mental health, heat illness and infectious diseases. Long-term administration of the aforementioned occupational health interventions is essential to ensure the ongoing support and care for these workers, who were put under one of the most severe occupational health risk conditions ever encountered. © The Author 2014. Published by Oxford University Press on behalf of The Japan Radiation Research Society and Japanese Society for Radiation Oncology.

The reproductive function state of women working at the Smolensk nuclear power plant in shops with hazard working conditions

International Nuclear Information System (INIS)

Lyaginskaya, A.M.; Osipov, V.A.; Bugrova, T.I.; Kreusheva, I.F.; Plitkina, V.M.; Karepanova, L.A.; Afanas'eva, R.V.

2001-01-01

The reproductive function state of female workers at the Smolensk nuclear power plant in shops with hazardous working conditions is estimated. Female workers occupied in major shops of the Smolensk nuclear power plant are interviewed and subjected to a questionnaire. Individual medical care records of pregnant women and newborns are analyzed. Health statistics data for the town of Desnogorsk are used for comparison. Indicators of the reproductive function among female workers occupied from 1984 up to 1998 at the Smolensk nuclear power plant in workplaces with hazardous working conditions have not been shown to differ from those among the general female population in the town of Desnogorsk: neither these indicators deteriorated during the 14 year period of work as compared with the initial level [ru

Development of safety culture by improving risk communication in a nuclear power plant

International Nuclear Information System (INIS)

Sugiman, Toshio; Yoshikawa, Hidekazu

2004-01-01

Safety culture is conceptually examined from the viewpoint of activity theory proposed by Engestroem. The theory is instrumental in broadening our scope of views to the extent that a particular (group of person(s) and his/her (their) environment are regarded as a part of activity of a larger collectivity consisting of people and their physical and institutional environments. Overwhelming orientation toward an unmanned plant is reflected in object → outcome and mediating artifacts in the structure of activity in a nuclear power plant while it is contradicted with another orientation toward the improvement of employee's ability in community, rules, and division of labor. Three possible ways to transform a currently dominant activity into a new form were suggested depending on a preliminary study of our research project headed by the seconds author. First, community of a nuclear power plant may as well be expanded to the extent that nuclear experts outside the plant, especially those working for a plant/equipment manufacturing company, can share information with workers inside the plant through internet system that has been developed in our project. Second, community of workplace may as well be reexamined concerning division of labor between a supervisor and subordinates. Among all, leader behaviors of a supervisor that were effective to reduce psychological stress of subordinates, which, in turn, make positive contribution to safety culture, were identified by a questionnaire survey. Last, a minority of workers who tend to take risks for radiation exposure more seriously than the majority and share similar risk cognition with ordinary citizens may as well be utilized as linking pin that brings a warning signal from both a minority of nuclear experts outside the plant and ordinary citizens to the majority of workers in the plant who tend to be devoted to implementing everyday job. (author)

Abnormality diagnostic technology for nuclear power plants

International Nuclear Information System (INIS)

Ishikawa, Satoshi

1986-01-01

In nuclear power plants, it is feared that the failure of the installations containing radioactive substances may inflict serious damage on public and workers. Therefore in nuclear power plants, the ensuring of safety is planned by supposing hypothetical accidents which are not likely to occur from engineering viewpoint, and multiple protection measures are taken in the plant constitution. In addition to the safety measures from such hardware aspect, recently in order to prevent the occurrence of accidents by using various safety-confirming means, and to detect early when any accident occurred, the development and putting in practical use of many monitoring equipments have been promoted. In such background, the development of nuclear power generation supporting system was carried out for five years since fiscal year 1980, subsidized by the Ministry of International Trade and Industry, and in this report, the technology of equipment abnormality diagnosis developed as a part of that project and the diagnostic techniques for actual plants are described. The technology of diagnosing nuclear reactor abnormality includes the diagnosis of loose metal pieces and the abnormal vibration of in-core structures. The detection and diagnosis of valve leak and the diagnosis of the deterioration of detectors are also explained. (Kako, I.)

The Union view of back end fuel cycle provisions for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1981-01-01

After a long political and technical discussion, the German trade unions united in the German Federation of Labor (DGB) arrived at the finding that back end fuel cycle provisions for nuclear power plants in the Federal Republic of Germany, in addition to the present concept of the Government providing for a reprocessing plant, should also include studies of the alternative possibility to store spent fuel elements over long periods of time, perhaps with a possibility to recover them later. That decision is also based on a report by the Nuclear Technology Working Group of the Metal Workers Union (IG Metall) and the Public Workers Union (OeTV). (orig.) [de

Optimization of radiological protection in Spanish nuclear power plants

International Nuclear Information System (INIS)

O'Donnell, P.; Amor, I.; Butragueno, J.L.

1997-01-01

Optimizing the radiological protection of occupationally exposed nuclear power plant workers has become one further item in what is called the safety culture. Spanish facilities are implementing programme with this in mind, grounded on a personal motivation policy with the backing of a suitable organizational structure. (Author)

Is nuclear energy safe for workers and the public. III

International Nuclear Information System (INIS)

McKenzie, J.J. Jr.

1976-01-01

Dr. McKenzie says a national energy policy does exist, being based on synthetic fuels from coal and nuclear energy to meet future demands, and based on a complete lack of attention to conservation. In meeting energy demands for the future, he feels the opportunity still exists to create the scenario that will require meaningful jobs in the process, jobs requiring less capital and less energy. On the risks of nuclear energy, Dr. McKenzie discusses the funding, research, and results of the Atomic Energy Commission's safety program. He airs his views on WASH-1400, the study by Professor Norman Rasmussen, dealing with the possibilities of reactor core meltdowns. He thinks a worse problem resulting from nuclear power plants is that of waste disposal and cites AEC's poor record of managing these wastes in Kansas and elsewhere. In concluding, Dr. McKenzie says: (1) nuclear power may not be the best thing in the world, maybe we should look at other alternatives; (2) conservation is most important, and creates jobs at the same time if handled correctly; (3) AFL-C10 should sponsor a study on energy systems investigating its employment potential, net energy, economic factors, and capital requirements; and (4) construction of nuclear and coal plants will create jobs, but building solar plants will create jobs with fewer restraints on the environment. A panel discussion follows this, the third paper, on nuclear safety for workers and the public

Experience with training of operating and maintenance personnel of nuclear power plants

International Nuclear Information System (INIS)

Pospisil, M.; Cencinger, F.

1988-01-01

The system is described of the specialist training of personnel for Czechoslovak nuclear power plants. Training consists of basic training, vocational training and training for the respective job. Responsible for the training is the Research Institute for Nuclear Power Plants; actual training takes place at three training centres. Personnel are divided into seven categories for training purposes: senior technical and economic staff, shift leaders, whose work has immediate effect on nuclear safety, engineering and technical personnel of technical units, shift leaders of technical units, personnel in technical units, shift service personnel and operating personnel, maintenance workers. Experience with training courses run at the training centre is summed up. Since 1980 the Centre has been training personnel mainly for the Dukovany nuclear power plant. Recommendations are presented for training personnel for the Temelin nuclear power plant. (Z.M.)

Transport, acceptance, storage and handling of the itens of nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

The norm aiming to establish the requirements applied to workers or organizations which participate of the activities of transport, acceptance, storage and handling of important itens for safety of nuclear power plants, is presented. The established requirements treat of protection and control necessary to assure that the quality of important itens for safety be it preserved from the end of fabrication until their incorporation to nuclear power plant. (M.C.K.) [pt

Effects of radiation and apolipoprotein E on lipid profile among workers of nuclear power plants in Korea

International Nuclear Information System (INIS)

Ki-Eun Moon; Mee-Seon Jung; Suk-Hee Sung; Youn-Koun Chang; Il-Keun Park; Yun-Mi Paek; Tae-In Choi; Soo-Geun Kim

2007-01-01

Complete text of publication follows. Several studies reported that the radiation was positively related to fatty liver, low HDL cholesterol, and hypertriglyceridemia. Genetic polymorphism affect prevalence of chronic disease by molecular epidemiology studies. Apolipoprotein E is an important genetic determinant of cardiovascular disease (CVD), namely through its influence on lipid metabolism. Thus, we investigated whether radiation and apo E polymorphism, and environmental factors contribute to the lipid profile in workers of nuclear power plants in Korea. DNA was extracted from the whole blood of 6896 study subjects (6357 males and 359 females), and apo E polymorphism was investigated using PCR. Plasma lipid profiles were measured by standardized enzymatic procedures and radiation dose was measured by the thermoluminescence dosemeter (TLD). Environmental factors such as exercise, smoking were measured from health management database of KHNP. Total of 6802 subjects (aged 20-58) were investigated and radiation exposure dose was 168.51±463.94 mSv in the recent 1-year dose and 248.24±559.21 mSv in the total accumulative dose. In addition, Apo E polymorphism was associated with significant differences in total cholesterol, HDL cholesterol, radiation dose, AI but others no significant. The multiple regression model showed that total cholesterol was positively correlated with age, SBP, BMI, AI, fasting glucose. HDL cholesterol was negatively correlated with AI. LDL cholesterol was positively correlated with age, BMI, fasting glucose. And triglyceride was significantly correlated in the BMI, AI, somking dose, vegetables but others no significant. Metabolic syndrome did not show any relation to the others; only age, SBP, DBP, BMI, fasting glucose, HOMA-IR influenced. However, there was no significant association between radiation dose and lipid profile. In conclusion, Apo E and well-known variables such as SBP, BMI were significantly associated with lipid profile level

Lung Cancer Mortality among Uranium Gaseous Diffusion Plant Workers: A Cohort Study 1952–2004

Directory of Open Access Journals (Sweden)

LW Figgs

2013-07-01

Full Text Available Background: 9%–15% of all lung cancers are attributable to occupational exposures. Reports are disparate regarding elevated lung cancer mortality risk among workers employed at uranium gaseous diffusion plants. Objective: To investigate whether external radiation exposure is associated with lung cancer mortality risk among uranium gaseous diffusion workers. Methods: A cohort of 6820 nuclear industry workers employed from 1952 to 2003 at the Paducah uranium gaseous diffusion plant (PGDP was assembled. A job-specific exposure matrix (JEM was used to determine likely toxic metal exposure categories. In addition, radiation film badge dosimeters were used to monitor cumulative external ionizing radiation exposure. International Classification for Disease (ICD codes 9 and 10 were used to identify 147 lung cancer deaths. Logistic and proportional hazards regression were used to estimate lung cancer mortality risk. Results: Lung cancer mortality risk was elevated among workers who experienced external radiation >3.5 mrem and employment duration >12 years. Conclusion: Employees of uranium gaseous diffusion plants carry a higher risk of lung cancer mortality; the mortality is associated with increased radiation exposure and duration of employment.

Regulatory practices for nuclear power plants in India

International Nuclear Information System (INIS)

Bajaj, S.S.

2013-01-01

The Atomic Energy Regulatory Board (AERB) is the national authority for ensuring that the use of ionizing radiation and nuclear energy does not cause any undue risk to the health of workers, members of the public and to the environment. AERB is responsible for the stipulation and enforcement of rules and regulations pertaining to nuclear and radiological safety. This paper describes the regulatory process followed by AERB for ensuring the safety of nuclear power plants (NPPs) during their construction as well as operation. This regulatory process has been continuously evolving to cater to the new developments in reactor technology. Some of the recent initiatives taken by AERB in this direction are briefly described. Today, AERB faces new challenges like simultaneous review of a large number of new projects of diverse designs, a fast growing nuclear power program and functioning of operating plants in a competitive environment. This paper delineates how AERB is gearing up to meet these challenges in an effective manner. (author)

Trend analysis of cables failure events at nuclear power plants

International Nuclear Information System (INIS)

Fushimi, Yasuyuki

2007-01-01

In this study, 152 failure events related with cables at overseas nuclear power plants are selected from Nuclear Information Database, which is owned by The Institute of Nuclear Safety System, and these events are analyzed in view of occurrence, causal factor, and so on. And 15 failure events related with cables at domestic nuclear power plants are selected from Nuclear Information Archives, which is owned by JANTI, and these events are analyzed by the same manner. As a result of comparing both trends, it is revealed following; 1) A cable insulator failure rate is lower at domestic nuclear power plants than at foreign ones. It is thought that a deterioration diagnosis is performed broadly in Japan. 2) Many buried cables failure events have been occupied a significant portion of cables failure events during work activity at overseas plants, however none has been occurred at domestic plants. It is thought that sufficient survey is conducted before excavating activity in Japan. 3) A domestic age related cables failure rate in service is lower than the overseas one and domestic improper maintenance rate is higher than the overseas one. Maintenance worker' a skill improvement is expected in order to reduce improper maintenance. (author)

Development of bus duct inspection robot at nuclear power plant

International Nuclear Information System (INIS)

Hamada, Mamoru; Hoshi, Teruaki; Komura, Yoshinari

2017-01-01

Under the present situation, nuclear power plant has some places which are inspected with difficulty or not inspected due to narrowness or physical restriction, when carrying out periodical inspection. The subject of our research and development is to improve the accuracy of inspection and also to save labor (liberation from distress work of the worker) by applying a robot technology to the periodical inspection of the nuclear power plant. As a specific example, we report that developed robot can inspect inside the narrow space of Isolated Phase Bus ducts, which connect between a turbine generator and the main transformer. (author)

Clinical aspects of the health disturbances in Chernobyl Nuclear Power Plant accident clean-up workers (liquidators) from Latvia.

Science.gov (United States)

Eglite, M E; Zvagule, T J; Rainsford, K D; Reste, J D; Curbakova, E V; Kurjane, N N

2009-06-01

The health status of some 6,000 workers from Latvia who went to clean-up the Chernobyl Nuclear Power Plant (CNPP) site following the explosion on 26 April 1986 has been analyzed. The data on these workers have been recorded in the Latvian State Register of Occupational disease patients and people exposed to ionizing radiation due to Chernobyl NPP accident (Latvian State Register) that was established in 1994. From these data, estimates have been made of external ionizing radiation to which these workers were exposed together with observations on the impact of exposure to heavy metals (especially lead and zinc) and radioactive isotopes released during the reactor 'meltdown'. These factors along with psycho-emotional and social-economic stresses account for a marked excess of mortality and morbidity in the group of CNPP accident clean-up workers compared with that of the non-exposed normal Latvian population adjusted for age and sex. The number of diseases or conditions in the CNPP accident clean-up workers has progressively risen from an average of 1.3 in 1986 to 10.9 in 2007. This exceeds for the Latvian population when adjusted for age and sex. The most serious conditions affect the nervous, digestive, respiratory, cardiovascular, endocrine (especially thyroid) and immunological systems. While the morbidity associated with diseases of the respiratory and digestive systems has decreased in recent years that in the other systems is increasing. In recent years, there has been an increased occurrence of cancers affecting the thyroid, prostate and stomach. Clinical and laboratory investigations suggest that surviving CNPP accident clean-up workers exhibit signs of immuno-inflammatory reactions causing premature aging with evidence of autoimmune diseases and immunological deficiencies or abnormalities. It is suggested that the CNPP accident clean-up workers may have a specific syndrome, the 'Chernobyl post-radiation neurosomatic polypathy', due to sustained oxidant

Different aspects of safety in Nuclear Fuel Plant at Pitesti, Romania

International Nuclear Information System (INIS)

Ivana, T.; Epure, Gh.

2009-01-01

Nuclear Fuel Plant (FCN) is a facility that produces fuel bundles of CANDU-6 type for the CANDU nuclear power plant. Only natural and depleted uranium in bulk and itemized form are present as nuclear materials in this facility. Uranium and wastes from the plant are handled, processed, treated and stored throughout the entire facility. The nuclear materials with natural and depleted uranium are entirely under nuclear safeguards. The amount of uranium present in the plant in different forms and activities together with zircaloy, beryllium and other hazardous substances, wastes, explosive materials at high temperatures, etc. lead to special measures undertaken by Nuclear Safety Department (DNS) to ensure nuclear safety. Different aspects of safety are continuously monitored in the plant: operational safety, industrial safety, radiological safety, labour safety, informational safety. The emergency preparedness and response, physical protection and the security of the plant and of the transportation of radioactive materials are contributing to cover the multitude of safety aspects. The safety culture of workers built directly on the safety components completes this activity in the plant. In addition the aspects of safety, security and safeguards are in permanent synergy, parts of the three components being included in each other. In the future the policy of FCN will be focused so that any improvement of one of the safety components will be reflected in improving the other safety aspects. (authors)

Health protection and industrial safety. Nuclear power plants

International Nuclear Information System (INIS)

1987-03-01

The standard applies to primary circuit components including its auxiliary facilities, and of the secondary circuit of nuclear power plants with pressurized water reactors; to lifting gear and load take-ups for the transport of nuclear fuel and primary circuit components; to elevators within the containment, and to electrical installations. Part 3 specifies the behaviour of workers in conformity with safety provisions during operation, inspection, lifetime surveillance, functional testing, and maintenance. Special demands are made on the water regime and on elevators, lifting gear, and load take-ups

Qualification, certification and training systems of a Japanese nuclear power plant supplier

International Nuclear Information System (INIS)

Yoshijima, S.; Tomita, J.; Yoneda, Y.

1982-01-01

Training and indoctrination of personnel are very important for performing quality assurance activities in nuclear power plants. The paper presents policies, procedures and practices with regard to a training system for site construction workers, a training system for plant operation personnel at a special facility, and services and activities for operating plants. The training system for site workers and technicians offers basic training for all workers, and special training and qualification for field welders, cable-termination workers and non-destructive examination personnel. In addition to the qualification system for field welders applied by the regulatory body, a privat-company qualification system exists. Also, a training centre for BWR operators has been established. This facility has a simulator duplicating the main control room of an actual plant and a computer-assisted instruction system. Standard training courses, short-term basic courses, re-training courses, group training courses and special training courses are held at the training centre. Finally, the services and activities performed by Toshiba Corporation for operating plants are described. These activities of the plant supplier aim at keeping up and further enhancing the safety and reliability of operating plants and mainly consist of: (1) collection and evaluation of plant operation data, with re-evaluation and improvement of systems and components; (2) development of new maintenance techniques; (3) development of measures for reducing annual outage periods; and (4) plant emergency preparedness. (author)

Radiological protection in nuclear power plants

International Nuclear Information System (INIS)

Zorrilla R, S.

2008-12-01

This presentation sharing experiences which correspond to the nuclear power plant of Laguna Verde. This nuclear power plant is located at level 2 of four possible, in the classification performance of the World Association of Nuclear Operators (WANO), which means the mexican nuclear power plant is classified in terms of its performance indicators and above the average achieved by their counterparts americans and canadians. In the national context, the nuclear power plant of Laguna Verde has also been honored with several awards such as the National Quality Award, the Clean Industry Certificate, the distinction of Environmental Excellence and others of similar importance. For the standards of WANO, the basic idea is that there are shortcomings in one of nuclear power plant concern to all partners. The indicators used for the classification will always go beyond more compliance with regulations, which are assumed, and rather assume come or a path to excellence. Among the most important indicators are: the collective dose, the percentage of areas declared as contaminated, the number, type and tendency of contamination personal cases, the number of dosimetry alarms, the number of unplanned exposures, loss control of high radiation areas and the release of contaminated material outside the restricted areas. Furthermore, as already indicated, nuclear power plants are of special care situations, such as, carrying out work in areas with radiation fields of more than 15 mSv h -1 , the movement of spent fuel in the reload floor. The consideration of the minimum total effective dose equivalent as a criterion for prescribing tools that reduce exposures, but may increase the external cases of contaminated casualties, the experience in portals such as workers subject to radiology, where exposure in industrial radiography, and so on. Special mention deserve the conditions generated during fuel reload stops, which causes a massive personnel movement, working simultaneously on

Malignant pleural mesothelioma risk among nuclear workers: a review

International Nuclear Information System (INIS)

Metz-Flamant, C; Guseva Canu, I; Laurier, D

2011-01-01

Exposure to ionising radiation has been suggested as a causal risk factor for malignant pleural mesothelioma (MPM). Studies of patients treated by radiotherapy for primary cancers have suggested that radiation contributes to the development of secondary MPM. Here we examined the risk to nuclear workers of MPM related to exposure to low doses of occupational radiation at low dose rates. All results concerning MPM risk in published studies of nuclear workers were examined for their association with radiation exposure and potential confounders. We found 19 relevant studies. Elevated risks of pleural cancer were reported in most (15/17) of these studies. Eight reported risks higher for radiation monitored workers than for other workers. However, of 12 studies that looked at associations with ionising radiation, only one reported a significant dose-risk association. Asbestos was an important confounder in most studies. We conclude that studies of nuclear workers have not detected an association between ionising radiation exposure and MPM. Further investigations should improve the consideration of asbestos exposure at the same time as they address the risk of MPM related to occupational exposure of nuclear workers to low doses of ionising radiation at low dose rates. (review)

Malignant pleural mesothelioma risk among nuclear workers: a review

Energy Technology Data Exchange (ETDEWEB)

Metz-Flamant, C; Guseva Canu, I; Laurier, D, E-mail: camille.metz@irsn.fr [Laboratory of Epidemiology, Institute of Radiological Protection and Nuclear Safety (IRSN), Fontenay-aux-Roses (France)

2011-03-01

Exposure to ionising radiation has been suggested as a causal risk factor for malignant pleural mesothelioma (MPM). Studies of patients treated by radiotherapy for primary cancers have suggested that radiation contributes to the development of secondary MPM. Here we examined the risk to nuclear workers of MPM related to exposure to low doses of occupational radiation at low dose rates. All results concerning MPM risk in published studies of nuclear workers were examined for their association with radiation exposure and potential confounders. We found 19 relevant studies. Elevated risks of pleural cancer were reported in most (15/17) of these studies. Eight reported risks higher for radiation monitored workers than for other workers. However, of 12 studies that looked at associations with ionising radiation, only one reported a significant dose-risk association. Asbestos was an important confounder in most studies. We conclude that studies of nuclear workers have not detected an association between ionising radiation exposure and MPM. Further investigations should improve the consideration of asbestos exposure at the same time as they address the risk of MPM related to occupational exposure of nuclear workers to low doses of ionising radiation at low dose rates. (review)

Investigations on Health Conditions of Chernobyl Nuclear Power Plant Accident Recovery Workers from Latvia in Late Period after Disaster

Directory of Open Access Journals (Sweden)

Reste Jeļena

2016-10-01

Full Text Available The paper summarises the main findings on Chernobyl Nuclear Power Plant (CNPP accident recovery workers from Latvia and their health disturbances, which have been studied by the authors during the last two decades. Approximately 6000 persons from Latvia participated in CNPP clean-up works in 1986–1991. During their work period in Chernobyl they were exposed to external as well as to internal irradiation, but since their return to Latvia they were living in a relatively uncontaminated area. Regular careful medical examinations and clinical studies of CNPP clean-up workers have been conducted during the 25 years after disaster, gathering knowledge on radiation late effects. The aim of the present review is to summarise the most important information about Latvian CNPP clean-up worker health revealed by thorough follow-up and research conducted in the period of 25 years after the accident. This paper reviews data of the Latvian State Register of Persons Exposed to Radiation due to CNPP Accident and gives insight in main health effects found by the researchers from the Centre of Occupational and Radiological Medicine (Pauls Stradiņš Clinical University Hospital and Rīga Stradiņš University in a number of epidemiological, clinical, biochemical, immunological, and physiological studies. Latvian research data on health condition of CNPP clean-up workers in the late period after disaster indicate that ionising radiation might cause premature ageing and severe polymorbidity in humans.

Nuclear regulation. License renewal questions for nuclear plants need to be resolved

International Nuclear Information System (INIS)

Fultz, Keith O.; Kruslicky, Mary Ann; McDowell, William D. Jr.; Coleman, Robert L.

1989-04-01

A December 1986 pipe rupture at Virginia Power's Surry unit 2 nuclear power plant injured eight workers; four later died. As a result of this accident, Representative Edward J. Markey requested GAO to examine the Surry accident and assess the problems confronting aging nuclear plants. In March 1988 we reported our findings concerning the accident and a July 1987 incident at the Trojan nuclear plant in Oregon. This report addresses problems confronting aging nuclear plants by examining the Nuclear Regulatory Commission's (NRC) program to develop a license renewal policy and accompanying regulations, and the initiatives underway by the Department of Energy (DOE) and the electric utility industry to extend the operating lives of these plants. Nuclear power has become second only to coal as the largest producer of electricity in the United States. The 110 nuclear plants currently in service are operated by 54 utilities, provide about 20 percent of the nation's electricity, and represent a capital investment of over $200 billion. The Atomic Energy Act authorizes NRC to issue nuclear plant operating licenses for up to 40 years and provides for license extensions beyond the initial operating period. The act does not, however, stipulate the criteria for evaluating a utility request to operate a nuclear plant longer than 40 years. The oldest operating license currently in effect will expire in the year 2000. According to NRC, about one-half of the existing operating licenses will terminate by the year 2015, and most licenses will expire by about 2030. Many utilities will have to decide in the early 1990s whether to continue operating older nuclear plants or to construct new generating capacity. A clear understanding of the terms and conditions governing the license renewal process will be a key element in deciding how to meet future electricity demand. Although NRC has developed 3 possible license renewal policy options and identified 15 areas of regulatory uncertainty that

Investigation of bias in a study of nuclear shipyard workers

International Nuclear Information System (INIS)

Greenberg, E.R.; Rosner, B.; Hennekens, C.; Rinsky, R.; Colton, T.

1985-01-01

The authors examined discrepant findings between a 1978 proportional mortality study and a 1981 cohort study of workers at the Portsmouth, New Hampshire Naval Shipyard to determine whether the healthy worker effect, selection bias, or measurement bias could explain why only the proportional mortality study found excess cancer deaths among nuclear workers. Lower mortality from noncancer causes in nuclear workers (the healthy worker effect) partly accounted for the observed elevated cancer proportional mortality. More important, however, was measurement bias which occurred in the proportional mortality study when nuclear workers who had not died of cancer were misclassified as not being nuclear workers based on information from their next of kin, thereby, creating a spurious association. Although the proportional mortality study was based on a small sample of all deaths occuring in the cohort, selection bias did not contribute materially to the discrepant results for total cancer deaths. With regard to leukemia, misclassification of occupation in the proportional mortality study and disagreement about cause of death accounted for some of the reported excess deaths. 16 references, 4 tables

Development of small size wall decontamination robot systems in nuclear power plants

International Nuclear Information System (INIS)

Fujita, Tsuneaki; Takahashi, Tsuyosi

2004-01-01

This paper describes the development of wall decontamination robot systems for nuclear power plants. In nuclear power plants, it is required to reduce maintenance costs, including annual inspection, repairs and so on. Most of such maintenance activities are actually performed after decontamination processes are completed. In particular, the decontamination process of reactor wells is very important for reducing the radiation exposure of human workers. In the past, decontamination of reactor wells used to be done by extra large machine and tools, which caused long working hours and tiresome works. It was one of the reasons maintenance costs couldn't have been easily reduced. There are narrow spaces in the reactor wells that have to be decontaminated by human workers. In order to minimize the radiation exposure to humans, wall decontamination robot systems have been developed. The decontamination robots have rolled brushes and suction mechanisms and are capable of removing contaminants attached to the wall surface of the reactor wells. By making the robots smaller, it is possible to work in narrower spaces. In this paper, the effectiveness of decontamination by the developed robots is shown through experiments in the actual nuclear power plants. (author)

Planning of emergency medical treatment in nuclear power plant

International Nuclear Information System (INIS)

Kusama, Tomoko

1989-01-01

Medical staffs and health physicists have shown deep concerning at the emergency plans of nuclear power plants after the TMI nuclear accident. The most important and basic countermeasure for accidents was preparing appropriate and concrete organization and plans for treatment. We have planed emergency medical treatment for radiation workers in a nuclear power plant institute. The emergency medical treatment at institute consisted of two stages, that is on-site emergency treatment at facility medical service. In first step of planning in each stage, we selected and treatment at facility medical service. In first step of planning in each stage, we selected and analyzed all possible accidents in the institute and discussed on practical treatments for some possible accidents. The manuals of concrete procedure of emergency treatment for some accidents were prepared following discussion and facilities and equipment for medical treatment and decontamination were provided. All workers in the institute had periodical training and drilling of on-site emergency treatment and mastered technique of first aid. Decontamination and operation rooms were provided in the facillity medical service. The main functions at the facility medical service have been carried out by industrial nurses. Industrial nurses have been in close co-operation with radiation safety officers and medical doctors in regional hospital. (author)

Internet usage and knowledge of radiation health effects and preventive behaviours among workers in Fukushima after the Fukushima Daiichi nuclear power plant accident.

Science.gov (United States)

Kanda, Hideyuki; Takahashi, Kenzo; Sugaya, Nagisa; Mizushima, Shunsaku; Koyama, Kikuo

2014-10-01

The Fukushima Daiichi nuclear power plant accident (FDNPPA) was the world's second largest nuclear power plant accident. At the time that it occurred, internet usage prevalence in Japan was as high as 80%. To compare health knowledge on radiation and preventive behaviour between internet users and non-users among adults employed in industries in Fukushima after the nuclear disaster. We conducted a cross-sectional questionnaire study among adults employed in industries in Fukushima 3-5 months after the FDNPPA. Targets were 1394 regular workers who took part in health seminars provided by the Fukushima Occupational Health Promotion Center. After applying the selection criteria, there were 1119 eligible participants. The questionnaire asked for personal characteristics and main sources of information about the FDNPPA, as well as health knowledge on radiation and preventive behaviours following the nuclear accident. We assessed the contribution of each variable using logistic regression analysis. Among the eligible respondents, 637 workers (56.9%) were internet users and 482 (43.1%) were non-users. Internet users had more health knowledge than non-users (average 4.6 radiation-related health conditions in internet users vs 3.6 conditions in non-users) and more preventive behaviours (average 2.6 behaviours in internet users vs 1.9 in non-users). According to logistic regression analyses, internet usage was positively associated with greater health knowledge on radiation (OR 1.13; 95% CI 1.08 to 1.20) and more preventive behaviours (OR 1.14; 95% CI 1.07 to 1.23). Internet usage was significantly and positively associated with greater health knowledge and more preventive behaviours. The internet is a useful method of distributing information to the general public in emergency situations such as a nuclear disaster. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

Characterization of the temporary radiation workforce at US nuclear power plants

International Nuclear Information System (INIS)

Cehn, J.I.

1984-01-01

The temporary radiation worker is the subject of this recent study by the National Environmental Studies Project. ''Lenny'', an imaginary worker, is actually a composite of the estimated 22,000 radiation workers employed at various times at the 80 nuclear power plants in the U.S. Lenny reports to a trailer on the plant site to check in and spends the next day and a half in a training class that covers radiation safety, federal regulations and exposure limits and plant procedures. He must take and pass a written exam, then he fills out a medical history, indicating whether or not he has received any industrial radiation exposure. After three days of training and ''processing'' he dons a radiation measuring dosimeter and begins work. A key question to this study is whether the temporary employees are getting assigned the dirty work. It has been alleged that temps are used as ''glowboys'' or ''radiation sponges''. The new study finds no basis for this allegation. Data show that permanent plant staff received nearly the same average annual radiation dose as temporary employees

Some aspects of increasing the quality of personnel training for nuclear power plants in Czechoslovakia

International Nuclear Information System (INIS)

Jacko, J.; Frimmelova, A.

1989-01-01

Nuclear power plant personnel in Czechoslovakia is subject to periodical training in accordance with the Unified System of Nuclear Facility Personnel Training. This training is the responsibility of the Educational and Training Centre of the Nuclear Plant Research Institute in Trnava. Nuclear plant personnel is divided into 7 groups as follows: A - supervisory technical-administrative management staff; B - selected operating personnel such as shift supervisors, unit supervisors, reactor operators and secondary circuit operators; C - engineering-technical personnel of technical and maintenance departments; D - managing shift-operating staff; E - workers at technical plant departments; F - operational shift workers and servicemen; and G - maintenance personnel. These groups are respected in the training, which includes basic training, re-training and additional training. The basic training comprises 8 stages: general theoretical education; specialized theoretical education; on-the-job training in a plant designated for training; training on a simulator (group B); preparing for and taking final examinations for the certificate; doubling in the NPP designated for training (groups B, D, F); preparation in the NPP of future employment; preparing for and taking the state examination for obtaining the license (group B). Details of the management of the training process, experience gained during the implementation of the training and challenges for future improvement of the system are outlined. (P.A.)

Primary circuit contamination in nuclear power plants: contribution to occupational exposure

International Nuclear Information System (INIS)

Provens, H.

2002-01-01

In every country since the 80's, a clear downward trend is observed concerning the occupational doses at nuclear power plants, as shows the regularly decreasing annual collective dose per operating reactor. Even if technology and work management are improving, the reduction and the control of radiation sources remain one critical point. This paper summarizes the results of an extended study on the primary circuit contamination in nuclear power plants and its contribution to workers' exposure. The paper reviews the origin and mechanisms of radiation production and the different ways of radiation control or reduction based on physical and chemical parameters and not organisational or human factors. It underlines that chemistry control of the primary circuit is one essential component of radiation protection optimisation in nuclear power plants. Results reported come from scientific data in open literature and cannot be generalized to all the power plants

Cancer mortality risk of nuclear power workers due to the exposure of ionising radiation in Germany

International Nuclear Information System (INIS)

Fehringer, F.; Seitz, G.; Hammer, G.P.; Blettner, M.

2006-01-01

A cohort study of German nuclear power workers was set up to investigate overall and cancer mortality risk related to a chronic exposure to ionising radiation of low-level dose. The German study was performed as a part of an international study carried out by the International Agency for Research on Cancer (IARC), Lyon. First results of the international study have been published recently [1]. German data are not yet included in this analysis. The German cohort consists of 4844 employees from 10 nuclear power plants. All persons who worked in these nuclear power plants in 1991 or started employment between 1991 und 1997 are included (except for employees of one plant, whose observation period started in 1992). These persons accumulated about 31,000 person years. Overall, 68 deaths were observed in the observation period between 1.1.1991-31.12.1997. Standardized mortality ratios (SMR) were computed for all causes of death, all cancers, cardiovascular diseases, external causes, and all other causes. Overall, a strong healthy worker effect was observed (SMR=0.52 [95% CI: 0.41;0.67]). No increase in total cancer mortality was seen (SMR=0.85 [95% CI: 0.53;1.30]). However, numbers are too small for stable risk estimates and further effort is under way to complete the cohort in terms of power plants and to extend the follow-up until 2005. (authors)

Cancer mortality risk of nuclear power workers due to the exposure of ionising radiation in Germany

Energy Technology Data Exchange (ETDEWEB)

Fehringer, F.; Seitz, G. [Berufsgenossenschaft der Feinmechanik und Elektrotechnik, Koln (Germany); Hammer, G.P.; Blettner, M. [Johannes Gutenberg-Universitat Mainz, Institut fur Medizinische Biometrie, Epidemiologie und Informatik des Klinikums (Germany)

2006-07-01

A cohort study of German nuclear power workers was set up to investigate overall and cancer mortality risk related to a chronic exposure to ionising radiation of low-level dose. The German study was performed as a part of an international study carried out by the International Agency for Research on Cancer (IARC), Lyon. First results of the international study have been published recently [1]. German data are not yet included in this analysis. The German cohort consists of 4844 employees from 10 nuclear power plants. All persons who worked in these nuclear power plants in 1991 or started employment between 1991 und 1997 are included (except for employees of one plant, whose observation period started in 1992). These persons accumulated about 31,000 person years. Overall, 68 deaths were observed in the observation period between 1.1.1991-31.12.1997. Standardized mortality ratios (SMR) were computed for all causes of death, all cancers, cardiovascular diseases, external causes, and all other causes. Overall, a strong healthy worker effect was observed (SMR=0.52 [95% CI: 0.41;0.67]). No increase in total cancer mortality was seen (SMR=0.85 [95% CI: 0.53;1.30]). However, numbers are too small for stable risk estimates and further effort is under way to complete the cohort in terms of power plants and to extend the follow-up until 2005. (authors)

Effects of the accident at Three Mile Island on the mental health and behavioral responses of the general population and nuclear workers

International Nuclear Information System (INIS)

Fabrikant, J.I.

1983-02-01

On March 28, 1979, an accident occurred at the Three Mile Island nuclear power plant Unit No. 2 near Middletown, PA. A Presidential Commission was established to investigate the incident and was given the responsibility to evaluate the actual and potential impact of the events on the health and safety of the workers and the public. A main conclusion of the investigation was that the most serious health effect was severe, short-lived mental stress. This paper describes the study and the findings for four different study groups: (1) the general population of heads of households located within 20 miles of the plant; (2) mothers of preschool children from the same area; (3) teenagers in the 7th, 9th, and 11th grades from the area; and (4) nuclear workers employed at the Three Mile Island nuclear power plant

World Council of Nuclear Workers

International Nuclear Information System (INIS)

Maisseu, Andre

2007-01-01

WONUC is an association of Trade Unions, Scientific Societies and Social Organizations of the employees, workers and professionals of the nuclear energy related industries and technologies; integrated by 35 Countries and 1.8 millions members. This paper expose the products and services that WONUC provide for the promotion of peaceful uses of nuclear energy and the result of their work around all the world

Radiation doses and cause-specific mortality among workers at a nuclear materials fabrication plant

International Nuclear Information System (INIS)

Checkoway, H.; Pearce, N.; Crawford-Brown, D.J.; Cragle, D.L.

1988-01-01

A historical cohort mortality study was conducted among 6781 white male employees from a nuclear weapons materials fabrication plant for the years 1947-1979. Exposures of greatest concern are alpha and gamma radiation emanating primarily from insoluble uranium compounds. Among monitored workers, the mean cumulative alpha radiation dose to the lung was 8.21 rem, and the mean cumulative external whole body penetrating dose from gamma radiation was 0.96 rem. Relative to US white males, the cohort experienced mortality deficits from all causes combined, cardiovascular diseases, and from most site-specific cancers. Mortality excesses of lung and brain and central nervous system cancers were seen from comparisons with national and state rates. Dose-response trends were detected for lung cancer mortality with respect to cumulative alpha and gamma radiation, with the most pronounced trend occurring for gamma radiation among workers who received greater than or equal to 5 rem of alpha radiation. These trends diminished in magnitude when a 10-year latency assumption was applied. Under a zero-year latency assumption, the rate ratio for lung cancer mortality associated with joint exposure of greater than or equal to 5 versus less than 1 rem of both types of radiation is 4.60 (95% confidence limits (CL) 0.91, 23.35), while the corresponding result, assuming a 10-year latency, is 3.05 (95% CL 0.37, 24.83). While these rate ratios, which are based on three and one death, respectively, lack statistical precision, the observed dose-response trends indicate potential carcinogenic effects to the lung of relatively low-dose radiation. There are no dose-response trends for mortality from brain and central nervous system cancers

A quantitative and comparative evaluation of the risks from nuclear power plants

International Nuclear Information System (INIS)

Vignes, S.; Bertin, M.; Nenot, J.C.

1980-01-01

All the significant data for the assessment of risks from the operation of nuclear power plants was collected and these risks were compared with all the risks of modern life. The scientific bases for the evaluation of individual risks and detriment were defined by UNSCEAR (1977) and by ICRP 26 (1978). In different industries, the risk of death from long term occupational illness is about 130 to 14,000 per million workers. For accidental deaths, the risk is estimated at about 16 to 1,600. The risk for the nuclear industry is lower than 100 per million workers. Comparisons are made with different causes of lethality: deaths from atmospheric pollution (sulfur compounds and dusts) related to fossile fuel combustion; iatrogenic accidents attributed to some drugs used in medicine or to other kind of treatment; calculated mortality for workers exposed to asestosis. The nuclear industr of the safest. The only risk to be considered is the major accident, the probability of which is very low. (H.K.)

Evaluation of robotic inspection systems at nuclear power plants

International Nuclear Information System (INIS)

White, J.R.; Eversole, R.E.; Farnstrom, K.A.; Harvey, H.W.; Martin, H.L.

1984-03-01

This report presents and demonstrates a cost-effective approach for robotics application (CARA) to surveillance and inspection work in existing nuclear power plants. The CARA was developed by the Remote Technology Corporation to systematically determine the specific surveillance/inspection tasks, worker hazards, and access or equipment placement restraints in each of the many individual rooms or areas at a power plant. Guidelines for designing inspection robotics are included and are based upon the modular arrangement of commercially-available sensors and other components. Techniques for maximizing the cost effectiveness of robotics are emphasized in the report including: selection of low-cost robotic components, minimal installation work in plant areas, portable systems for common use in different areas, and standardized robotic modules. Factors considered as benefits are reduced radiation exposure, lower man-hours, shorter power outage, less waste material, and improved worker safety concerns. A partial demonstration of the CARA methodology to the Sequoyah (PWR) and Browns Ferry (BWR) Plants is provided in the report along with specific examples of robotic installations in high potential areas

Study on the improvement of working environment at night in maintenance works at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hiramoto, Mitsuru; Kotani, Fumio [Institute of Nuclear Safety System Inc., Seika, Kyoto (Japan)

2000-09-01

At the maintenance work site in nuclear power plants, due to the shortening (reduction of a regular inspection period) of the regular inspection period, the tendency toward working on around-the-clock basis has increased; thus, nighttime work is on the rise. Based upon research both locally and internationally, as well as examples of measures against such a tendency and the results of on-site surveys of the environment surrounding maintenance works at nuclear power plants, the author comprehensively studied the effects of nighttime work on workers, the measures to cope with the situation, and how a working environment for nighttime work should be. Based on the results, the authors made a guidebook for nighttime maintenance work at nuclear power plants. This guidebook, which deals with the subject of nighttime maintenance work at nuclear power plants, is quite unique in the world. It is expected that by using this guidebook, the quality of nighttime maintenance work and the levels of techniques/skills would be enhanced and maintained, and the safety of workers would be ensured, promoting considerably thus the establishment of a comfortable workplace. (author)

Study on the improvement of working environment at night in maintenance works at nuclear power plants

International Nuclear Information System (INIS)

Hiramoto, Mitsuru; Kotani, Fumio

2000-01-01

At the maintenance work site in nuclear power plants, due to the shortening (reduction of a regular inspection period) of the regular inspection period, the tendency toward working on around-the-clock basis has increased; thus, nighttime work is on the rise. Based upon research both locally and internationally, as well as examples of measures against such a tendency and the results of on-site surveys of the environment surrounding maintenance works at nuclear power plants, the author comprehensively studied the effects of nighttime work on workers, the measures to cope with the situation, and how a working environment for nighttime work should be. Based on the results, the authors made a guidebook for nighttime maintenance work at nuclear power plants. This guidebook, which deals with the subject of nighttime maintenance work at nuclear power plants, is quite unique in the world. It is expected that by using this guidebook, the quality of nighttime maintenance work and the levels of techniques/skills would be enhanced and maintained, and the safety of workers would be ensured, promoting considerably thus the establishment of a comfortable workplace. (author)

Fault Tree Analysis for an Inspection Robot in a Nuclear Power Plant

Science.gov (United States)

Ferguson, Thomas A.; Lu, Lixuan

2017-09-01

The life extension of current nuclear reactors has led to an increasing demand on inspection and maintenance of critical reactor components that are too expensive to replace. To reduce the exposure dosage to workers, robotics have become an attractive alternative as a preventative safety tool in nuclear power plants. It is crucial to understand the reliability of these robots in order to increase the veracity and confidence of their results. This study presents the Fault Tree (FT) analysis to a coolant outlet piper snake-arm inspection robot in a nuclear power plant. Fault trees were constructed for a qualitative analysis to determine the reliability of the robot. Insight on the applicability of fault tree methods for inspection robotics in the nuclear industry is gained through this investigation.

Consideration of Evaluation of Communication using Work Domain Analysis (WDA) in Nuclear Power Plants

International Nuclear Information System (INIS)

Jang, In Seok; Seong, Poong Hyun; Park, Jin Kyun

2009-01-01

The nature of work has changed, this corresponding to a trend toward to computerization. In this phase, the role of people began to evolve from one of manual laborer, requiring primarily perception-motor skill, to intellectual worker, thereby requiring more conceptual knowledge and cognitive skills which means system such as nuclear power plant are getting more complicated and complex. Thus, the evolution of work has led to a greater demand for communication, collaboration, problem solving thereby increasing the discretion, and therefore the variability, in worker action. Because of these reasons, traditional approaches, normative method and descriptive method, have not been proper anymore. Naikar points out that by focusing on constraints, rather than on particular ways of working, it is possible to support workers in adapting their behavior online and in real time in a variety of situation, including unanticipated events. For these complex domain such as communication in nuclear power plant control room, an approach is required that models the conditions framing formative behavior, allowing the examination of emergent, unanticipated, unpredicted actions. In this study, it could be helpful to introduce the method that is proper to apply in complex and unanticipated like nuclear power plants. Thus, Abstraction Decomposition Space (ADS) which is the tool of Work Domain Analysis(WDA) is presented as an approach that is particularly amenable for this domain. The aim is to address ADS as a beginning of modeling the structure of what need to be analyzed can be used to support the analysis of communication in nuclear power plants. If the model that is made by ADS is correct, quantitative evaluation of communication could be done

Certification of Canadian nuclear power plant personnel

International Nuclear Information System (INIS)

Newbury, F.

2014-01-01

The Canadian Nuclear Safety Commission (CNSC) regulates the use of nuclear energy and materials to protect health, safety, security of Canadians and the environment, and to implement Canada's international commitments on the peaceful use of nuclear energy. As part of its mandate, the CNSC requires certification of those who work in positions with direct impact on the safety of Canadian nuclear power plants (NPPs) and research reactors. Other positions, such as exposure device operators and radiation safety officers at other nuclear facilities, also require CNSC certification. In this paper, the certification process of Canadian NPP personnel will be examined. In keeping with the CNSC's regulatory philosophy and international practice, licensees bear the primary responsibility for the safe operation of their NPPs. They are therefore held entirely responsible for training and testing their workers, in accordance with applicable regulatory requirements, to ensure they are fully qualified to perform their duties. The CNSC obtains assurance that all persons it certifies are qualified to carry out their respective duties. It achieves this by overseeing a regime of licensee training programs and certification examinations, which are based on a combination of appropriate regulatory guidance and compliance activities. Reviews of the knowledge-based certification examination methodology and of lessons learned from Fukushima have generated initiatives to further strengthen the CNSC's certification programs for NPP workers. Two of those initiatives are discussed in this paper. (author)

An influence of occupational exposure on level of chromosome aberrations in nuclear power plant workers

International Nuclear Information System (INIS)

Birute Griciene; Grazina Slapsyte

2007-01-01

Complete text of publication follows. Objective. The workers of Ignalina Nuclear Power Plant (INPP) receive the highest occupational ionising radiation doses in Lithuania. Their occupational exposure results mainly from external low LET gamma radiation. Some workers receive additional internal and neutron exposure. Though exposure doses are generally low and don't exceed the annual dose limit, the higher doses are obtained during outages. The aim of the present study was to analyse chromosome aberration frequencies in lymphocytes of INPP workers exposed to the different types of ionising radiation. Methods. The blood sampling of 52 INPP male workers was performed in 2004-2006. For 29 workers radiation exposure resulted from the external gamma rays only. Their mean annual dose averaged over the 3-year period prior blood sampling was 11.7±8.7 mSv. The mean cumulative dose - 197.7±174.7 mSv. 15 workers had an intake of gamma radionuclides ( 60 Co, 137 Cs), contributing to the doses less than 0.1 mSv. Their mean cumulative dose - 278.2±191.9 mSv. The mean annual dose averaged over the 3-year period prior blood sampling was 11.8±5.3 mSv. For 8 subjects neutron doses below 0.2 mSv were recorded. Their mean annual dose averaged over the 3-year period prior blood sampling was 7.0±2.9 mSv. The mean cumulative dose was 241.8±93.0 mSv. Heparinized venous blood samples were taken and cultures were initiated according to the standard procedures. Phytohaemagglutinin (7.8 μg/ml) stimulated cultures were incubated at 37degC for 72 hours in RPMI 1640 medium supplemented with 12% heat-inactivated newborn calf serum, 40 μg/ml gentamycin. Colchicine was added to the culture during the initiation at a final concentration of 0,25 μg/ml. The harvested lymphocytes were treated with hypotonic KCl (0,075 M) and then fixed in methanol-glacial acetic acid (3:1). Flame-dried slides were stained with Giemsa, coded and scored blind. Generally 500 first-division cells per individual were

Worker Alienation and Compensation at the Savannah River Site.

Science.gov (United States)

Ashwood, Loka; Wing, Steve

2016-05-01

Corporations operating U.S. nuclear weapons plants for the federal government began tracking occupational exposures to ionizing radiation in 1943. However, workers, scholars, and policy makers have questioned the accuracy and completeness of radiation monitoring and its capacity to provide a basis for workers' compensation. We use interviews to explore the limitations of broad-scale, corporate epidemiological surveillance through worker accounts from the Savannah River Site nuclear weapons plant. Interviewees report inadequate monitoring, overbearing surveillance, limited venues to access medical support and exposure records, and administrative failure to report radiation and other exposures at the plant. The alienation of workers from their records and toil is relevant to worker compensation programs and the accuracy of radiation dose measurements used in epidemiologic studies of occupational radiation exposures at the Savannah River Site and other weapons plants. © The Author(s) 2016.

Nuclear power plants

International Nuclear Information System (INIS)

Margulova, T.Ch.

1976-01-01

The textbook focuses on the technology and the operating characteristics of nuclear power plants equiped with pressurized water or boiling water reactors, which are in operation all over the world at present. The following topics are dealt with in relation to the complete plant and to economics: distribution and consumption of electric and thermal energy, types and equipment of nuclear power plants, chemical processes and material balance, economical characteristics concerning heat and energy, regenerative preheating of feed water, degassing and condenser systems, water supply, evaporators, district heating systems, steam generating systems and turbines, coolant loops and pipes, plant siting, ventilation and decontamination systems, reactor operation and management, heat transfer including its calculation, design of reactor buildings, and nuclear power plants with gas or sodium cooled reactors. Numerous technical data of modern Soviet nuclear power plants are included. The book is of interest to graduate and post-graduate students in the field of nuclear engineering as well as to nuclear engineers

Job creation, heterogeneous workers and technical change : matched worker/plant data : evidence from Norway

OpenAIRE

Salvanes, Kjell G.; Førre, Svein Erik

2001-01-01

Abstract: Using matched worker/plant level data for Norway, theories explaining the change in skill composition are assessed using direct evidence on the job creation and destruction for high, medium and low skilled workers. Skill based job creation is analysed in detail for plants in a high-skill service sector and in low- and high-tech manufacturing sectors. Given a compressed wage structure in Norway and increased supply of high skilled workers, the supply of skills may also explain the...

Staffing, recruitment, training, qualification and certification of operating personnel of nuclear power plants

International Nuclear Information System (INIS)

1999-10-01

Safety of public, occupational workers and the protection of environment should be assured while activities for economic and social progress are pursued. These activities include the establishment and utilisation of nuclear facilities and the use of radioactive sources. This safety guide provides guidance on the aspects of staffing, recruitment, training, qualification and certification of operating personnel of nuclear power plants

Comparative study T-type and I-type layout of PWR nuclear power plants

International Nuclear Information System (INIS)

Eko Rudi Iswanto and Siti Alimah

2010-01-01

Determining plant layout is one of the five major stages during the life time of a nuclear power plant. Some important factors that affect in the selecting of plant layout are availability of infrastructure, economic aspects, social aspects, public and environment safety, and also easy to do. Another factor to be considered is requirements as seismic design, which refers to the principles of good security workers, communities and the environment of radiological risks. There are many layout types of nuclear power plant, two of them are T-type layout and I-type layout. Each type of the plant layout has advantage and disadvantage, therefore this study is to understand them. Good layout is able to provide a high level of security against earthquakes. In term of earthquake design, I-type layout has a higher security level than T-type layout. Therefore, I-type layout can be a good choice for PWR nuclear power plants 1000 MWe that will be built in Indonesia. (author)

Monitoring of exposure to selected metals in workers of a ferroalloy production plant using NAA and PIXE

International Nuclear Information System (INIS)

Kucera, J.; Havranek, V.; Hnatowicz, V.; Bencko, V.; Fabianova, E.; Sysalova, J.

1998-01-01

Advantages and pitfalls of direct and biological monitoring of occupational exposure are briefly mentioned and a project aimed at evaluating exposure to chromium (and possibly manganese) in workers of a ferro-alloy production plant using both the above approaches is outlined. Facilities for NAA and PIXE at the Nuclear Physics Institute at Rez to be used in the project are described. Results of quality assurance of INAA method for analysis of workplace air born particulate matter and blood sampling are presented. Results from previous work relating to this Co-ordinated Research Programme - studying exposure of workers of a vanadium pentoxide production plant are also briefly reviewed. (author)

Analysis of changed bio-signal to radiation exposure of nuclear medicine worker

International Nuclear Information System (INIS)

Lee, Hwun Jae; Lee, Sang Bock

2007-01-01

In this paper, we are evaluated about bio-signal between general workers and nuclear medicine workers which is more radiation exposure relatively. In order to reciprocal evaluated two group, we experimented nuclear medicine workers in Chung-Buk National University Hospital at department of nuclear medicine and worker in Chon-Nam National University Hospital at CT room, general radiographic room, medical recording room, receipt room, general office room. Used of experimental equipments as follows, for a level of radiation measurement by pocket dosimeter which made by Arrow-Tech company, for heart rate and blood pressure measurement by TONOPORT V which made by GE medical systems company, for heat flux and skin temperature and energy expenditure measurement by Armband senseware 2000 which made by Bodymedia company. Result of experiment obtains as follows : 1) Individual radiation exposure is recorded 3.05 uSv at department of nuclear medicine and order as follows CT room, general radiograpic room, medical recording room, receipt room, general office room. Department of nuclear medicine more 1.5 times than other places. 2) Radiation accumulated dose is not related to Heat flux, Skin temperature, Energy expenditure. 3) Blood pressure is recorded equal to nuclear medical workers, general officer, general people about systolic blood pressure and diastolic blood pressure. Compared to blood pressure between nuclear medical works which is more radiation exposure and other workers was not changed. Consequently, more radiation exposed workers at nuclear medicine field doesn't have hazard

Forecasting manpower requirements for nuclear power plant construction

International Nuclear Information System (INIS)

Seltzer, N.; Schriver, W.R.

1978-01-01

This paper presents both the methodology and results of a segment of a comprehensive construction manpower demand forecasting system aimed at forecasting virtually all construction manpower requirements in the United States of America. The part of the system dealing with the demand for construction workers needed to build nuclear powered electricity generating plants is discussed here. The object of the system is to forecast manpower construction needs for each of 29 construction crafts on a monthly basis in each of 10 geographical regions of the United States. The method used is to establish profiles of the types of workers and time phasing required in the past. Profiling was done for different types of plants, different capacity classes, and different geographical locations. An appropriate worker profile matrix cannot simply be multiplied by the capacity of the proposed plant if the number of man-hours required per kilowatt of generating capacity is not constant. The value of this latter variable has changed considerably recently - presumably because of an increased awareness of environmental and safety considerations. Econometric techniques are used to forecast values for man-hours per kilowatt which are then multiplied by projected new capacity to be put in place. The resulting total man-hour requirement is then allocated over time and by craft through use of a worker profile matrix. The summary results indicate that 20 percent increases in man-hours required per kilowatt of capacity can be expected between 1977 and 1981. Total construction labour demand will rise from 65,700 work-years in 1977 to nearly 96,600 work-years in 1981. Forecasts of the actual number of different types of workers to be demanded in each month and in each region are available from the system. (author)

Proposal and field practice of a 'hiyarihatto' activity method for promotion of statements of participants for nuclear power plant organization

International Nuclear Information System (INIS)

Aoyagi, Saizo; Fujino, Hidenori; Ishii, Hirotake; Shimoda, Hiroshi; Sakuda, Hiroshi; Yoshikawa, Hidekazu; Sugiman, Toshio

2011-01-01

In a 'hiyarihatto' activity, workers report and discuss incident cases related to their work. Such an activity is particularly effective for cultivating participants' attitudes about safety. Nevertheless, a conventional face-to-face hiyarihatto activity includes features that are inappropriate for conduct in a nuclear power plant organization. For example, workers at nuclear power plants are geographically distributed and busy. Therefore, they have great difficulty in participating in a face-to-face hiyarihatto activity. Furthermore, workers' hesitation in discussing problems inhibits the continuation of their active participation. This study is conducted to propose a hiyarihatto activity with an asynchronous and distributed computer-mediated communication (CMC) for a nuclear power plant organization, with the demonstration of its effectiveness through field practice. The proposed method also involves the introduction of special participants who follow action guidelines for the promotion of the continuation of the activity. The method was used in an actual nuclear power plant organization. Results showed that the method is effective under some conditions, such as during periods without facility inspection. Special participants promoted the activity in some cases. Moreover, other factors affecting the activity and some improvements were identified. (author)

Manpower requirements of quality assurance personnel for the nuclear power plants

International Nuclear Information System (INIS)

Aly, A.E.; El-sayed, A.A.; Shabaan, I.H.

1987-01-01

Basic principles for structuring and staffing of the quality assurance (Q.A.)organisation in the nuclear power plant (NPP) are presented. the manpower requirements of the Q.A.organisation in the NPP during both construction and operational stages are determined. the manpower requirements for Q.A./Q.C. functions in a NPP are found to be proportional to the number of craft workers needed to perform the required level of the construction. The Q.A./Q.C. personnel are about 15% of the total number of the craft workers required during construction

Exploratory study of the radiation-protection training programs in nuclear power plants

International Nuclear Information System (INIS)

Fields, C.D.

1982-06-01

The objective of the study was to examine current radiation training programs at a sample of utilities operating nuclear reactors and to evaluate employee information on radiation health. The study addressed three elements: (1) employee perceptions and understanding of ionizing radiation; (2) utility trainers-their background, training, and problems; (3) the content, materials, and conduct of training programs; (4) program uniformity and completeness. These areas were examined through visits to utilities, surveys, and employee interviews. The programs reviewed were developed by utility personnel who have backgrounds, for the most part, in health physics but who may have little formal training in adult education. This orientation, coupled with the inherent nature of the subject, has produced training programs that appear to be too technical to achieve the educational job intended. The average nuclear power plant worker does not have the level of sophistication needed to understand some of the information. It became apparent that nuclear power plant workers have concerns that do not necessarily reflect those of the scientific community. Many of these result from misunderstandings about radiation. Unfortunately, the training programs do not always address these unfounded but very real fears

Results of comparative assessment of US and foreign nuclear power plant dose experience and dose reduction programs

International Nuclear Information System (INIS)

Baum, J.W.; Horan, J.R.; Dionne, B.J.

1985-01-01

The objectives of this study were to determine how collective dose equivalents at US nuclear power plants compare to those of other technically advanced countries, and to evaluate factors that contribute to the differences. Fifty Health Physicists and nuclear engineers from 10 countries met at BNL May 29 - June 1, 1984 to exchange information and hold discussions on ''Historical Dose Experience and Dose Reduction (ALARA) at Nuclear Power Plants''. Results of evaluation of data from this meeting and other data from recent publications are summarized. Based on data evaluated to date it is clear that US plants have higher collective dose equivalents per reactor and per MW-yr generated than most other countries. Factors which contribute to low doses include: 1) minimization of cobalt in primary system components exposed to water, 2) careful control of primary system oxygen and pH, 3) good primary system water purity to minimize corrosion product formation, 4) careful plant design, layout and component segregation and shielding, 5) management interest and commitment, 6) minimum number of workers and in-depth worker training, 7) use of special tools, and 8) plant standardization

Thyroid disorders in employees of a nuclear power plant

International Nuclear Information System (INIS)

Kindler, Stefan; Volzke, Henry

2005-01-01

Full text: Aim of the Study: The thyroid gland is a potential target organ for radiation-related damage. The aim of this analysis was to investigate the association between occupational exposure to ionizing radiation and the risk of autoimmune thyroid disease (AITD) in workers of a former nuclear power station. Methods: Seventy-one male power station workers aged 38 to 57 years who were exposed to a life time dose in the upper allowed limit (70-400 m Sv) were compared to two random samples of male persons, who were not exposed to occupational radiation. Both samples were selected from the data set of the population-based Study of Health in Pomerania. Thyroid ultrasonography was performed by the same observers. Laboratory parameters for the study groups were analyzed in a central laboratory. Results: The power station workers with occupational exposure to radiation were more educated than the subjects of the two control groups. The exposed were less often current smokers, but more often never smokers compared to the control groups. After controlling analyses for age and further relevant confounders no significant differences between exposed and controls with respect to thyroid disorders were detected. Conclusion: We conclude that workers of a nuclear power plant with an exposure to ionizing radiation within the upper allowed limit have no increased risk of thyroid disorders. This may at least in part be explained by a healthy worker effect. (author)

Development of experimental method to simulate the corrosion products in the primary system of nuclear power plant

International Nuclear Information System (INIS)

Kim, Sang Hyun; Kim, In Sup; Jang, Chang Heui

2005-01-01

Corrosion products are recognized as one of the major sources of occupational radiation exposure for nuclear power plant workers. Numerous studies have been conducted on the primary water chemistry to reduce the amount of crud in the primary circuit to avoid the radioactivity build-up in the plant. However, experiments with crud are restricted in laboratory because the crud is highly radioactive material. The objective of this study is to develop the simulating method of corrosion product in nuclear power plant

Radiological protection in nuclear power plants; La proteccion radiologica en las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Zorrilla R, S. [CFE. Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)

2008-12-15

This presentation sharing experiences which correspond to the nuclear power plant of Laguna Verde. This nuclear power plant is located at level 2 of four possible, in the classification performance of the World Association of Nuclear Operators (WANO), which means the mexican nuclear power plant is classified in terms of its performance indicators and above the average achieved by their counterparts americans and canadians. In the national context, the nuclear power plant of Laguna Verde has also been honored with several awards such as the National Quality Award, the Clean Industry Certificate, the distinction of Environmental Excellence and others of similar importance. For the standards of WANO, the basic idea is that there are shortcomings in one of nuclear power plant concern to all partners. The indicators used for the classification will always go beyond more compliance with regulations, which are assumed, and rather assume come or a path to excellence. Among the most important indicators are: the collective dose, the percentage of areas declared as contaminated, the number, type and tendency of contamination personal cases, the number of dosimetry alarms, the number of unplanned exposures, loss control of high radiation areas and the release of contaminated material outside the restricted areas. Furthermore, as already indicated, nuclear power plants are of special care situations, such as, carrying out work in areas with radiation fields of more than 15 mSv h{sup -1}, the movement of spent fuel in the reload floor. The consideration of the minimum total effective dose equivalent as a criterion for prescribing tools that reduce exposures, but may increase the external cases of contaminated casualties, the experience in portals such as workers subject to radiology, where exposure in industrial radiography, and so on. Special mention deserve the conditions generated during fuel reload stops, which causes a massive personnel movement, working simultaneously on

Second analysis of mortality of nuclear industry workers in Japan, 1986-1997

International Nuclear Information System (INIS)

Ohshima, Sumio; Murata, Motoi

2001-01-01

This article is a commentary concerning the second report of the study in the title committed by the Science and Technology Agency (the present Ministry of Education, Culture, Sports, Science and Technology) to Radiation Effects Association. The study is an epidemiological one as for the relationships between long-term low dose radiation and its health effects in workers of nuclear industry like nuclear power plant and uses the cohort methodology for the factor (exposure dose) and diseases (mortality). In about 244,000 personnel, mortality was calculated from obtainable 179,000 resident cards of object males. For those died during the study period, cause of death was checked with the card for the movement of population (Ministry of Health, Labor and Welfare). The exposure dose was checked with the dose records of radiation workers stored in the registration center. Analysis results of standardized mortality ratio (comparison of mortality of the objects and non-object Japanese males) and of correlation of integrated dose and mortality gave no clear evidence that the low dose radiation exposure affects the mortality due to cancer. (K.H.)

Occupational exposures at nuclear power plants. Fourteenth annual report of the ISOE programme, 2004

International Nuclear Information System (INIS)

2006-01-01

The ISOE Programme was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from 478 operating and shutdown commercial nuclear power plants participating in the programme (representing some 90% of the world's total operating commercial reactors). The Fourteenth Annual Report of the ISOE Programme summarises achievements made during 2004 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

Occupational exposures at nuclear power plants. Eleventh annual report of the Isoe programme, 2001

International Nuclear Information System (INIS)

2002-01-01

The ISOE Programme was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from the 452 commercial nuclear power plants participating in the programme (representing some 90 per cent of the world's total operating commercial reactors). The Eleventh Annual Report of the ISOE Programme summarises achievements made during 2001 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

Data base on nuclear power plant dose reduction research projects

Energy Technology Data Exchange (ETDEWEB)

Khan, T.A.; Baum, J.W.

1986-10-01

Staff at the ALARA Center of Brookhaven National Laboratory have established a data base of information about current research that is likely to result in lower radiation doses to workers. The data base, concerned primarily with nuclear power generation, is part of a project that the ALARA Center is carrying out for the Nuclear Regulatory Commission. This report describes its current status. A substantial amount of research on reducing occupational exposure is being done in the US and abroad. This research is beginning to have an impact on the collective dose expenditures at nuclear power plants. The collective radiation doses in Europe, Japan, and North America all show downward trends. A large part of the research in the US is either sponsored by the nuclear industry through joint industry organizations such as EPRI and ESEERCO or is done by individual corporations. There is also significant participation by smaller companies. The main emphasis of the research on dose reduction is on engineering approaches aimed at reducing radiation fields or keeping people out of high-exposure areas by using robotics. Effective ALARA programs are also underway at a large number of nuclear plants. Additional attention should be given to non-engineering approaches to dose reduction, which are potentially very useful and cost effective but require quantitative study and analysis based on data from nuclear power plants. 9 refs., 1 fig.

Licensing Process for Nuclear Power Plants in Pakistan and its comparison with other Countries

International Nuclear Information System (INIS)

Iqbal, Javed; Choi, Kwang Sik

2012-01-01

Pakistan Nuclear Regulatory Authority (PNRA) was established in January 2001 with the promulgation of the Ordinance, No-III of 2001. Pakistan is one of the countries in the world who intend to expand its nuclear power program for energy generation upto 8800 MWe by 2030. Presently, there are two research reactors and three nuclear power plants in operation and two power plants are under various stages of construction which are expected to be in commercial operation in 2016. It is obvious that the primary responsibility of ensuring safety of nuclear power plants (NPPs) operation rests with the Pakistan Atomic Energy Commission (PAEC). However, PNRA's prime mission is to ensure the safe operation of nuclear and radiation facilities, safe use of radioactive sources and protection of the radiation workers, general public and the environment from the harmful hazards of radiation by formulating and implementing effective regulations. Pakistan Nuclear Regulatory Authority issues authorizations for nuclear power plants in three stages i.e. site permit, construction license and operation license after detailed safety review. This paper presents the licensing process for NPPs in Pakistan and its comparison with SSG-12, USA and Finland

Development of automatic pipe welder for nuclear power plant

International Nuclear Information System (INIS)

Iwamoto, Taro; Ando, Shimon; Omae, Tsutomu; Ito, Yoshitoshi; Araya, Takeshi.

1978-01-01

Numerous pipings are installed in nuclear power plants, and of course, the reliability of these pipings are very important to preserve the safety of the plants. These pipings undergo periodic inspection yearly, and when some defects are found or some reconstructions to superior systems are made, field welding in the plants is required. When the places to be welded are in containment vessels, the works must be carried out in radiation environment. In order to maintain the highest quality of welding and to reduce the radiation exposure of workers, many skilled workers are required. This automatic pipe welder was developed to solve these problems, aiming at carrying out welding works by remote control at the safe places outside containment vessels. Especially in order to obtain the highest quality of welding, it was not perfectly automated, but the man-machine system so as to enable to utilize the delicate sense of workers was adopted. The visual and contact detecting systems to monitor welding works, remote control system, computer control, light, small and easily installed welding head, grinding and supersonic flow detecting equipments, the power source of transistor switching type, air cooling equipment, and the function for setting welding conditions according to algorithm were added to the welding machine. The outline and main components of this automatic pipe welder are explained. (Kako, I.)

Half-century archives of occupational medical data on French nuclear workers: a dusty warehouse or gold mine for epidemiological research?

Science.gov (United States)

Garsi, Jerome-Philippe; Samson, Eric; Chablais, Laetitia; Zhivin, Sergey; Niogret, Christine; Laurier, Dominique; Guseva Canu, Irina

2014-12-01

This article discusses the availability and completeness of medical data on workers from the AREVA NC Pierrelatte nuclear plant and their possible use in epidemiological research on cardiovascular and metabolic disorders related to internal exposure to uranium. We created a computer database from files on 394 eligible workers included in an ongoing nested case-control study from a larger cohort of 2897 French nuclear workers. For each worker, we collected records of previous employment, job positions, job descriptions, medical visits, and blood test results from medical history. The dataset counts 9,471 medical examinations and 12,735 blood test results. For almost all of the parameters relevant for research on cardiovascular risk, data completeness and availability is over 90%, but it varies with time and improves in the latest time period. In the absence of biobanks, collecting and computerising available good-quality occupational medicine archive data constitutes a valuable alternative for epidemiological and aetiological research in occupational health. Biobanks rarely contain biological samples over an entire worker's carrier and medical data from nuclear industry archives might make up for unavailable biomarkers that could provide information on cardiovascular and metabolic diseases.

Feasibility study on mental healthcare using indoor plants for office workers

Science.gov (United States)

Kubota, Tsuyoshi; Matsumoto, Hiroshi; Genjo, Kaori; Nakano, Takaoki

2017-10-01

In recent years, it has become a problem that office workers' stresses affect their intellectual productivity. As one of strategies mitigating the stress while working, many studies on the effect of indoor plants introduced into the office have been conducted. The psychological and physiological effects of indoor plants have been expected to mitigate the office workers' stresses. Also, the effects of green amenities such as improvement of productivity, control of the indoor thermal environment, relaxation and recovery of visual fatigue, and improvement of air quality have been expected. In this study, a field investigation on the green amenity effects of indoor plants on office workers' psychological and physiological responses in an actual office was conducted and discussed. This paper describes the measurement results of the physical environment and workers' psychological and physiological responses under the condition with shelves installed with indoor plants in an office room. It was suggested that indoor plants such as mint, basil and begonia, and a combination of red and green plants were effective for mitigating worker's stresses.

Nuclear power. Volume 1. Nuclear power plant design

International Nuclear Information System (INIS)

Pedersen, E.S.

1978-01-01

NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 1 contains the following chapters; (1) nuclear reactor theory; (2) nuclear reactor design; (3) types of nuclear power plants; (4) licensing requirements; (5) shielding and personnel exposure; (6) containment and structural design; (7) main steam and turbine cycles; (8) plant electrical system; (9) plant instrumentation and control systems; (10) radioactive waste disposal (waste management) and (11) conclusion

Initial examination of the effects of overtime and shift scheduling on nuclear power plant safety performance

International Nuclear Information System (INIS)

Baker, K.; Olson, J.; Montgomery, J.

1990-01-01

The research reported here uses currently available data to begin to document overtime and shift scheduling practices in the nuclear industry and assess their safety consequences. Overtime and the 12-hour shift schedule have been found to affect employee fatigue and human error in other industries but neither of these practices have been systematically researched within the nuclear industry. Overtime has long been a standard practice in the nuclear industry and, recently, several licensees have adopted a 12-hour shift schedule for control room operations crews. Although 12-hour shifts have certain benefits for the employer and employee alike (e.g., can require fewer total employees and provide longer periods of time-off) there is some concern that the 12-hour shift may produce greater employee fatigue. Moreover, the 12-hour shift may exacerbate the negative effect of overtime. The potential effect of human error in the nuclear industry for the health and safety of both nuclear power plant workers and the general public requires that these practices be assessed. Data on overtime practices was obtained from the International Brotherhood of Electrical Workers (IBEW) for plants covered by the bargaining unit - approximately 63% of the total number of operating plants. Information on operator shift schedule was collected from all operating plants in 1987 by the NRC. The research produced fairly strong evidence that greater amounts of overtime worked by operators is associated with a greater number of operational problems

System model for evaluation of an emergency response plan for a nuclear power plant based on an assessment of nuclear emergency exercises

International Nuclear Information System (INIS)

Silva, Marcos Vinicius C.; Medeiros, Jose A.C.C.

2011-01-01

Nuclear power plants are designed and built with systems dedicated to provide a high degree of protection to its workers, the population living in their neighborhoods and the environment. Among the requirements for ensuring safety there are the existence of the nuclear emergency plan. Due to the relationship between the actions contemplated in the emergency plan and the nuclear emergency exercise, it becomes possible to assess the quality of the nuclear emergency plan, by means of emergency exercise evaluation, The techniques used in this work aim at improving the evaluation method of a nuclear emergency exercise through the use of performance indicators in the evaluation of the structures, actions and procedures involved. The proposed model enables comparisons between different moments of an emergency plan directed to a nuclear power plant as well as comparisons between plans dedicated to different facilities. (author)

System model for evaluation of an emergency response plan for a nuclear power plant based on an assessment of nuclear emergency exercises

Energy Technology Data Exchange (ETDEWEB)

Silva, Marcos Vinicius C.; Medeiros, Jose A.C.C. [Universidade Federal do Rio de Janeiro (PEN/COPPE/UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia. Programa de Engenharia Nuclear

2011-07-01

Nuclear power plants are designed and built with systems dedicated to provide a high degree of protection to its workers, the population living in their neighborhoods and the environment. Among the requirements for ensuring safety there are the existence of the nuclear emergency plan. Due to the relationship between the actions contemplated in the emergency plan and the nuclear emergency exercise, it becomes possible to assess the quality of the nuclear emergency plan, by means of emergency exercise evaluation, The techniques used in this work aim at improving the evaluation method of a nuclear emergency exercise through the use of performance indicators in the evaluation of the structures, actions and procedures involved. The proposed model enables comparisons between different moments of an emergency plan directed to a nuclear power plant as well as comparisons between plans dedicated to different facilities. (author)

Linking empowering leadership to safety participation in nuclear power plants: a structural equation model.

Science.gov (United States)

Martínez-Córcoles, Mario; Schöbel, Markus; Gracia, Francisco J; Tomás, Inés; Peiró, José M

2012-07-01

Safety participation is of paramount importance in guaranteeing the safe running of nuclear power plants. The present study examined the effects of empowering leadership on safety participation. Based on a sample of 495 employees from two Spanish nuclear power plants, structural equation modeling showed that empowering leadership has a significant relationship with safety participation, which is mediated by collaborative team learning. In addition, the results revealed that the relationship between empowering leadership and collaborative learning is partially mediated by the promotion of dialogue and open communication. The implications of these findings for safety research and their practical applications are outlined. An empowering leadership style enhances workers' safety performance, particularly safety participation behaviors. Safety participation is recommended to detect possible rule inconsistencies or misunderstood procedures and make workers aware of critical safety information and issues. Crown Copyright © 2012. Published by Elsevier Ltd. All rights reserved.

Developing positive worker attitudes toward radiation protection

International Nuclear Information System (INIS)

Millis, N.L.

1987-01-01

Teamwork, productivity, and reducing exposure are admirable goals presented to the workers in a nuclear power plant. A common thread to achievement in these areas resides in worker attitudes toward the tasks presented. A positive, alert, and cooperative attitude is an element in a worker's mind that must be created and maintained by good leadership and management practices. At the Calvert Cliffs Nuclear Power Plant, management has used certain strategies to foster good positive worker attitudes toward radiation protection and quality workmanship in all tasks. Strategies differ from management by objectives in that they have no deadlines or timetables in and of themselves. Rather, strategies are preplanned methods that can be called upon when the opportunity arises to improve worker attitudes. A series of five strategies for positive attitude development are described in the full paper. The strategies are identified with buzz words to allow the user a recall mechanism (as with the acronyms abounding in the nuclear industry). They cover the range of management techniques from example setting to reward/recognition. Although not unique to radiation exposure management, nor all inclusive, the strategies provide some though stimulation in creating productive worker attitudes

Neutron dosimetry inside the containment building of Spanish nuclear power plants with PADC based dosemeters

Energy Technology Data Exchange (ETDEWEB)

Garcia-Fuste, M.J. [Grup de Fisica de les Radiacions. Departament de Fisica. Edifici C. Universitat Autonoma de Barcelona, E-08193 Bellaterra (Spain); Domingo, C., E-mail: carles.domingo@uab.ca [Grup de Fisica de les Radiacions. Departament de Fisica. Edifici C. Universitat Autonoma de Barcelona, E-08193 Bellaterra (Spain); Amgarou, K.; Bouassoule, T.; Castelo, J. [Grup de Fisica de les Radiacions. Departament de Fisica. Edifici C. Universitat Autonoma de Barcelona, E-08193 Bellaterra (Spain)

2009-10-15

The Spanish Nuclear Safety Council (Consejo de Seguridad Nuclear, CSN) recommends performing neutron individual dose assignments at workplaces based on ambient dose equivalent measurements using area monitors and by estimating the amount of time that workers spend in the different monitored environments. In addition, some Spanish nuclear power plants estimate the neutron dose equivalent using albedo thermoluminescence dosemeters (TLD). In the period 2004-2006, our group, together with other research centers, participated in a project, funded by the CSN, with the support of the Spanish Nuclear Power Plants Association (UNESA), to investigate in situ which could be the best practical procedure for individual neutron dose monitoring in nuclear power plants. As part of this survey, several units of the UAB PADC based neutron dosemeter were exposed, on a methacrylate phantom simulating a human body, at four different places inside the containment building of the Asco I nuclear power plant. The influence of different types of calibration neutron fields is analysed and the dose equivalent for each point is estimated.

Occupational dose reduction developments and data collected at nuclear power plants

International Nuclear Information System (INIS)

Dionne, B.J.; Baum, J.W.

1984-01-01

Occupational dose reduction developments and data collected at nuclear power plants have been described. Written descriptions of repetitive high dose jobs, their collective dose equivalent ranges and list of dose reduction techniques will aid in reducing collective dose equivalents from these dose-reduction targets. Knowing which components contribute to high maintenance or repair dose will aid in reducing routine maintenance collective dose equivalents. The radwaste dose reduction improvements will aid in reducing radwaste operations collective dose equivalent and reduce the number of radwaste workers who exceed their administrative dose limits. The identification and rating of managers' and workers' ALARA incentives will provide the basis for recommendations to improve dose reduction incentives. Lastly, the identification and rating of the key components of an ALARA program will aid in the development and coordination of the nuclear station ALARA programs

Occupational exposures at nuclear power plants. Twelfth annual report of the Isoe programme, 2002

International Nuclear Information System (INIS)

2004-01-01

The Information System on Occupational Exposure (ISOE) was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The ISOE Programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from the 465 commercial nuclear power plants participating in the Programme (representing some 90 per cent of the world's total operating commercial reactors). The Twelfth Annual Report of the ISOE Programme summarises achievements made during 2002 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

Development of advanced secondary chemistry monitoring system for Korea nuclear power plants

International Nuclear Information System (INIS)

Lee, Sang Hak; Kim, Chung Tae

1997-01-01

Water chemistry control is one of the most important tasks in order to maintain the reliability of plant equipments and extend the operating life of the plant. KEPCO and KOPEC developed a computerized tool for this purpose -ASCMS (advanced secondary chemistry monitoring system) which is able to monitor and diagnose the secondary water chemistry. A prototype system had been installed at KORI 3 nuclear power plant since April 1993 in order to evaluate the system performance. After the implementation of enhancements identified during the testing of the prototype, we have developed the advanced secondary monitoring system, ASCMS which is installed at 5 nuclear power plants and has been under operations since April 1997. The ASCMS comprises PC subsystem designed for data acquisition, data analysis, and data diagnosis. The ASCMS will provide overall information related to steam generator secondary side water chemistry problems and improve plant availability, reduce radiation exposure to workers, and reduce operating and maintenance costs. 6 figs

Integrated Nuclear Recycle Plant

International Nuclear Information System (INIS)

Patodi, Anuj; Parashar, Abhishek; Samadhiya, Akshay K.; Ray, Saheli; Dey, Mitun; Singh, K.K.

2017-01-01

Nuclear Recycle Board (NRB), Tarapur proposes to set up an 'Integrated Nuclear Recycle Plant' at Tarapur. This will be located in the premises of BARC facilities. The project location is at coastal town of Tarapur, 130 Km north of Mumbai. Project area cover of INRP is around 80 hectares. The plant will be designed to process spent fuel received from Pressurized Heavy Water Reactors (PHWRs). This is the first large scale integrated plant of the country. INRP will process spent fuel obtained from indigenous nuclear power plants and perform left over nuclear waste disposal

Nuclear power plant safety - the risk of accidents

International Nuclear Information System (INIS)

Higson, D.; Crancher, D.W.

1975-08-01

Although it is physically impossible for any nuclear plant to explode like an atom bomb, an accidental release of radioactive material into the environment is conceivable. Three factors reduce the probability of such releases, in dangerous quantities, to an extremely low level. Firstly, there are many safety features built into the plant including a leaktight containment building to prevent the escape of such material. Secondly, the quality of engineering and standards used are far more demanding than in conventional power engineering. Thirdly, strict government licensing and regulatory control is enforced at all phases from design through construction to operation. No member of the general public is known to have been injured or died as a result of any accident to a commercial nuclear power plant. Ten workers have died as a result of over-exposure to radiation from experimental reactors and laboratory work connected with the development of nuclear plant since 1945. Because of this excellent safety record the risk of serious accidents can only be estimated. On the basis of such estimates, the chance of an accident in a nuclear power reactor which could cause a detectable increase in the incidence of radiation-induced illnesses would be less than one chance in a million per year. In a typical highly industrialised society, such as the USA, the estimated risk of an individual being killed by such accidents, from one hundred operating reactors, is no greater than one chance in sixteen million per year. There are undoubtedly risks from reactor accidents but estimates of these risks show that they are considerably less than from other activities which are accepted by society. (author)

Fukushima Nuclear Accident, the Third International Severe Nuclear Power Plant Accident

International Nuclear Information System (INIS)

Rashad, S.M.

2013-01-01

Japan is the world's third largest power user. Japan's last remaining nuclear reactor shutdown on Saturday 4 Th of May 2012 leaving the country entirely nuclear free. All of 50 of the nation's operable reactors (not counting for the four crippled reactors at Fukushima) are now offline. Before last year's Fukushima nuclear disaster, the country obtained 30% of its energy from nuclear plants, and had planned to produce up to 50% of its power from nuclear sources by 2030. Japan declared states of emergency for five nuclear reactors at two power plants after the units lost cooling ability in the aftermath of Friday 11 March 2011 powerful earthquake. Thousands of (14000) residents were immediately evacuated as workers struggled to get the reactors under control to prevent meltdowns. On March 11 Th, 2011, Japan experienced a sever earthquake resulting in the shutdown of multiple reactors. At Fukushima Daiichi site, the earthquake caused the loss of normal Ac power. In addition it appeals that the ensuing tsunami caused the loss of emergency Ac power at the site. Subsequent events caused damage to fuel and radiological releases offsite. The spent fuel problem is a wild card in the potentially catastrophic failure of Fukushima power plant. Since the Friday's 9.0 earthquake, the plant has been wracked by repeated explosions in three different reactors. Nuclear experts emphasized there are significant differences between the unfolding nuclear crisis at Fukushima and the events leading up to the Chernobyl disaster in 1986. The Chernobyl reactor exploded during a power surge while it was in operation and released a major cloud of radiation because the reactor had no containment structure around to. At Fukushima, each reactor has shutdown and is inside a 20 cm-thick steel pressure vessel that is designed to contain a meltdown. The pressure vessels themselves are surrounded by steel-lined, reinforced concrete shells. Chernobyl disaster was classified 7 on the International

Nuclear plant simulation using the Nuclear Plant Analyzer

International Nuclear Information System (INIS)

Beelman, R.J.; Laats, E.T.; Wagner, R.J.

1984-01-01

The Nuclear Plant Analyzer (NPA), a state-of-the-art computerized safety analysis and engineering tool, was employed to simulate nuclear plant response to an abnormal transient during a training exercise at the US Nuclear Regulatory Commission (USNRC) in Washington, DC. Information relative to plant status was taken from a computer animated color graphics display depicting the course of the transient and was transmitted to the NRC Operations Center in a manner identical to that employed during an actual event. Recommendations from the Operations Center were implemented during on-line, interactive execution of the RELAP5 reactor systems code through the NPA allowing a degree of flexibility in training exercises not realized previously. When the debriefing was conducted, the RELAP5 calculations were replayed by way of the color graphics display, adding a new dimension to the debriefing and greatly enhancing the critique of the exercise

Nuclear power plant outages

International Nuclear Information System (INIS)

1998-01-01

The Finnish Radiation and Nuclear Safety Authority (STUK) controls nuclear power plant safety in Finland. In addition to controlling the design, construction and operation of nuclear power plants, STUK also controls refuelling and repair outages at the plants. According to section 9 of the Nuclear Energy Act (990/87), it shall be the licence-holder's obligation to ensure the safety of the use of nuclear energy. Requirements applicable to the licence-holder as regards the assurance of outage safety are presented in this guide. STUK's regulatory control activities pertaining to outages are also described

Decontamination work in the area surrounding Fukushima Dai-ichi Nuclear Power Plant: another occupational health challenge of the nuclear disaster.

Science.gov (United States)

Wada, Koji; Yoshikawa, Toru; Murata, Masaru

2012-01-01

This article describes occupational health measures for workers involved in decontamination of radioactive material discharged around Fukushima Dai-ichi Nuclear Power Plant after the explosions in 2011. Decontamination is performed by removing radioactive particles (mainly cesium) from surfaces of soil, grass and trees, and buildings. Measurement of radiation doses is necessary to reduce exposure, and to determine whether workers can work below dose limits. Protective equipment for decontamination is determined based on the concentration of radiation in contaminated soil and the exposure to dust. Health examinations by physicians are mandated for decontamination workers upon hiring and every 6 months. While there is no possibility of acute radiation injury from decontamination, workers may be anxious about the unclear effects of chronic low level radiation exposure on health. Measures to protect the decontamination workers are the top priority.

Development of a new cause classification method considering plant ageing and human errors for adverse events which occurred in nuclear power plants and some results of its application

International Nuclear Information System (INIS)

Miyazaki, Takamasa

2007-01-01

The adverse events which occurred in nuclear power plants are analyzed to prevent similar events, and in the analysis of each event, the cause of the event is classified by a cause classification method. This paper shows a new cause classification method which is improved in several points as follows: (1) the whole causes are systematically classified into three major categories such as machine system, operation system and plant outside causes, (2) the causes of the operation system are classified into several management errors normally performed in a nuclear power plant, (3) the content of ageing is defined in detail for their further analysis, (4) human errors are divided and defined by the error stage, (5) human errors can be related to background factors, and so on. This new method is applied to the adverse events which occurred in domestic and overseas nuclear power plants in 2005. From these results, it is clarified that operation system errors account for about 60% of the whole causes, of which approximately 60% are maintenance errors, about 40% are worker's human errors, and that the prevention of maintenance errors, especially worker's human errors is crucial. (author)

Occupational health programme for lead workers in battery plants

Science.gov (United States)

Lee, Byung-Kook

The realization of problems resulting from the exposure to undue high lead levels of workers in lead-using industries, particularly in storage battery plants, has given rise to a new occupational health service, the so-called type specific (harmful agent specific) group occupational health. In 1988, the Korean Ministry of Labor designated the Institute of Industrial Medicine, Soonchunhyang University, as an authorized organization to take care of lead workers in lead industries. The following occupational health services are provided by the Institute: (i) physical health examination; (ii) biological monitoring with zinc protoporphyrin, urine δ-aminolevulinic acid and blood lead; (iii) respiratory protection with maintenance-free respirators; (iv) measurement of the environmental condition of workplaces; (v) health education. A three-year occupational health programme for lead workers has contributed to improvements in the working conditions of lead industries, particularly in large-scale battery plants, and has decreased the unnecessary high lead burden of workers through on-going medical surveillance with biological monitoring and health education schemes. The strong commitment of both employers and the government to improve the working conditions of lead industries, together with the full cooperation of lead workers, has served to reduce the high lead burdens of lead workers. This decreases the number of lead-poisoning cases and provides more comfortable workplaces, particularly in battery plants.

Mortality among plutonium and other workers at a nuclear facility

International Nuclear Information System (INIS)

Wilkinson, G.S.; Voelz, G.L.; Acquavella, J.F.; Tietjen, G.L.; Reyes, M.; Brackbill, R.; Wiggs, L.

1983-01-01

Mortality among plutonium and other nuclear workers has been investigated to assess the effects of exposures to low levels of internal and external radiation. Standarized mortality ratios (SMRs) for white male workers employed at least two years from 1951 through 1977 were significantly lower than expected for all causes, all cancers, cancers of the respiratory system, and lung cancer. Benign neoplasms, all of which were intracranial tumors, were significantly elevated. No bone cancers were discovered and other radiogenic cancers did not differ significantly from expectation. Duration of employment and latency did not affect these results. SMRs for a subcohort of plutonium exposed workers were significantly low for all causes of deaths and all cancers. Estimates of relative risk for workers exposed to 2 or more nCi compared to unexposed workers were not significantly higher or lower than unity. These findings do not support the hypothesis of increased mortality among plutonium and other nuclear workers. The excess for benign and unspecified intracranial tumors is not consistent with previous studies on radiation induced brain tumors in terms of latency and exposure levels

Guidelines for the medical surveillance of atomic radiation workers

International Nuclear Information System (INIS)

1991-11-01

These guidelines are provided for the use and guidance of occupational physicians concerned with the medical surveillance of atomic radiation workers (ARWs). Persons employed in industries where there is exposure to ionizing radiation should be screened medically for fitness for certain jobs before starting such work and at appropriate intervals while employed. This includes workers at uranium mines, mills and refineries, nuclear fuel fabrication plants, nuclear power plants and research facilities, and facilities using radionuclides in an industrial setting. An important purpose of medical surveillance is to ensure that workers are fit both physically and psychologically to undertake the tasks they may be called upon to perform

Emotional consequences of nuclear power plant disasters.

Science.gov (United States)

Bromet, Evelyn J

2014-02-01

The emotional consequences of nuclear power plant disasters include depression, anxiety, post-traumatic stress disorder, and medically unexplained somatic symptoms. These effects are often long term and associated with fears about developing cancer. Research on disasters involving radiation, particularly evidence from Chernobyl, indicates that mothers of young children and cleanup workers are the highest risk groups. The emotional consequences occur independently of the actual exposure received. In contrast, studies of children raised in the shadows of the Three Mile Island (TMI) and Chernobyl accidents suggest that although their self-rated health is less satisfactory than that of their peers, their emotional, academic, and psychosocial development is comparable. The importance of the psychological impact is underscored by its chronicity and by several studies showing that poor mental health is associated with physical health conditions, early mortality, disability, and overuse of medical services. Given the established increase in mental health problems following TMI and Chernobyl, it is likely that the same pattern will occur in residents and evacuees affected by the Fukushima meltdowns. Preliminary data from Fukushima indeed suggest that workers and mothers of young children are at risk of depression, anxiety, psychosomatic, and post-traumatic symptoms both as a direct result of their fears about radiation exposure and an indirect result of societal stigma. Thus, it is important that non-mental health providers learn to recognize and manage psychological symptoms and that medical programs be designed to reduce stigma and alleviate psychological suffering by integrating psychiatric and medical treatment within the walls of their clinics.Introduction of Emotional Consequences of Nuclear Power Plant Disasters (Video 2:15, http://links.lww.com/HP/A34).

Ionizing radiation dose control for workers in a nuclear plant working with unsealed sources; Controle da dose de radiacao ionizante para trabalhadores em uma instalacao radiativa com fontes nao seladas

Energy Technology Data Exchange (ETDEWEB)

Gerulis, Eduardo

2006-07-01

With the liberation of the use of the nuclear energy for peaceful applications, International Commission Radiological Protection, ICRP, founded in 1928, created a system of protection of the undesirable doses of ionizing radiation in 1958. This has been received by workers, members of the public and environment and hence it became possible for the introduction of these applications. This protection system is adopted by the International Agency of Energy Atomic, IAEA, that publishes recommendations in safety series, 88 and by the Comissao Nacional de Energia Nuclear, CNEN, which publishes these regulations. The international recommendations and national regulations were adapted and they need to be applied in this way. The present paper uses recommendations of the publication 75 from ICRP, of the publication 115 from 88 and regulations of the regulation NN 3.01 from CNEN to present, through radiological protection measures, the ionizing radiation dose control for workers in a nuclear plant that works in the research, production, division and packing of unsealed sources to be used in clinical applications. In that way it is possible to prevent appropriately the undesirable doses and to confirm the received doses. (author)

Nuclear power plant siting

International Nuclear Information System (INIS)

Sulkiewicz, M.; Navratil, J.

The construction of a nuclear power plant is conditioned on territorial requirements and is accompanied by the disturbance of the environment, land occupation, population migration, the emission of radioactive wastes, thermal pollution, etc. On the other hand, a nuclear power plant makes possible the introduction of district heating and increases the economic and civilization activity of the population. Due to the construction of a nuclear power plant the set limits of negative impacts must not be exceeded. The locality should be selected such as to reduce the unfavourable effects of the plant and to fully use its benefits. The decision on the siting of the nuclear power plant is preceded by the processing of a number of surveys and a wide range of documentation to which the given criteria are strictly applied. (B.H.)

Adequacy of current systems for monitoring extremity exposures at nuclear power plants

International Nuclear Information System (INIS)

Reece, W.D.; Harty, R.

1985-01-01

In general, only a small portion of workers at commercial nuclear power plants are limited by extremity exposures, and these workers can be readily identified. There seems to be no need for increased badging among the radiation workers. However, those workers who are extremity limited may not be receiving adequate dosimetry. For workers handling compact sources, unless contrary information is available, the tip of the thumb of the dominant hand can be assumed to be the limiting site, and dose to the thumb tip averaged over one square centimeter at the basal layer of the skin should be measured or estimated. As discussed briefly in this paper, the assessment of dose in high gradient fields can be a difficult task. The particular dosimeter studied is a band-aid type composed of a thermoluminescent material embedded in a carbon matrix under 4 mils of plastic. Advantages and disadvantages of the technique are discussed

Issues behind Radiation management of workers at Fukushima Nuclear Power Plant of Tokyo Electric Power Company. From the viewpoint of radiation exposure of the ocular lens and the biological effects to the lens

International Nuclear Information System (INIS)

Hayashida, Toshiyuki; Sasaki, Hiroshi; Hatsusaka, Natsuko; Hamada, Nobuyuki; Tatsuzaki, Hideo; Akahane, Keiichi; Yokoyama, Sumi

2017-01-01

In March 2011, the accident occurred at the Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company. During recovery from critical situations, the radiation dose for some emergency workers exceeded the effective dose limit recommended for an emergency situation. A month after the accident, the International Commission on Radiological Protection issued a statement on tissue reactions recommending significant reduction of the equivalent dose limit to the lens of the eye. Many radiation workers will need to be involved in treatment of water contaminated with radionuclides, fuel debris retrieval, and decommissioning of reactors for a long period of time. Thus, the optimized radiation control in the fields, exposure reduction, prevention of tissue reactions, and reduction of stochastic risks for workers becomes necessary. This paper discusses issues in relation to radiation protection of the ocular lens in such recovery workers, from the viewpoint of radiation exposure of workers, its management, manifestations and mechanisms of the lens effects. (author)

Application of the Safety Classification of Structures, Systems and Components in Nuclear Power Plants

International Nuclear Information System (INIS)

2016-04-01

This publication describes how to complete tasks associated with every step of the classification methodology set out in IAEA Safety Standards Series No. SSG-30, Safety Classification of Structures, Systems and Components in Nuclear Power Plants. In particular, how to capture all the structures, systems and components (SSCs) of a nuclear power plant to be safety classified. Emphasis is placed on the SSCs that are necessary to limit radiological releases to the public and occupational doses to workers in operational conditions This publication provides information for organizations establishing a comprehensive safety classification of SSCs compliant with IAEA recommendations, and to support regulators in reviewing safety classification submitted by licensees

Care of personnel on the building site of the Dukovany nuclear power plant

International Nuclear Information System (INIS)

Kurial, P.

1984-01-01

The accommodation is described of workers on the building site of the Dukovany nuclear power plant. The quality is appraised of accommodation, catering and refreshments. There is a health care unit on site and 15 beds are reserved at the Trebic hospital for emergency cases. Trade union and youth organizations look after sports and cultural activities. (E.S.)

Trend analysis of explosion events at overseas nuclear power plants

International Nuclear Information System (INIS)

Shimada, Hiroki

2008-01-01

We surveyed failures caused by disasters (e.g., severe storms, heavy rainfall, earthquakes, explosions and fires) which occurred during the 13 years from 1995 to 2007 at overseas nuclear power plants (NPPs) from the nuclear information database of the Institute of Nuclear Safety System. Incorporated (INSS). The results revealed that explosions were the second most frequent type of failure after fires. We conducted a trend analysis on such explosion events. The analysis by equipment, cause, and effect on the plant showed that the explosions occurred mainly at electrical facilities, and thus it is essential to manage the maintenance of electrical facilities for preventing explosions. In addition, it was shown that explosions at transformers and batteries, which have never occurred at Japan's NPPs, accounted for as much as 55% of all explosions. The fact infers that this difference is attributable to the difference in maintenance methods of transformers (condition based maintenance adopted by NPPs) and workforce organization of batteries (inspections performed by utilities' own maintenance workers at NPPs). (author)

A reanalysis of cancer mortality in Canadian nuclear workers (1956–1994) based on revised exposure and cohort data

Science.gov (United States)

Zablotska, L B; Lane, R S D; Thompson, P A

2014-01-01

Background: A 15-country study of nuclear workers reported significantly increased radiation-related risks of all cancers excluding leukaemia, with Canadian data a major factor behind the pooled results. We analysed mortality (1956–1994) in the updated Canadian cohort and provided revised risk estimates. Methods: Employment records were searched to verify and revise exposure data and to restore missing socioeconomic status. Excess relative risks per sievert (ERR/Sv) of recorded radiation dose and 95% confidence intervals (CIs) were estimated using Poisson regression. Results: A significant heterogeneity of the dose–response for solid cancer was identified (P=0.02), with 3088 early (1956–1964) Atomic Energy of Canada Limited (AECL) workers having a significant increase (ERR/Sv=7.87, 95% CI: 1.88, 19.5), and no evidence of radiation risk for 42 228 workers employed by three nuclear power plant companies and post-1964 AECL (ERR/Sv=−1.20, 95% CI: workers and non-significantly increased in other workers. In analyses with separate terms for tritium and gamma doses, there was no evidence of increased risk from tritium exposure. All workers had mortality lower than the general population. Conclusion: Significantly increased risks for early AECL workers are most likely due to incomplete transfer of AECL dose records to the National Dose Registry. Analyses of the remainder of the Canadian nuclear workers (93.2%) provided no evidence of increased risk, but the risk estimate was compatible with estimates that form the basis of radiation protection standards. Study findings suggest that the revised Canadian cohort, with the exclusion of early AECL workers, would likely have an important effect on the 15-country pooled risk estimate of radiation-related risks of all cancer excluding leukaemia by substantially reducing the size of the point estimate and its significance. PMID:24231946

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2003-01-01

This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

Deterministic Effects of Occupational Exposures in the Mayak Nuclear Workers Cohort

International Nuclear Information System (INIS)

Azinova, T. V.; Okladnikova, N. D.; Sumina, M. V.; Pesternikova, V. S.; Osovets, V. S.; Druzhimina, M. B.; Seminikhina, N. g.

2004-01-01

A wide spread and utilization of nuclear energy in the recent decade leads to a stable increasing of contingents exposed to ionizing radiation sources. in order to predict radiation risks it's important to have and apply all the experience in assessment of health effects due to radiation exposures generated by now in different countries. the proposed report will present results of the long-term follow-up for a cohort of nuclear workers at the Mayak Production Association, with was the first nuclear facility in Russia. The established system of individual dosimetry of external exposure, monitoring of internal radiation and special system of medical follow-up of healthy nuclear workers during the last 50 years allowed collecting of the unique primary data to study radiation effects, their patterns and mechanisms specific of exposure dose. The study cohort includes 61 percent of males and 39 percent of females. The vital status is known for 90 percent of cases, 44 percent of workers are still alive and undergo regular medical examination in our Clinic. Unfortunately, by now 50 percent of workers have died. 6 percent of workers were lost for the follow-up. total doses from chronic external gamma rays in the cohort ranged from 0.6 to 10.8 Gy (annual exposure doses were from 0.001 to 7.4 Gy), Pu body burden was from 0.3 to 72.3 kBq. Most intensive chronic exposure of workers was registered during 1948 to 1958. At this time, 19 radiation accidents occurred at the Mayak PA. Thus, the highest incidence of deterministic effects was observed right at this period. In the cohort of Mayak nuclear workers there were diagnosed 60 cases of acute radiation syndrome (I to IV degrees of severity); 2079 cases of chronic radiation sickness; 120 cases of plutonium pneumoscelarosis; 5 cases of radiation cataracts; and over 400 cases of local radiation injuries. The report will present dependences of the observed effects on absorbed radiation dose and dose rate in terms of acute radiation

Structural radioactive waste from 'retubing/refurbishment' of Embalse nuclear power plant. Regulatory perspective

International Nuclear Information System (INIS)

Alvarez, Daniela E.; Lee Gonzales, Horacio M.; Medici, Marcela A.; Piumetti, Elsa H.

2009-01-01

Unlike the building of a new nuclear reactor, the 'retubing / refurbishment' of nuclear reactors that have been in operation for many years, involves the replacement of components in a radioactive environment. This requires a carefully planned radiation protection program to ensure protection of workers, the public and the environment as well as a radioactive waste management program for those radioactive waste generated during the process, which go beyond those generated during the normal operation and maintenance of the plant. Nucleoelectrica Argentina Sociedad Anonima (NA-SA) is scheduled to conduct the Life Extension Process of Embalse Nuclear Power Plant (CNE) which essentially consist of 'retubing / refurbishment' of the installation. The Nuclear Regulatory Authority (ARN) will then have an important activity related to the above process. In particular, this paper will describe some points of interest related to the generation and management of radioactive waste during the 'retubing / refurbishment' of the CNE, from the regulatory point of view. (author)

Radiation-related impacts for nuclear plant physical modifications

International Nuclear Information System (INIS)

Sciacca, F.; Knudson, R.; Simion, G.; Baca, G.; Behling, H.; Behling, K.; Britz, W.; Cohen, S.

1989-10-01

The radiation fields in nuclear power plants present significant obstacles to accomplishing repairs and modifications to many systems and components in these plants. The NRC's generic cost estimating methodology attempts to account for radiation-related impacts by assigning values to the radiation labor productivity factor. This radiation labor productivity factor is then used as a multiplier on the greenfield or new nuclear plant construction labor to adjust for the actual operating plant conditions. The value assigned to the productivity factor is based on the work-site radiation levels. The relationship among ALARA practices, work-place radiation levels, and radiation-related cost impacts previously had not been adequately characterized or verified. The assumptions made concerning the use and application of radiation-reduction measures such as system decontamination and/or the use of temporary shielding can significantly impact estimates of both labor requirements and radiation exposure associated with a particular activity. Overall guidance was needed for analysts as to typical ALARA practices at nuclear power plants and the effects of these practices in reducing work-site dose rates and overall labor requirements. This effort was undertaken to better characterize the physical modification cost and radiological exposure impacts related to the radiation environment of the work place. More specifically, this work sought to define and clarify the quantitative relationships between or among: radiation levels and ALARA practices, such as the use of temporary shielding, decontamination efforts, or the use of robots and remote tools; radiation levels and labor productivity factors; radiation levels, in-field labor hours, and worker radiation exposure; radiation levels and health physics services costs; and radiation levels, labor hours, and anti-contamination clothing and equipment. 48 refs., 4 figs., 4 tabs

A study on exposure dose from injection work and elution work for radiation workers and frequent workers in nuclear medicine

International Nuclear Information System (INIS)

Ju, Yong Jin; Chung, Woon Kwan; Dong, Kyung Rae; Choi, Eun Jin; Kwak, Jong Gil; Ryu, Jae Kwang

2017-01-01

Compared to other occupations, there is a greater risk of exposure to radiation due to the use of radioisotopes in nuclear medicine for diagnostic evaluations and therapy. To consider ways to reduce exposure dose for those in nuclear medicine involved in injection work and elution work among radiation workers as well as for sanitation workers and trainees among frequent workers an investigation into exposure dose and situational analysis from changes in yearly exposure dose evaluations, changes in work environment and changes in forms of inspection were conducted. Exposure dose measurements were taken by using EPD MK2 worn during working hours for one injection worker, one elution worker, two sanitation workers, and one trainee at a general hospital in the Seoul area for three days from July 18th to 20th 2016. Radiation from radioisotopes which are a part of nuclear medicine can significantly affect not only radiation workers who deal with radioisotopes directly but also frequency works as well. According to this study the annual dose limit for elution workers and injection workers were considered safe as the amount of exposure was not large enough to have a signifcant effect. The limits of this study consist in the duration of this study and the quantity of participants. Also there was a limitation of the measurement device involving accumulated exposure, where the EPD MK2 cannot check the changes in exposure according to a particular activity

A study on exposure dose from injection work and elution work for radiation workers and frequent workers in nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Ju, Yong Jin; Chung, Woon Kwan [Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of); Dong, Kyung Rae [Dept. of Radiological Technology, Gwangju Health University, Gwangju (Korea, Republic of); Choi, Eun Jin; Kwak, Jong Gil [Dept. of Public Health and Medicine, Dongshin University Graduate School, Naju (Korea, Republic of); Ryu, Jae Kwang [Dept. of Nuclear Medicine, Asan Medical Center, Seoul (Korea, Republic of)

2017-03-15

Compared to other occupations, there is a greater risk of exposure to radiation due to the use of radioisotopes in nuclear medicine for diagnostic evaluations and therapy. To consider ways to reduce exposure dose for those in nuclear medicine involved in injection work and elution work among radiation workers as well as for sanitation workers and trainees among frequent workers an investigation into exposure dose and situational analysis from changes in yearly exposure dose evaluations, changes in work environment and changes in forms of inspection were conducted. Exposure dose measurements were taken by using EPD MK2 worn during working hours for one injection worker, one elution worker, two sanitation workers, and one trainee at a general hospital in the Seoul area for three days from July 18th to 20th 2016. Radiation from radioisotopes which are a part of nuclear medicine can significantly affect not only radiation workers who deal with radioisotopes directly but also frequency works as well. According to this study the annual dose limit for elution workers and injection workers were considered safe as the amount of exposure was not large enough to have a signifcant effect. The limits of this study consist in the duration of this study and the quantity of participants. Also there was a limitation of the measurement device involving accumulated exposure, where the EPD MK2 cannot check the changes in exposure according to a particular activity.

76 FR 1469 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

Science.gov (United States)

2011-01-10

... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Environmental Assessment... Plant, LLC, the licensee, for operation of the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Impact Statement for License Renewal of Nuclear Plants, Calvert Cliffs Nuclear Power Plant (NUREG-1437...

Use of virtual reality to estimate radiation dose rates in nuclear plants

International Nuclear Information System (INIS)

Augusto, Silas C.; Mol, Antonio C.A.; Jorge, Carlos A.F.; Couto, Pedro M.

2007-01-01

Operators in nuclear plants receive radiation doses during several different operation procedures. A training program capable of simulating these operation scenarios will be useful in several ways, helping the planning of operational procedures so as to reduce the doses received by workers, and to minimize operations' times. It can provide safe virtual operation training, visualization of radiation dose rates, and estimation of doses received by workers. Thus, a virtual reality application, a free game engine, has been adapted to achieve the goals of this project. Simulation results for Argonauta research reactor of Instituto de Engenharia Nuclear are shown in this paper. A database of dose rate measurements, previously performed by the radiological protection service, has been used to display the dose rate distribution in the region of interest. The application enables the user to walk in the virtual scenario, displaying at all times the dose accumulated by the avatar. (author)

On exposure of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1988

International Nuclear Information System (INIS)

1989-01-01

The Law for Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1988 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the exposure of workers was below the permissible exposure dose in 1988 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of Japan Atomic Energy Research Institute and Power Reactor and Nuclear Fuel Development Corporation. (N.K.)

Health management of radiation workers

International Nuclear Information System (INIS)

Kunugita, Naoki; Igari, Kazuyuki

2013-01-01

People in Japan have expressed great anxiety about possible radiation and radioactivity after the accident at the Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company's (TEPCO), due to the great earthquake and tsunami in eastern Japan on 11 March 2011. A large number of workers were engaged in response and recovery operations, and they were possibly exposed to high doses of radiation as compared to the general population. In the accident at the Chernobyl Nuclear Power Plant in 1986, high doses of radiation to 134 plant staff and emergency personnel resulted in acute radiation syndrome (ARS), which proved fatal for 28 of them. In the Fukushima accident, six workers were exposed to more than 250 mSv of radiation during the initial response phase, but no one showed ARS. It is necessary to continue registration of radiation doses for all workers who were exposed to radiation to facilitate suitable healthcare management in the future. In addition to radiation exposure, a group of workers were also exposed to other health hazards. Frequent occurrence of heat disorders has been a concern for the workers wearing protective clothing with poor ventilation. A comprehensive program to prevent heat illness was implemented by TEPCO under the guidance of the Ministry of Health, Labour, and Welfare. It is important to provide effective systems not only for prevention of radiation exposure but also for general management of other health risks including heat disorders and infection. (author)

Radiation protection for repairs of reactor's internals at the 2nd Unit of the Nuclear Power Plant Temelin

International Nuclear Information System (INIS)

Zapletal, P.; Konop, R.; Koc, J.; Kvasnicka, O.; Hort, M.

2011-01-01

This presentation describes the process and extent of repairs of the 2 nd unit of the Nuclear power plant Temelin during the shutdown of the reactor. All works were optimized in terms of radiation protection of workers.

Life management plants at nuclear power plants PWR

International Nuclear Information System (INIS)

Esteban, G.

2014-01-01

Since in 2009 the CSN published the Safety Instruction IS-22 (1) which established the regulatory framework the Spanish nuclear power plants must meet in regard to Life Management, most of Spanish nuclear plants began a process of convergence of their Life Management Plants to practice 10 CFR 54 (2), which is the current standard of Spanish nuclear industry for Ageing Management, either during the design lifetime of the plant, as well as for Long-Term Operation. This article describe how Life Management Plans are being implemented in Spanish PWR NPP. (Author)

Reduction of noise influence during the periodical inspection of the nuclear power plant

International Nuclear Information System (INIS)

Hikono, Masaru

2002-01-01

At the nuclear power plant under the regular inspection, the sound level and the worker's impression of the environmental noises were measured. The environmental noise was the level with a possibility to cause the noise-induced deafness and have the psychological influence on the workers such as ''Get irritated''. These results imply the necessity of the noise countermeasure. For the noise influence relaxation, we examined the effectiveness of ear protections (e.g., ear plugs) and the intelligibility improvement of the paging system, prepared the noise management manual and the educational leaflet for the support of worker's self-defense. The results of the examinations showed that ear plug was effective especially in the high-noise environment and that the improvement of paging system increased the intelligibility. (author)

Experimental ratio between the 'real' dose per organ and the calculated dose determined by means of the Embalse nuclear power plant's personal dosimeter

International Nuclear Information System (INIS)

Thomasz, E.; Salas, C.A.

1987-01-01

The specific purpose of the study was to determine the experimental ratio between the reading of dosimeters used by the personnel of the Embalse nuclear power plant and the 'real' dose absorbed by the worker in different organs. An anthropomorphic phantom ALDERSON internal and externally loaded with approximately 150 TLD crystals was used. This phantom was placed in five enclosures that were usually occupied by workers of the Embalse nuclear power plant. In this way, the average dose per organ and the effective equivalent dosis in each enclosure could be calculated and compared with the personal dosimeters placed over the thorax and the conversion factor rem/rem for each enclosure was determined. The average factor resulting from the five considered enclosures was 0.73 rem/rem. This means that the personal dosimeters over value the real dosis absorbed by the personnel of the Embalse nuclear power plant in approximately 37%. (Author)

Benchmarking Nuclear Power Plants

International Nuclear Information System (INIS)

Jakic, I.

2016-01-01

One of the main tasks an owner have is to keep its business competitive on the market while delivering its product. Being owner of nuclear power plant bear the same (or even more complex and stern) responsibility due to safety risks and costs. In the past, nuclear power plant managements could (partly) ignore profit or it was simply expected and to some degree assured through the various regulatory processes governing electricity rate design. It is obvious now that, with the deregulation, utility privatization and competitive electricity market, key measure of success used at nuclear power plants must include traditional metrics of successful business (return on investment, earnings and revenue generation) as well as those of plant performance, safety and reliability. In order to analyze business performance of (specific) nuclear power plant, benchmarking, as one of the well-established concept and usual method was used. Domain was conservatively designed, with well-adjusted framework, but results have still limited application due to many differences, gaps and uncertainties. (author).

Development of remote repair robots for dissolvers in nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Sugiyama, Sen; Kunikata, Michio; Kawamura, Hironobu.

1985-01-01

For nuclear facilities, various types of remote maintenance and inspection devices have been developed to reduce radiation exposure to workers, save labor, and improve the operating rate of the plant. Existing robot technology, however, could not be employed when we were recently called upon to inspect and repair pinhole defects which had occurred in the spent fuel dissolvers of the Power Reactor and Nuclear Fuel Development Corporation's Tokai Reprocessing Plant, because the work had to be done in an extremely radioactive environment, conditions too extreme for conventional robots. For this reason, we developed highly radiation-resistant repair robots capable of fully remote-controlled operation inside the barrels of the dissolvers, which have the inconvenient shape of 270 mm inside diameter and 6 m length. The process for developing the six different repair robots and the their functions are described in this paper. This development was sponsored by the Power Reactor and Nuclear Fuel Development Corporation (PNC) under contract with Hitachi, Ltd. (author)

Safety and radiation protection at the Swedish nuclear power plants 2000

International Nuclear Information System (INIS)

2001-04-01

During 2000 no events occurred, or discoveries were made, that seriously affected the reactor safety at the Swedish nuclear plants. The basic safety strategy is designed so that hidden faults and deficiencies shall not lead to any serious consequences for the plants. It is of outmost importance that the safety work at the plants is performed with the best effort and quality in order to realize this strategy. Especially in the new economic situation of the utilities after deregulation of the electricity market. The total radiation dose to the personnel and contracted workers at the plants was the lowest ever recorded with all NPPs running (8.1 man Sv). Corrosion damages led to a stand-still of two reactors during a long period, and thorough analyses were performed before the Inspectorate allowed a restart

Radiation exposure and cause specific mortality among nuclear workers in Belgium (1969-1994)

International Nuclear Information System (INIS)

Engels, H.; Swaen, G. M. H.; Slangen, J.; Van Amersvoort, L.; Holmstock, L.; Van Mieghem, E.; Van Regenmortel, I.; Wambersie, A.

2005-01-01

Cause specific mortality was studied in nuclear workers from five nuclear facilities in Belgium and compared to the general population. For the 1969-1994 period, mortality in male nuclear workers is significantly lower for all causes of death and for all cancer deaths. The same conclusions are reached if one assumes a latency period of 20 y between the first irradiation and cancer induction. In female workers, mortality due to all causes and all cancer deaths is not different from that of the general population. Analysis of cause specific mortality was performed for male and female workers for three endpoints: specific cancer sites, cardiovascular and respiratory diseases. No significant increase in mortality was observed. In male workers, the influence of cumulative dose was also investigated using four dose levels: No significant correlation was found. Smoking habits may be a confounding factor in smoking related health conditions. (authors)

Action research for the development of the organizational climate in nuclear power plants. Review of the 6-year research and development program

International Nuclear Information System (INIS)

Yoshida, Michio; Misumi, Jyuji; Misumi, Emiko; Kotani, Fumio; Fukui, Hirokazu; Sakurai, Yukihiro

1998-01-01

The Institute of Nuclear Safety System, Incorporated and the Japan Institute for Group Dynamics have conducted action research for the development of the organizational climate in nuclear power plants. First, two types of scales were completed. One is for measuring the leadership behavior of leaders working at nuclear power plants and the other is for measuring the safety consciousness of workers. After having diagnosed the reality of actual nuclear power plants using those scales developed, leadership training courses were developed and implemented successfully. Analyses of the commitment to organization and self-efficacy and the relationship between leadership and personality were conducted as well. (author)

Action research for the development of the organizational climate in nuclear power plants. Review of the 6-year research and development program

Energy Technology Data Exchange (ETDEWEB)

Yoshida, Michio [Kumamoto Univ. (Japan). Faculty of Education; Misumi, Jyuji; Misumi, Emiko; Kotani, Fumio; Fukui, Hirokazu; Sakurai, Yukihiro

1998-09-01

The Institute of Nuclear Safety System, Incorporated and the Japan Institute for Group Dynamics have conducted action research for the development of the organizational climate in nuclear power plants. First, two types of scales were completed. One is for measuring the leadership behavior of leaders working at nuclear power plants and the other is for measuring the safety consciousness of workers. After having diagnosed the reality of actual nuclear power plants using those scales developed, leadership training courses were developed and implemented successfully. Analyses of the commitment to organization and self-efficacy and the relationship between leadership and personality were conducted as well. (author)

Regulatory aspects of radiation protection in Indian nuclear plants

International Nuclear Information System (INIS)

Chander, Vipin; Pawar, S.K.; Duraisamy, S.

2012-01-01

Atomic Energy Act of 1962 covers the radiation safety aspects in the development, control and use of atomic energy. To carry out certain regulatory and safety functions under this act, Atomic Energy Regulatory Board (AERB) was constituted in November 15, 1983. Operating Nuclear Power Plants (NPPs) account for about 60% of occupational collective dose and about 65% of the number of radiation workers in the nuclear fuel cycle facilities. Therefore radiation protection aspects in NPPs are of prime importance. In 1970s and 1980s the high radiation exposures in NPPs was an issue with TAPS-1 and 2 reaching annual collective dose of 50 Person-Sv. In response to this, AERB constituted an expert committee to investigate the possibility of reducing collective doses in NPPs in 1988. Subsequently the recommendations of this committee were implemented in all NPPs. In 1990, International Commission on Radiological Protection (ICRP) recommended a downward revision of occupational dose limit to 20 mSv/yr from the earlier limit of 50 mSv/yr. Regulatory body endorsed these recommendations and gradually brought down the annual dose limits from 40 mSv in 1991 to 30 mSv in 1994 with the limit of 100 mSv averaged over a five year period in line with ICRP recommendations. Over the years, the regulatory body has put in place a sound regulatory frame work and mechanism to ensure adequate protection of occupational workers, members of public and environment due to operation of NPPs. Vast experiences in the field of radiation protection vis-à-vis stringent regulatory requirements such as review of exposure cases and special regulatory inspections during Biennial Shut Down (BSD) has helped in downward trends in occupational and public doses. This paper highlights the role of regulatory body in controlling the radiation doses to both occupational workers and members of public in the NPPs through a three-tier review system. The regulatory oversight, inspections and reviews has resulted in

Q Fever Outbreak among Workers at a Waste-Sorting Plant.

Directory of Open Access Journals (Sweden)

Eva Alonso

Full Text Available An outbreak of Q fever occurred in February-April 2014 among workers at a waste-sorting plant in Bilbao (Spain. The outbreak affected 58.5% of investigated employees, 47.2% as confirmed cases (PCR and/or serology and 11.3% as probable cases (symptoms without laboratory confirmation. Only employees who had no-access to the waste processing areas of the plant were not affected and incidence of infection was significantly higher among workers not using respiratory protection masks. Detection by qPCR of Coxiella burnetii in dust collected from surfaces of the plant facilities confirmed exposure of workers inside the plant. Animal remains sporadically detected among the residues received for waste-sorting were the most probable source of infection. After cleaning and disinfection, all environmental samples tested negative. Personal protection measures were reinforced and made compulsory for the staff and actions were taken to raise farmers' awareness of the biological risk of discharging animal carcasses as urban waste.

Are atomic power plants saver than nuclear power plants

International Nuclear Information System (INIS)

Roeglin, H.C.

1977-01-01

It is rather impossible to establish nuclear power plants against the resistance of the population. To prevail over this resistance, a clarification of the citizens-initiatives motives which led to it will be necessary. This is to say: It is quite impossible for our population to understand what really heappens in nuclear power plants. They cannot identify themselves with nuclear power plants and thus feel very uncomfortable. As the total population feels the same way it is prepared for solidarity with the citizens-initiatives even if they believe in the necessity of nuclear power plants. Only an information-policy making transparent the social-psychological reasons of the population for being against nuclear power plants could be able to prevail over the resistance. More information about the technical procedures is not sufficient at all. (orig.) [de

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2005-01-01

This 2005 edition of the Elecnuc booklet summarizes in tables all numerical data relative to the nuclear power plants worldwide. These data come from the PRIS database managed by the IAEA. The following aspects are reviewed: 2004 highlights; main characteristics of reactor types; map of the French nuclear power plants on 2005/01/01; worldwide status of nuclear power plants at the end of 2004; units distributed by countries; nuclear power plants connected to the grid by reactor-type group; nuclear power plants under construction on 2004; evolution of nuclear power plant capacities connected to the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear power plants by country at the end 2004; performance indicator of PWR units in France; trend of the generation indicator worldwide; 2004 load factor by owners; units connected to the grid by countries at 12/31/2004; status of licence renewal applications in USA; nuclear power plants under construction at 12/31/2004; shutdown reactors; exported nuclear capacity in net MWe; exported and national nuclear capacity connected to the grid; exported nuclear power plants under construction or order; exported and national nuclear capacity under construction or order; recycling of plutonium in LWR; Mox licence plant projects; Appendix - historical development; acronyms, glossary

Nuclear power plant operator licensing

International Nuclear Information System (INIS)

1997-01-01

The guide applies to the nuclear power plant operator licensing procedure referred to the section 128 of the Finnish Nuclear Energy Degree. The licensing procedure applies to shift supervisors and those operators of the shift teams of nuclear power plant units who manipulate the controls of nuclear power plants systems in the main control room. The qualification requirements presented in the guide also apply to nuclear safety engineers who work in the main control room and provide support to the shift supervisors, operation engineers who are the immediate superiors of shift supervisors, heads of the operational planning units and simulator instructors. The operator licensing procedure for other nuclear facilities are decided case by case. The requirements for the basic education, work experience and the initial, refresher and complementary training of nuclear power plant operating personnel are presented in the YVL guide 1.7. (2 refs.)

Organizing nuclear power plant operation

International Nuclear Information System (INIS)

Adams, H.W.; Rekittke, K.

1987-01-01

With the preliminary culmination in the convoy plants of the high standard of engineered safeguards in German nuclear power plants developed over the past twenty years, the interest of operators has now increasingly turned to problems which had not been in the focus of attention before. One of these problems is the organization of nuclear power plant operation. In order to enlarge the basis of knowledge, which is documented also in the rules published by the Kerntechnischer Ausschuss (Nuclear Technology Committee), the German Federal Minister of the Interior has commissioned a study of the organizational structures of nuclear power plants. The findings of that study are covered in the article. Two representative nuclear power plants in the Federal Republic of Germany were selected for the study, one of them a single-unit plant run by an independent operating company in the form of a private company under German law (GmbH), the other a dual-unit plant operated as a dependent unit of a utility. The two enterprises have different structures of organization. (orig.) [de

Investigation of internal contamination by tritium in A-1 nuclear power plant personnel in 1974

International Nuclear Information System (INIS)

Ondris, D.; Herchl, M.; Homolova, E.

1977-01-01

The results are presented of the 1974 personnel monitoring of the Bohunice A-1 nuclear power plant staff for internal contamination with tritium. Totally, 650 urine samples taken from 103 workers were analyzed using the recommended ICRP procedure. In routine examinations, the highest dose equivalent value of tritium incorporated within two weeks did not exceed 10 mrem, i.e., the maximum annual dose equivalent did not exceed 260 mrem. 8.5 μCi tritium per 1 litre urine was considered to be an alarm value. In a selected group of 21 high-risk persons analyses were conducted before and after each operation associated with tritium hazards. The limit dose was set to 5.8 μCi.l -1 , i.e., the tritium concentration equivalent to 10% of the maximum permissible annual intake. In 18 workers where tritium risk was of a more serious nature the biological half-life was followed up, with the average biological half-life being 8.5 days, with 5 days for the minimum and 12 days for the maximum values. The results show that in 1974 the tritium burden did not exceed 1/10 of the maximum permissible dose for any of the A-1 nuclear power plant workers. (L.O.)

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2003-01-01

The Japan Atomic Industrial Forum (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2002 was made up on bases of answers on questionnaires from 65 electric power companies and other nuclear organizations in 28 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

On exposure management of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1993

International Nuclear Information System (INIS)

1994-01-01

The Law of Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1993 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the the exposure of workers was below the permissible exposure dose in 1993 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of JAERI and PNC. (J.P.N.)

On nuclear power plant uprating

International Nuclear Information System (INIS)

Ho, S. Allen; Bailey, James V.; Maginnis, Stephen T.

2004-01-01

Power uprating for commercial nuclear power plants has become increasingly attractive because of pragmatic reasons. It provides quick return on investment and competitive financial benefits, while involving low risks regarding plant safety and public objection. This paper briefly discussed nuclear plant uprating guidelines, scope for design basis analysis and engineering evaluation, and presented the Salem nuclear power plant uprating study for illustration purposes. A cost and benefit evaluation of the Salem power uprating was also included. (author)

Working conditions in nuclear reprocessing plants

International Nuclear Information System (INIS)

1986-12-01

In the context of the project, the working conditions of workers in reprocessing plants and associated plant of the fuel circuit were thoroughly examined. The project design and course of the project are a good example of a precautionary technical assessment necessary for social policy reasons, which is in the public interest and is required by the Trade Unions. By working conditions, one means the whole set of scientific/technical, medical, legal, economic and political conditions for the permanent employment of workers in reprocessing plants including the associated parts of the fuel circuit. (orig./HP) [de

Plant Design Nuclear Fuel Element Production Capacity Optimization to Support Nuclear Power Plant in Indonesia

International Nuclear Information System (INIS)

Bambang Galung Susanto

2007-01-01

The optimization production capacity for designing nuclear fuel element fabrication plant in Indonesia to support the nuclear power plant has been done. From calculation and by assuming that nuclear power plant to be built in Indonesia as much as 12 NPP and having capacity each 1000 MW, the optimum capacity for nuclear fuel element fabrication plant is 710 ton UO 2 /year. The optimum capacity production selected, has considered some aspects such as fraction batch (cycle, n = 3), length of cycle (18 months), discharge burn-up value (Bd) 35,000 up 50,000 MWD/ton U, enriched uranium to be used in the NPP (3.22 % to 4.51 %), future market development for fuel element, and the trend of capacity production selected by advances country to built nuclear fuel element fabrication plant type of PWR. (author)

Construction and commissioning experience of evolutionary water cooled nuclear power plants

International Nuclear Information System (INIS)

2004-04-01

Electricity market liberalization is an established fact in several countries and there is a trend to adopt it in other countries. The essential aim of market liberalization is to improve the overall economic efficiency. In order that nuclear power remains a viable option for electricity generation, its costs should be competitive with alternative sources while, at the same time, it should have a safe and reliable operation record. The capital cost of nuclear power plants (NPPs) generally accounts for 43-70% of the total nuclear electricity generation costs, compared to 26-48% for coal plants and 13-32% for gas plants. Most of these expenditures are incurred during the construction phase of a NPP. The achievement of shorter construction periods using improved technology and construction methods has a significant benefit on the costs incurred prior to any production of electricity. This document is intended to make the recent worldwide experience on construction and commissioning of evolutionary water cooled NPPs available to Member States and especially to those with nuclear power plants under construction/planning, and to those seriously considering nuclear power projects in the future. The final aim is to assist utilities and other organizations in Member States to improve the construction of nuclear power plants and achieve shortened schedules and reduced costs without compromising quality and safety. This document aims to provide an overview of the most advanced technologies, methods and processes used in construction and commissioning of recent nuclear projects. To better achieve this objective the presentation is selectively focused more on the new developments rather than providing a full review of all issues related to construction and commissioning. The experience described in this TECDOC applies to managers, engineers, supervisors, technicians and workers in various organizations dealing with the site construction and commissioning of nuclear power plants

Nuclear security - New challenge to the safety of nuclear power plants

International Nuclear Information System (INIS)

Li Ganjie

2008-01-01

The safety of nuclear power plants involves two aspects: one is to prevent nuclear accidents resulted from systems and equipments failure or human errors; the other is to refrain nuclear accidents from external intended attack. From this point of view, nuclear security is an organic part of the nuclear safety of power plants since they have basically the same goals and concrete measures with each other. In order to prevent malicious attacks; the concept of physical protection of nuclear facilities has been put forward. In many years, a series of codes and regulations as well as technical standard systems on physical protection had been developed at international level. The United Nations passed No. 1540 resolution as well as 'Convention on the Suppression of Acts of Nuclear terrorism', and revised 'Convention on Physical Protection of Nuclear Materials', which has enhanced a higher level capacity of preparedness by international community to deal with security issues of nuclear facilities. In China, in order to improve the capability of nuclear power plants on preventing and suppressing the external attacks, the Chinese government consecutively developed the related codes and standards as well as technical documents based on the existing laws and regulations, including 'Guide for the Nuclear Security of Nuclear Power Plants' and 'Guide for the Physical Protection of Nuclear Materials', so as to upgrade the legislative requirements for nuclear security in power plants. The government also made greater efforts to support the scientific research and staff training on physical protection, and satisfying the physical protection standards for newly-built nuclear facilities such as large scale nuclear power plants to meet requirement at international level. At the same time old facilities were renovated and the Chinese government established a nuclear emergency preparedness coordination mechanism, developed corresponding emergency preparedness plans, intensified the

Nuclear power plants in the world

International Nuclear Information System (INIS)

2008-01-01

The Japan Atomic Industrial Forum, Inc. (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2007/2008 was made up on bases of answers on questionnaires from electric power companies and other nuclear organizations around the world by JAIF. This report is comprised of 18 items, and contains generating capacity of the plants; effect of the Niigata-ken chuetsu-oki earthquake; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities, and so forth. (J.P.N.)

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2004-01-01

The Japan Atomic Industrial Forum, Inc. (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2003 was made up on bases of answers on questionnaires from 81 electric power companies and other nuclear organizations in 33 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

A methodology for nuclear power plant operational events evaluation

International Nuclear Information System (INIS)

Araujo, Jeferson

2015-01-01

Operational events are normal occurrences in industrial plants and in nuclear power plants. The evaluation of operational events gains importance when it comes specifically to nuclear power plants due to the proportions that the impact and the consequences of these events may cause to the installation itself, their workers, the external area of the nuclear installation, the environment and to the public in general. These consequences, for the operation of these facilities can range from very little, until the consequences that lead to accidents and can cause significant impacts. Operational events may be associated or have influence in many fields of knowledge, such as operation, maintenance, engineering, Radiological Protection, physical protection, chemistry, Human or Organizational Factors and external events, among others. The accident at the Fukushima Daichi nuclear power plant, shows the importance of exhausting all the studies concerning operational events in order to improve the operational safety of nuclear plants, considering all the causes and possible consequences. In this context, the evaluation of operational events discipline emerges as an important and relevant tool to contribute to the maintenance and/or improvement of the operational safety of nuclear installations. Not without reason the nuclear industry actively participates in programs of exchange of operational experience, where relevant events are thoroughly evaluated and discussed in specific forums, such as power plant operators, regulators and/or joint technical meetings, always with the purpose to prevent, minimize or mitigate its consequences. Any evaluation of operational events passes necessarily by an in-depth study of the circumstances of the event, culminating with the identification of your cause and proposition of corrective actions to prevent recurrence of similar events. Additionally, the events should not be studied individually, but evaluated within a temporal context in order

A methodology for nuclear power plant operational events evaluation

Energy Technology Data Exchange (ETDEWEB)

Araujo, Jeferson, E-mail: jeferson@cnen.gov.br [Comissao Nacional de Energia Nuclear (CGRC/CNEN), Rio de janeiro, RJ (Brazil). Coordenacao Geral de Reatores e do Ciclo de Combustivel; Costa, Sergio Dias, E-mail: sergiodiascosta@hotmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2015-07-01

Operational events are normal occurrences in industrial plants and in nuclear power plants. The evaluation of operational events gains importance when it comes specifically to nuclear power plants due to the proportions that the impact and the consequences of these events may cause to the installation itself, their workers, the external area of the nuclear installation, the environment and to the public in general. These consequences, for the operation of these facilities can range from very little, until the consequences that lead to accidents and can cause significant impacts. Operational events may be associated or have influence in many fields of knowledge, such as operation, maintenance, engineering, Radiological Protection, physical protection, chemistry, Human or Organizational Factors and external events, among others. The accident at the Fukushima Daichi nuclear power plant, shows the importance of exhausting all the studies concerning operational events in order to improve the operational safety of nuclear plants, considering all the causes and possible consequences. In this context, the evaluation of operational events discipline emerges as an important and relevant tool to contribute to the maintenance and/or improvement of the operational safety of nuclear installations. Not without reason the nuclear industry actively participates in programs of exchange of operational experience, where relevant events are thoroughly evaluated and discussed in specific forums, such as power plant operators, regulators and/or joint technical meetings, always with the purpose to prevent, minimize or mitigate its consequences. Any evaluation of operational events passes necessarily by an in-depth study of the circumstances of the event, culminating with the identification of your cause and proposition of corrective actions to prevent recurrence of similar events. Additionally, the events should not be studied individually, but evaluated within a temporal context in order

How nuclear liability practices have been implemented in US. US nuclear claims experience

International Nuclear Information System (INIS)

Bardes, C.R.

2000-01-01

Three Mile Island has been only major nuclear incident in US involving a power plant that resulted in payments to public. In addition to Three Mile Island, there have been only 3 lawsuits by members of the public against nuclear power plant operators; these alleged bodily injury and property damage resulting from normal operations. Of 202 claims handled by ANI, 161 involved individual nuclear facilities workers. Costs of the worker claims (through 1998) was US $1.5 million for indemnity (losses) and US$35.9 million for legal defense costs. By far, 1979 TMI accident produced largest number of third-party claims. ANI's emergency claims handling procedure for large nuclear accident tested and proved itself at Three Mile Island

Study on the distribution coefficient during environmental impact evaluation in Chinese inland nuclear power plants

International Nuclear Information System (INIS)

Xu Haifeng; Shang Zhaorong; Chen Fangqiang

2012-01-01

Description the radionuclide distribution coefficient of the important factors in the river sediment systems, at home and abroad the main method of measuring the K d value and progress in China's inland nuclear power plant environmental impact assessment of workers to carry out the distribution coefficient K d value measurement ideas put forward recommendations. (authors)

Nuclear Power Plants (Rev.)

Energy Technology Data Exchange (ETDEWEB)

Lyerly, Ray L.; Mitchell III, Walter [Southern Nuclear Engineering, Inc.

1973-01-01

Projected energy requirements for the future suggest that we must employ atomic energy to generate electric power or face depletion of our fossil-fuel resources—coal, oil, and gas. In short, both conservation and economic considerations will require us to use nuclear energy to generate the electricity that supports our civilization. Until we reach the time when nuclear power plants are as common as fossil-fueled or hydroelectric plants, many people will wonder how the nuclear plants work, how much they cost, where they are located, and what kinds of reactors they use. The purpose of this booklet is to answer these questions. In doing so, it will consider only central station plants, which are those that provide electric power for established utility systems.

Improvement of the nuclear plant analyzer for Korean Standard Nuclear Power Plants

International Nuclear Information System (INIS)

Choi, Sung Soo; Han, Byoung Sub; Suh, Jae Seung; Son, Dae Seong

2005-04-01

Accurate analysis of the operating characteristics of Nuclear Power Plants provides valuable information for both norman and abnormal operation. The information can be used for the enhancement of plant performance and safety. Usually, such analysis is performed using computer codes used for plant design or simulators. However, their usages are limited because special expertise is required to use the computer codes and simulators are not portable. Therefore, it deemed necessary to develop an NPA which minimizes those limitations and can be used for the analysis and simulation of Nuclear Power Plants. The purpose of this study is to develop a real-time best-estimate NPA for the Korean Nuclear Power Plants(KSNP). The NPA is an interactive, high fidelity engineering simulator. NPA combines the process model simulating the plant behavior with the latest computer technology such as Graphical User Interface(GUI) and simulation executive for enhanced user interface. The process model includes models for a three-dimensional reactor core, the NSSS, secondary system including turbine and feedtrain, safety auxiliary systems, and various control systems. Through the verification and validation of the NPA, it was demonstrated that the NPA can realistically simulate the plant behaviors during transient and accident conditions

Nuclear power plants in post-war thought

International Nuclear Information System (INIS)

Toya, Hiroshi

2015-01-01

This paper overviews how nuclear power plants have been talked about in the post-war thought. Science and technology sometimes significantly change the thinking way of humans, and nuclear power generation is an extreme technology. This paper overviews how nuclear power plants and humans are correlated. The following three points are discussed as the major issues of contemporary thought over nuclear power plants. First, on the danger of nuclear power plants, the risk of destructive power that nuclear energy has, and the danger of unreasoning development in science and technology civilization are discussed. Second, on the ethics issues surrounding nuclear power plants, the ethics that are based on unbalanced power relations, and democratic responsibility ethics based on discussion ethics are discussed. Third, on the issues of nuclear power plants and imagination, the limitations of democratic discussion surrounding nuclear power plants, the formation of imagination commensurate with the destructive power of nuclear power plants, and the formation of imagination that can represent the distant future are discussed. (A.O.)

Some aspects of nuclear power development in Czechoslovakia

International Nuclear Information System (INIS)

Simandl, S.; Stefec, V.

1986-01-01

Some technical and economic aspects of the development of nuclear power in Czechoslovakia are discussed. Specific conditions include the high population density of the territory and related factors as well as the shortage of raw materials for the construction of technological equipment and for the construction of buildings. It is stated that projects of future nuclear power plants should use reserves, such as are available in the standard project of a WWER-1000 nuclear power plant now being used in Temelin, as against foreign nuclear power plants. This mainly includes a bigger built-up area per installed megawatt of power and a greater number of personnel for operation and maintenance. Also discussed is the world-wide growth of capital costs, of construction time and of the number of workers needed for the construction of nuclear power plants. With the exception of the V-2 nuclear power plant the construction time of Czechoslovak nuclear power plants does not exceed world average. The maximum number of workers required for construction, however, compares unfavourably with advanced capitalist countries. Operating costs in Czechoslovakia are more favourable for nuclear power plants than for coal burning power plants and pumped-storage hydroelectric plants. (Z.M.)

Reduction of noise influence during the periodical inspection of the nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Hikono, Masaru [Inst. of Nuclear Safety System Inc., Mihama, Fukui (Japan)

2002-09-01

At the nuclear power plant under the regular inspection, the sound level and the worker's impression of the environmental noises were measured. The environmental noise was the level with a possibility to cause the noise-induced deafness and have the psychological influence on the workers such as ''Get irritated''. These results imply the necessity of the noise countermeasure. For the noise influence relaxation, we examined the effectiveness of ear protections (e.g., ear plugs) and the intelligibility improvement of the paging system, prepared the noise management manual and the educational leaflet for the support of worker's self-defense. The results of the examinations showed that ear plug was effective especially in the high-noise environment and that the improvement of paging system increased the intelligibility. (author)

Radiological safety of nuclear power plants in India

International Nuclear Information System (INIS)

Sathish, A.V.

2015-01-01

Safety in nuclear power plants (NPPs) is often less understood and more talked about, thus the author wanted to share the facts to clear the myths. Safety is accorded overriding priority in all the activities. All nuclear facilities are sited, designed, constructed, commissioned and operated in accordance with strict quality and safety standards. Principles of defence in depth, redundancy and diversity are followed in the design of all nuclear facilities and their systems/components. PPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, approved standard operating and maintenance procedures, a well-defined waste management methodology, periodically rehearsed emergency preparedness and disaster management plans. The regulatory framework in the country is robust, with the independent Atomic Energy Regulatory Board (AERB) having powers to frame the policies, laying down safety standards, monitoring and enforcing all the safety provisions. As a result, India's safety record has been excellent in over 400 reactor years of operation of power reactors

Public regulation of nuclear plants

International Nuclear Information System (INIS)

Burtheret, M.; Cormis, de

1980-01-01

The construction and operation of nuclear plants are subject to a complex system of governmental administration. The authors list the various governmental authorisations and rules applicable to these plants. In the first part, they describe the national regulations which relate specifically to nuclear plants, and emphasize the provisions which are intended to ensure the safety of the installations and the protection of the public against ionizing radiation. However, while the safety of nuclear plants is a major concern of the authorities, other interests are also protected. This is accomplished by various laws or regulations which apply to nuclear plants as well as other industrial installations. The duties which these texts, and the administrative practice based thereon, impose on Electricite de France are covered in the second part [fr

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2000-01-01

The Japan Atomic Industrial Forum (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Developmental trends on nuclear power plants in the world'. In this report, some data at the end of 1999 was made up on bases of answers on questionnaires from 72 electric companies in 31 nations and regions in the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; location of the plants; the plants in the world; and so forth. And, it also has some survey results on the 'Liberalization of electric power markets and nuclear power generation' such as some 70% of respondents in nuclear power for future option, gas-thermal power seen as power source with most to gain from liberalization, merits on nuclear power generation (environmental considerations and supply stability), most commonly voiced concern about new plant orders in poor economy, and so forth. (G.K.)

Nuclear power plant safety

International Nuclear Information System (INIS)

Otway, H.J.

1974-01-01

Action at the international level will assume greater importance as the number of nuclear power plants increases, especially in the more densely populated parts of the world. Predictions of growth made prior to October 1973 [9] indicated that, by 1980, 14% of the electricity would be supplied by nuclear plants and by the year 2000 this figure would be about 50%. This will make the topic of international co-operation and standards of even greater importance. The IAEA has long been active in providing assistance to Member States in the siting design and operation of nuclear reactors. These activities have been pursued through advisory missions, the publication of codes of practice, guide books, technical reports and in arranging meetings to promote information exchange. During the early development of nuclear power, there was no well-established body of experience which would allow formulation of internationally acceptable safety criteria, except in a few special cases. Hence, nuclear power plant safety and reliability matters often received an ad hoc approach which necessarily entailed a lack of consistency in the criteria used and in the levels of safety required. It is clear that the continuation of an ad hoc approach to safety will prove inadequate in the context of a world-wide nuclear power industry, and the international trade which this implies. As in several other fields, the establishment of internationally acceptable safety standards and appropriate guides for use by regulatory bodies, utilities, designers and constructors, is becoming a necessity. The IAEA is presently planning the development of a comprehensive set of basic requirements for nuclear power plant safety, and the associated reliability requirements, which would be internationally acceptable, and could serve as a standard frame of reference for nuclear plant safety and reliability analyses

Exchange of dose data within nuclear activities in Finland and Sweden

International Nuclear Information System (INIS)

Vilkamo, O.; Malmqvist, L.

1988-01-01

In the Nordic countries, Denmark, Finland, Iceland, Norway and Sweden, only Sweden and Finland have introduced nuclear power into energy production. The first still operating nuclear power plant was commissioned in Sweden in 1972 and in Finland in 1977. It was soon noticed that there was a growing tendency that small groups of workers used to move at short notice between Finland and Sweden to work in the nuclear power plants in both countries during maintenance periods. In 1983, the regulatory authorities for radiation protection, National Institute of Radiation Protection in Sweden and Finnish Centre for Radiation and Nuclear Safety in Finland, surveyed the radiation exposure to those workers. The authorities have brought about an arrangement by means of which the central dose data bases in the other country since 1984 have been able to record without delay the radiation doses received by her own citizens in the nuclear power plants of the neighbouring country. In addition, the authorities have confirmed the procedures of controlling dose data on workers from the neighbouring country, before those workers start working in a nuclear power plant regulated by the national authorities in question. The paper describes the starting point of the activity, the established practice and the experience achieved. Until now, the practical experiences are positive. The total radiation exposure to the workers in the Swedish and Finnish nuclear power plants has been relatively low at each plant site. Thus, the main objective in the exchange of dose data, is to achieve a good radiation protection control

Summary of nuclear power plant construction

International Nuclear Information System (INIS)

Tamura, Saburo

1973-01-01

Various conditions for the construction of nuclear power plants in Japan without natural resources were investigated. Expansion of the sites of plants, change of reactor vessels, standardization of nuclear power plants, possiblity of the reduction of construction period, approaching of nuclear power plants to consuming cities, and group construction were studied. Evaluation points were safety and economy. Previous sites of nuclear power plants were mostly on plane ground or cut and enlarge sites. Proposals for underground or offshore plants have been made. The underground plants were made at several places in Europe, and the ocean plant is now approved in U.S.A. as a plant on a man-made island. Vessels for containing nuclear reactors are the last barriers to the leakage of radioactive substance. At the initial period, the vessels were made of steel, which were surrounded by shielding material. Those were dry well type containers. Then, vessel type changed to pressure-suppression type wet containers. Now, it tends to concrete (PC or RC) type containers. There is the policy on the standardization of nuclear power plants by U.S.A.E.C. in recent remarkable activity. The merit and effect of the standardization were studied, and are presented in this paper. Cost of the construction of nuclear power plants is expensive, and interest of money is large. Then, the reduction of construction period is an important problem. The situations of plants approaching to consuming cities in various countries were studied. Idea of group construction is described. (Kato, T.)

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

1998-01-01

This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1997 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1997; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; forecasts; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

Nuclear power plant diagnostic system

International Nuclear Information System (INIS)

Prokop, K.; Volavy, J.

1982-01-01

Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

KWU Nuclear Plant Analyzer

International Nuclear Information System (INIS)

Bennewitz, F.; Hummel, R.; Oelmann, K.

1986-01-01

The KWU Nuclear Plant Analyzer is a real time engineering simulator based on the KWU computer programs used in plant transient analysis and licensing. The primary goal is to promote the understanding of the technical and physical processes of a nuclear power plant at an on-site training facility. Thus the KWU Nuclear Plant Analyzer is available with comparable low costs right at the time when technical questions or training needs arise. This has been achieved by (1) application of the transient code NLOOP; (2) unrestricted operator interaction including all simulator functions; (3) using the mainframe computer Control Data Cyber 176 in the KWU computing center; (4) four color graphic displays controlled by a dedicated graphic computer, no control room equipment; and (5) coupling of computers by telecommunication via telephone

On present situation of radioactive waste management and exposure of workers in nuclear reactor facilities for commercial power generation in fiscal 1988

International Nuclear Information System (INIS)

1989-01-01

The article summarizes the contents of some reports including the Report on Radiation Management in 1988 that were submitted by the operators of nuclear reactor facilities for commercial power generation according to the requirements specified in the Law Concerning Regulation on Nuclear Material, Nuclear Fuel and Nuclear Reactor. According to these reports, the annual radiation release in all nuclear power generation plants was well below the radiation release limits set up in the report 'On Guidelines for Target Dose in Areas around Light Water Reactor Facilities for Power Generation'. Data submitted also show that there are no significant problems with the management of radioactive solid waste. In all nuclear generation plants, the personal exposure of workers is below the permissible exposure dose specified in law. The Agency of Natural Resources and Energy is planned to further promote the development of advanced techniques for automatization and remote control of light water reactors and to provide effective guidance to electrical contractors for positive radiation management. (N.K.)

Nuclear accidents and safety measures of domestic nuclear power plants

International Nuclear Information System (INIS)

Song Zurong; Che Shuwei; Pan Xiang

2012-01-01

Based on the design standards for the safety of nuclear and radiation in nuclear power plants, the three accidents in the history of nuclear power are analyzed. And the main factors for these accidents are found out, that is, human factors and unpredicted natural calamity. By combining the design and operation parameters of domestic nuclear plants, the same accidents are studied and some necessary preventive schemes are put forward. In the security operation technology of domestic nuclear power plants nowadays, accidents caused by human factors can by prevented completely. But the safety standards have to be reconsidered for the unpredicted neutral disasters. How to reduce the hazard of nuclear radiation and leakage to the level that can be accepted by the government and public when accidents occur under extreme conditions during construction and operation of nuclear power plants must be considered adequately. (authors)

Perspectives of nuclear power plants

International Nuclear Information System (INIS)

Vajda, Gy.

2001-01-01

In several countries the construction of nuclear power plants has been stopped, and in some counties several plants have been decommissioned or are planned to. Therefore, the question arises: have nuclear power plants any future? According to the author, the question should be reformulated: can mankind survive without nuclear power? To examine this challenge, the global power demand and its trends are analyzed. According to the results, traditional energy sources cannot be adequate to supply power. Therefore, a reconsideration of nuclear power should be imminent. The economic, environmental attractions are discussed as opposite to the lack of social support. (R.P.)

The value of cytogenetic monitoring versus film dosimetry in the hot zone of a nuclear power plant

International Nuclear Information System (INIS)

Kubelka, D.; Fucic, A.; Milkovic-Kraus, S.

1992-01-01

Cytogenetic analysis was carried out in 41 workers prior to and following regular maintenance work in a nuclear power plant. Although film dosimetry did not show the maximal annual permitted dose in any of the examined subjects, cytogenetic analysis carried out following the work detected dicentric chromosomes in peripheral blood lymphocytes of 20 workers. According to our findings smoking habits and previous exposure to ionizing radiation had no effect on the increased number of chromosomal aberrations. (author). 23 refs.; 1 tab

Off-shore nuclear power plant

International Nuclear Information System (INIS)

Nakanishi, T.

1980-01-01

In order to avoid losses of energy and seawater pollution an off-shore nuclear power plant is coupled with a power plant which utilizes the temperature difference between seawater and hot reactor cooling water. According to the invention the power plant has a working media loop which is separated from the nuclear power plant. The apparative equipment and the operational characteristics of the power plant are the subject of the patent. (UWI) [de

Incidence and mortality by cancer among French nuclear workers of contracting companies

International Nuclear Information System (INIS)

Guerin, S.; Haddy, N.; Giardini, M.; Paoletti, C.; De Vathaire, F.

2006-01-01

Full text of publication follows: Current radiation protection standards of occupationally exposed workers are based on an extrapolation of cancer risks estimates derived from studies of the survivors of atomic bombings in Hiroshima and Nagasaki. In order to confirm these standards, International Agency for Research Cancer coordinated a retrospective cohort study to estimate the risk of cancer death after low-level exposure to gamma-ray, in a worldwide population of 400 000 nuclear industry workers in 15 countries. Methods: The present study is part of the international study and includes about 13,000 French nuclear industry workers of 10 contracting companies and subsidiary companies. This study was restricted to workers who wore a radiation dosimeter or badge. Contracting companies were selected on the basis of at least 100 workers in activity in 1996. A retrospective cohort was constituted. For each worker, we collected data concerning personal identifiers, occupational history, exposure history, vital status and cause of death. In order to guarantee the reliability of dosimetry data, we confronted monthly doses of X and gamma rays obtained from each company with monthly doses obtained from the National Institute of Radio Protection (I.R.S.N.). The cut off date was the 31 December of 2000. An incidence study is running within this cohort. Data relatives to poly-exposures, incident cancers and other pathologies, have being collected through a questionnaire form. Results: A total of 12,690 workers were included in the cohort, 1,457 could not be identified. Among the 11,233 identified workers, 280 deaths were recorded and 36% of them were cancer. Most of the workers were men (96%) and the median age at cut off date was equal to 41 years old. Only 25% of workers were exposed seven years or more. The median cumulative dose was equal to 3.1 mSv and 25% of workers had a cumulative dose superior to 22 mSv. Conclusion: Median cumulative dose was lower than expected as

Plant life management optimized utilization of existing nuclear power plants

International Nuclear Information System (INIS)

Watzinger, H.; Erve, M.

1999-01-01

For safe, reliable and economical nuclear power generation it is of central importance to understand, analyze and manage aging-related phenomena and to apply this information in the systematic utilization and as-necessary extension of the service life of components and systems. An operator's overall approach to aging and plant life management which also improves performance characteristics can help to optimize plant operating economy. In view of the deregulation of the power generation industry with its increased competition, nuclear power plants must today also increasingly provide for or maintain a high level of plant availability and low power generating costs. This is a difficult challenge even for the newest, most modern plants, and as plants age they can only remain competitive if a plant operator adopts a strategic approach which takes into account the various aging-related effects on a plant-wide basis. The significance of aging and plant life management for nuclear power plants becomes apparent when looking at their age: By the year 2000 roughly fifty of the world's 434 commercial nuclear power plants will have been in operation for thirty years or more. According to the International Atomic Energy Agency, as many as 110 plants will have reached the thirty-year service mark by the year 2005. In many countries human society does not push the construction of new nuclear power plants and presumably will not change mind within the next ten years. New construction licenses cannot be expected so that for economical and ecological reasons existing plants have to be operated unchallengeably. On the other hand the deregulation of the power production market is asking just now for analysis of plant life time to operate the plants at a high technical and economical level until new nuclear power plants can be licensed and constructed. (author)

Building of nuclear power plant

International Nuclear Information System (INIS)

Saito, Takashi.

1997-01-01

A first nuclear plant and a second nuclear power plant are disposed in adjacent with each other in a building for a nuclear reactor. A reactor container is disposed in each of the plants, and each reactor container is surrounded by a second containing facility. A repairing chamber capable of communicating with the secondary containing facilities for both of the secondary containing facilities is disposed being in contact with the second containing facility of each plant for repairing control rod driving mechanisms or reactor incorporated-type recycling pumps. Namely, the repairing chamber is in adjacent with the reactor containers of both plants, and situated between both of the plants as a repairing chamber to be used in common for both plants. Air tight inlet/exit doors are formed to the inlets/exits of both plants of the repairing chamber. Space for the repairing chamber can be reduced to about one half compared with a case where the repairing chamber is formed independently on each plant. (I.N.)

Nuclear Power Plants. Revised.

Science.gov (United States)

Lyerly, Ray L.; Mitchell, Walter, III

This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. Among the topics discussed are: Why Use Nuclear Power?; From Atoms to Electricity; Reactor Types; Typical Plant Design Features; The Cost of Nuclear Power; Plants in the United States; Developments in Foreign…

75 FR 66802 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

Science.gov (United States)

2010-10-29

... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; Notice of Withdrawal of...) has granted the request of Calvert Cliffs Nuclear Power Plant, LLC, the licensee, to withdraw its... for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, located in Calvert County, MD. The...

Electromagnetic compatibility of nuclear power plants

International Nuclear Information System (INIS)

Cabayan, H.S.

1983-01-01

Lately, there has been a mounting concern about the electromagnetic compatibility of nuclear-power-plant systems mainly because of the effects due to the nuclear electromagnetic pulse, and also because of the introduction of more-sophisticated and, therefore, more-susceptible solid-state devices into the plants. Questions have been raised about the adequacy of solid-state-device protection against plant electromagnetic-interference sources and transients due to the nuclear electromagnetic pulse. In this paper, the author briefly reviews the environment, and the coupling, susceptibility, and vulnerability assessment issues of commercial nuclear power plants

Nuclear power plants in populated areas

International Nuclear Information System (INIS)

Wachsmann, F.

1973-01-01

The article first deals with the permanently increasing demand for electical power. Considering the ever growing energy demand which can no longer be covered by conventional power plants, it has become necessary to set up nuclear power plants of larger range. The author presents in a survey the basic function of nuclear power plants as well as the resulting risks and safety measures. The author concludes that according to present knowledge there is no more need to erect nuclear power plants outside densely populated urban areas but there is now the possibility of erecting nuclear power plants in densely populated areas. (orig./LH) [de

Determination of external doses due to the melting of radioactively contaminated steel from nuclear facility in studsvik plant

International Nuclear Information System (INIS)

Brun-Yaba, Ch.; Menon, Sh.; Bjerler, J.; Wirendal, B.

2002-01-01

Radioactively contaminated material arises in many industries, both nuclear and non-nuclear. This material may be re-used, recycled or disposed of in a landfill. This project deals with low-level contaminated scrap recycling in a melting plant. The purpose is to register the radiation dose uptake by workers in the melting plant for practical scenarios and to compare these values to the results of computer calculation code for the same scenarios. In a recent past, dose evaluation studies have been done with codes but, often, the predictions are not exactly compared with the industrial practices measurements

[Influencing factors for hearing loss in workers exposed to noise in a cement plant].

Science.gov (United States)

Wang, X M; Wu, H; Jiao, J; Li, Y H; Zhang, Z R; Zhou, W H; Yu, S F

2016-12-20

Objective: To investigate the incidence of noise-induced hearing loss (NIHL) and related influencing factors in workers exposed to noise in a cement plant. Methods: In October 2015, cluster sampling was used for questionnaire investigation and health examination of workers exposed to noise in a cement plant in Henan Province, China. The association of demographic features, living habits, cumulative noise exposure (CNE) , hypertension, and hyperlipidemia with NIHL was analyzed. Results: There was mainly medium-or high-frequency noise in the working place of this cement plant. The prevalence rate of NIHL was 18.4%, and male workers had a significantly higher prevalence rate than female workers (χ(2)=28.09, P workers who smoked had a significantly higher prevalence rate of NIHL than those who did not smoke (χ(2)=14.15, P workers with a drinking habit had a significantly higher prevalence rate of NIHL than those without such habit (χ(2)=7.95, P workers who did not wear earplugs had a significantly higher prevalence rate of NIHL than those who wore earplugs (χ(2)=19.93, P workers with hyperlipidemiahad a significantly higher prevalence rate of NIHL than those without hyperlipidemia (χ(2)=12.43, P workers in a cement plant have a high prevalence rate of NIHL, and CNE, sex, age, degree of education, use of earplugs, and hyperlipidemia may be influencing factors for NIHL.

Nuclear Security for Floating Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Skiba, James M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-10-13

Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

Nuclear power plants in the world - 2010 edition

International Nuclear Information System (INIS)

2010-01-01

This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2009 highlights, Main characteristics of reactor types, Map of the French nuclear power plants on 2010/01/01, Worldwide status of nuclear power plants (12/31/2009), Units distributed by countries, Nuclear power plants connected to the Grid- by reactor type groups, Nuclear power plants under construction on 2009, Evolution of nuclear power plants capacities connected to the grid, First electric generations supplied by a nuclear unit in each country, Electrical generation from nuclear power plants by country at the end 2009, Performance indicator of french PWR units, Evolution of the generation indicators worldwide by type, Nuclear operator ranking according to their installed capacity, Units connected to the grid by countries at 12/31/2009, Status of licence renewal applications in USA, Nuclear power plants under construction at 12/31/2009, Shutdown reactors, Exported nuclear capacity in net MWe, Exported and national nuclear capacity connected to the grid, Exported nuclear power plants under construction, Exported and national nuclear capacity under construction, Nuclear power plants ordered at 12/31/2009, Long term shutdown units at 12/31/2009, COL applications in the USA, Recycling of Plutonium in reactors and experiences, Mox licence plants projects, Appendix - historical development, Meaning of the used acronyms, Glossary

Temporary worker in the nuclear power industry: an equity analysis

International Nuclear Information System (INIS)

Melville, M.H.

1981-01-01

There are clear indications based both on the statistical data and on empirical evidence that the employment of large numbers of temporary workers has become a permanent and growing characteristic of the industry. It appears that the size of that work force has been seriously underestimated and that it receives a disproportionate share of the occupational radiation. In order to stay within the limits governing individual exposure in the workplace, the risk has been spread among a larger segment of the population. These facts raise important and ongoing issues of societal and employer responsibility. By the reckonings of this study, the total number of workers employed on a temporary basis by the nuclear power industry is eighteen times greater than those much more narrowly defined by the Nuclear Regulatory Commission (NRC) as transient workers: individuals hired and terminating employment with two or more employers in one quarter. It is estimated that the whole temporary work force numbered about 23,520 in 1976, over a third (35%) of the industry total, and absorbed 47.5% of the total occupational radiation dose. The problems, then, are not inconsiderable: they affect thousands of individuals, a significant segment of the nuclear power industry's work force, members of society who are subjected to a disproportionate burden of radiation risk. Among the conclusions is that it may be necessary to establish special standards, limitations, and records for temporary workers to ensure adequate health protection, follow-up, and care

Organisation of radiation protection at Sizewell Nuclear Power Plant in the UK. Report n. 290

International Nuclear Information System (INIS)

Crouail, P.; Jeannin, B.; Lefaure, C.; Panisset, L.

2004-01-01

This report first describes the organisation and management of radiation protection at Sizewell Nuclear Power Plant (UK): general organisation, organisation of the radiation protection department, goals of radiation protection at plant and corporate levels, measurement of radiation protection performance, presence of health physicists in the plant, national and international comparisons. Then, it addresses the training of workers and radiation protection specialists with respect to radiation protection, the management of zoning and surveillance (action to address the radiation risk and the contamination risk). It describes the relationships of Health physicists with contractors and other workers teams, and the relationships with safety authorities. It indicates the different outages of this organisation: general planning, information sheets, physicists work planning, reviews and meetings. It describes the management of personal dosimetry with radiation work permits and actions aimed at the reduction of doses during various operations. The last part proposes a feedback experience report and evokes the generated database, and addresses events reporting

Nuclear plant life - A business decision

International Nuclear Information System (INIS)

Joosten, J.K.

1995-01-01

Regarding the future of the nuclear power option, many scenarios have been put forth over the years. The most commonly accepted projections for installed nuclear capacity show it growing at a rate of about 2% per year throughout the next few decades. These projections appear modes on the surface. However, underlying the projections are critical assumptions and sometimes misconceptions about the lifetimes of existing reactors and how they are determined. The notion of a 40 year plant life is very common. Consequently, many projections start either with the assumption that no plants will be retired in the near terms or with the assumption that each retired plant will be replaced by another nuclear plant after 40 years. Effectively, these assumptions yield future projections for installed capacity that might be characterized as low growth, medium growth and high growth scenarios - or grow, grow, grow. The question remains as to whether or not these assumptions accurately model the driving forces and constraints to nuclear development. After all, there is no scientific basis for believing that all plants, PWRs BWRs, RBMKs, etc., should have the same 40 year life. Most power plant owners purchase the plant for the main reason of supplying electrical power to their consumer. For these owners, electricity production is a day to day commercial activity with various alternatives on how to achieve the prime objective. The decision of which electricity generation alternative to select (gas, coal, nuclear or renewable energy) and how long to operate the plant before replacing it with a new one is essentially a business decision. The paper discusses ageing, the nuclear plant life decision process, the factors which influence the decision and their ramifications regarding the near term growth of nuclear power capacity. The modelling of nuclear plant lifetimes is also discussed. (author). 5 refs, 10 figs, 1 tab

Owners of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hudson, C.R.; White, V.S.

1996-11-01

Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of July 1996. The report is divided into sections representing different aspects of nuclear plant ownership.

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2000-01-01

This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1999 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1999; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; grid connection forecasts; world electric power market; electronuclear owners and share holders in EU, capacity and load factor; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; 1999 gross load factor by operator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

Advanced plant design recommendations from Cook Nuclear Plant experience

International Nuclear Information System (INIS)

Zimmerman, W.L.

1993-01-01

A project in the American Electric Power Service Corporation to review operating and maintenance experience at Cook Nuclear Plant to identify recommendations for advanced nuclear plant design is described. Recommendations so gathered in the areas of plant fluid systems, instrument and control, testing and surveillance provisions, plant layout of equipment, provisions to enhance effective maintenance, ventilation systems, radiological protection, and construction, are presented accordingly. An example for a design review checklist for effective plant operations and maintenance is suggested

Health effects of the nuclear accident at Three Mile Island

International Nuclear Information System (INIS)

Fabrikant, J.I.

1980-05-01

Between March 28 and April 15, 1979 the collective dose resulting from the radioactivity released to the population living within a 50-mile radius of the Three Mile Island nuclear plant was about 2000 person-rems, less than 1% of the annual natural background level. The average dose to a person living within 5 miles of the nuclear plant was less than 10% of annual background radiation. The maximum estimated radiation dose received by any one individual in the general population (excluding the nuclear plant workers) during the accident was 70 mrem. The doses received by the general population as a result of the accident were so small that there will be no detectable additional cases of cancer, developmental abnormalities, or genetic ill-health. Three Three Mile Island nuclear workers received radiation doses of about 3 to 4 rem, exceeding maximum permissible quarterly dose of 3 rem. The major health effect of the accident at Three Mile Island was that of a pronounced demoralizing effect on the general population in the Three Mile Island area, including teenagers and mothers of preschool children and the nuclear plant workers. However, this effect proved transient in all groups studied except the nuclear workers

Human factors estimation methods in nuclear power plant

International Nuclear Information System (INIS)

Takano, Kenichi; Yoshino, Kenji; Nagasaka, Akihiko; Ishii, Keichiro; Nakasa, Hiroyasu

1985-01-01

To improve the operational and maintenance work reliability, it is neccessary for workers to maintain his performance always at high level, that leads to decreasing mistaken judgements and operations. This paper inuolves the development and evaluation of ''Multi-Purpose Physiological Information Measurement system'' to estimate human performance and conditions with a highly fixed quantity. The following itemes is mentioned : (1) Most suitable physiological informations are selected to measure worker' performance in nuclear power plant with none-disturbance, ambulatory, continual, and multi channel measurement. (2) Relatively important physiological informations are measured with the real-time monitoring functions. (electrocardiogram, respirometric functions and EMG (electromyogram) pulse rete). (3) It is made to optimize the measurement condition and analysing methods in the use of a noise-cut function and a D.C. drift cutting method. (4) As a example, it is clear that, when the different weight is loaded to the arm and make it strech-bend motion, the EMG signal is measured and analysed by this system, the analysed EMG pulse rate and maximum amplitude is related to the arm loaded weight. (author)

Elecnuc. Nuclear power plants worldwide

International Nuclear Information System (INIS)

1998-01-01

This small folder presents a digest of some useful information concerning the nuclear power plants worldwide and the situation of nuclear industry at the end of 1997: power production of nuclear origin, distribution of reactor types, number of installed units, evolution and prediction of reactor orders, connections to the grid and decommissioning, worldwide development of nuclear power, evolution of power production of nuclear origin, the installed power per reactor type, market shares and exports of the main nuclear engineering companies, power plants constructions and orders situation, evolution of reactors performances during the last 10 years, know-how and development of nuclear safety, the remarkable facts of 1997, the future of nuclear power and the energy policy trends. (J.S.)

Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

International Nuclear Information System (INIS)

Satoh, Yoshinori; Li, Ye; Zhu, Xuefeng; Rizwan, Uddin

2014-01-01

Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor

Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Satoh, Yoshinori; Li, Ye; Zhu, Xuefeng; Rizwan, Uddin [University of Illinois, Urbana (United States)

2014-08-15

Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor.

The ''healthy worker effect'' and other determinants of mortality in workers in the nuclear industry

International Nuclear Information System (INIS)

Beral, V.; Carpenter, L.; Booth, M.; Inskip, H.; Brown, A.

1987-01-01

Workers in the nuclear industry has been found to have lower mortality rates than the national average. This is in part due to the ''healthy worker effect'' - the recruitment of healthy individuals into the workforce. Employees of the United Kingdom Atomic Energy Authority had especially low mortality rates in the 15 years following first employment. Thereafter mortality rates remained about 20% below the national average. Social class was a clear predictor of mortality, the professional and executive classes (Social Classes I and II) having mortality rates about 40% below the national average. Mortality was not related to duration of employment. Radiation and non-radiation workers generally showed similar patterns of mortality. (author)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-02-01

During the third quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. The annual maintenance outages of the Loviisa plant units were held during the report period. All events during this quarter are classified as Level hero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were below authorised limits. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

TOSHIBA CAE system for nuclear power plant

International Nuclear Information System (INIS)

Machiba, Hiroshi; Sasaki, Norio

1990-01-01

TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plant using Computer Aided Engineering (CAE). TOSHIBA CAE system for nuclear power plant consists of numbers of sub-systems which had been integrated centering around the Nuclear Power Plant Engineering Data Base (PDBMS) and covers all stage of engineering for nuclear power plant from project management, design, manufacturing, construction to operating plant service and preventive maintenance as it were 'Plant Life-Cycle CAE System'. In recent years, TOSHIBA has been devoting to extend the system for integrated intelligent CAE system with state-of-the-art computer technologies such as computer graphics and artificial intelligence. This paper shows the outline of CAE system for nuclear power plant in TOSHIBA. (author)

Operation and maintenance of nuclear power plants

International Nuclear Information System (INIS)

Ackermann, G.

1987-01-01

This textbook gives a systematic introduction into the operational and maintenance activities in nuclear power plants with pressurized water reactors. Subjects: (1) Setup and operational behaviour of power reactors, (2) setup of nuclear power plants, (3) radiation protection and nuclear safety, (4) nuclear fuel, (5) constructional layout of nuclear power plants, (6) management, and (7) maintenance. 158 figs., 56 tabs

Consequences of the nuclear power plant accident at Chernobyl

International Nuclear Information System (INIS)

Ginzburg, H.M.; Reis, E.

1991-01-01

The Chernobyl Nuclear Power Plant accident, in the Ukrainian Soviet Socialist Republic (SSR), on April 26, 1986, was the first major nuclear power plant accident that resulted in a large-scale fire and subsequent explosions, immediate and delayed deaths of plant operators and emergency service workers, and the radioactive contamination of a significant land area. The release of radioactive material, over a 10-day period, resulted in millions of Soviets, and other Europeans, being exposed to measurable levels of radioactive fallout. Because of the effects of wind and rain, the radioactive nuclide fallout distribution patterns are not well defined, though they appear to be focused in three contiguous Soviet Republics: the Ukrainian SSR, the Byelorussian SSR, and the Russian Soviet Federated Socialist Republic. Further, because of the many radioactive nuclides (krypton, xenon, cesium, iodine, strontium, plutonium) released by the prolonged fires at Chernobyl, the long-term medical, psychological, social, and economic effects will require careful and prolonged study. Specifically, studies on the medical (leukemia, cancers, thyroid disease) and psychological (reactive depressions, post-traumatic stress disorders, family disorganization) consequences of continued low dose radiation exposure in the affected villages and towns need to be conducted so that a coherent, comprehensive, community-oriented plan may evolve that will not cause those already affected any additional harm and confusion

The Assessment of I-131 Internal Doses of Nuclear Medicine Workers in Korea Using Thyroid uptake system

International Nuclear Information System (INIS)

Bahn, Young Kag; Oh, Gi Back; Lee, Chang Ho; Lee, Jong Doo; Yeom, Yu Sun; Hwang, Young Muk

2012-01-01

There are possibilities the radiation workers could intake the radiation when workers deal with radiation-materials. Therefore, internal radiation doses of radiation workers need to be assessed. Although an application of the nuclear medicine is continuously increased in Korea, there is not a proper tool and form to monitor the internal doses of nuclear medicine workers. However, it is possible to attain the internal doses of I-131 to evaluate using thyroid uptake and well count system. In this study, we measured and evaluated the I-131 internal doses of nuclear medicine workers in Korea using thyroid uptake and well count system and performed an air sampling

Nuclear plant scram reduction

International Nuclear Information System (INIS)

Wiegle, H.R.

1986-01-01

The Nuclear Utility Management and Human Resources Committee (NUMARC) is a confederation of all 55 utilities with nuclear plants either in operation or under construction. NUMARC was formed in April 1984 by senior nuclear executives with hundreds of man-years of plant experience to improve (plant) performance and resolve NRC concerns. NUMARC has adopted 10 commitments in the areas of management, training, staffing and performance. One of these commitments is to strive to reduce automatic trips to 3 per year per unit for calendar year 1985 for plants in commercial operation greater than 3 years (with greater than 25% capacity factor). This goal applies to any unplanned automatic protection system trips at any time when the reactor is critical. Each utility has committed to develop methods to thoroughly evaluate all unplanned automatic trips to identify the root causes and formulate plans to correct the root causes thus reducing future unplanned scrams. As part of this program, the Institute of Nuclear Power Operations (INPO) collects and evaluates information on automatic reactor trips. It publishes the results of these evaluations to aid the industry to identify root causes and corrective actions

Effects of nuclear electromagnetic pulse (EMP) on nuclear power plants

International Nuclear Information System (INIS)

Barnes, P.R.; Manweiler, R.W.; Davis, R.R.

1977-09-01

The electromagnetic pulse (EMP) from a high-altitude nuclear detonation consists of a transient pulse of high intensity electromagnetic fields. These intense fields induce current and voltage transients in electrical conductors. Although most nuclear power plant cables are not directly exposed to these fields, the attenuated EMP fields that propagate into the plant will couple some EMP energy to these cables. The report predicts the probable effects of the EMP transients that could be induced in critical circuits of safety-related systems. It was found that the most likely consequence of EMP for nuclear plants is an unscheduled shutdown. EMP could prolong the shutdown period by the unnecessary actuation of certain safety systems. In general, EMP could be a nuisance to nuclear power plants, but it is not considered a serious threat to plant safety

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-09-01

Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear safety and radiation protection which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Safety-enhancing modifications at the nuclear power plants and issues relating to the use of nuclear energy which are of general interest are also reported. The reports include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the first quarter of 1993, a primary feedwater system pipe break occurred at Loviisa 2, in a section of piping after a feedwater pump. The break was erosion-corrosion induced. Repairs and inspections interrupted power generation for seven days. On the International Nuclear Event Scale the event is classified as a level 2 incident. Other events in the first quarter of 1993 had no bearing on nuclear safety and radiation protection

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1991-12-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO 1 and II were in operation for almost the whole second quarter of 1991. The load factor average was 87.4 %. In consequence of a fire, which broke out in the switchgear building, connections to both external grids were lost and TVO II relied on power supplied by four back-up diesels for 7.5 hrs. The event is classified as Level 2 on the International Nuclear Event Scale. The process of examining the non-leaking fuel bundles removed from the Loviisa nuclear reactors has continued. The examinations have revealed, so far, that the uppermost spacing lattices of the bundles exhibit deformations similar to those detected in the leaking fuel bundles removed from the reactors. This event is classified as Level 1 on the International Nuclear Event Scale. Other events in this quarter which are classified according to the International Nuclear Event Scale are Level Zero (Below Scale) on the Scale. The Finnish Centre for Radiation and Nuclear Safety has assessed the safety of the Loviisa and Olkiluoto nuclear power plants based on the new regulations issued on 14.2.1991 by the Council of State. The safety regulations are much more stringent than those in force when the Loviisa and Olkiluoto nuclear power plants were built. The assessment indicated that the TVO nuclear power plant meets these safety regulations. The Loviisa nuclear power plant meets the requirements with the exception of certain requirements related to the ensuring of safety functions and provision for accidents. At the Loviisa nuclear power plant there are several projects under consideration to enhance safety

Nuclear power plants maintenance

International Nuclear Information System (INIS)

Anon.

1988-01-01

Nuclear power plants maintenance now appears as an important factor contributing to the competitivity of nuclea energy. The articles published in this issue describe the way maintenance has been organized in France and how it led to an actual industrial activity developing and providing products and services. An information note about Georges Besse uranium enrichment plant (Eurodif) recalls that maintenance has become a main data not only for power plants but for all nuclear industry installations. (The second part of this dossier will be published in the next issue: vol. 1 January-February 1989) [fr

Cooling towers of nuclear power plants

International Nuclear Information System (INIS)

Mikyska, L.

1986-01-01

The specifications are given of cooling towers of foreign nuclear power plants and a comparison is made with specifications of cooling towers with natural draught in Czechoslovak nuclear power plants. Shortcomings are pointed out in the design of cooling towers of Czechoslovak nuclear power plants which have been derived from conventional power plant design. The main differences are in the adjustment of the towers for winter operation and in the designed spray intensity. The comparison of selected parameters is expressed graphically. (J.B.)

The operation of nuclear power plants

International Nuclear Information System (INIS)

Brosche, D.

1992-01-01

The duties to be performed in managing the operation of a nuclear power plant are highly diverse, as will be explained in this contribution by the examples of the Grafenrheinfeld Nuclear Power Station. The excellent safety record and the high availabilities of German nuclear power plants demonstrate that their operators have adopted the right approaches. Systematic evaluation of the operating experience accumulated inhouse and in other plants is of great significance in removing weak spots and improving operation. The manifold and complex activities in the structure of organization and of activities in a nuclear power plant require a high degree of division of labor. (orig.) [de

4. Nuclear power plant component failures

International Nuclear Information System (INIS)

1990-01-01

Nuclear power plant component failures are dealt with in relation to reliability in nuclear power engineering. The topics treated include classification of failures, analysis of their causes and impacts, nuclear power plant failure data acquisition and processing, interdependent failures, and human factor reliability in nuclear power engineering. (P.A.). 8 figs., 7 tabs., 23 refs

Preparation and practice for nuclear power plant operation

International Nuclear Information System (INIS)

Wu Xuesong; Lu Tiezhong

2015-01-01

The operational preparation of the nuclear power plant is an important work in nuclear power plant production preparation. Due to the construction period of nuclear power plant from starting construction to production is as long as five years, the professional requirements of nuclear power operation are very strict, and the requirements for nuclear safety are also extremely high. Especially after the Fukushima accident, higher requirements for the safe operation of nuclear power plant are posed by competent authorities of the national level, regulatory authorities and each nuclear power groups. Based on the characteristics of the construction phase of nuclear power plant and in combination with engineering practice, this paper expounds the system established in the field of nuclear power plant operation and generally analyses the related management innovation. (authors)

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-06-01

Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

Nuclear Power Plant Lifetime Management Study (I)

Energy Technology Data Exchange (ETDEWEB)

Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1997-12-31

As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

Nuclear Power Plant Lifetime Management Study (I)

Energy Technology Data Exchange (ETDEWEB)

Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-12-31

As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

Micronuclei Frequencies in Lymphocytes of Nuclear Malaysia Radiation Workers

International Nuclear Information System (INIS)

Mohd Rodzi Ali; Aisyah Mohd Yusof; Rahimah Abdul Rahim; Juliana Mahamat Napiah; Yahaya Talib; Shafii Khamis

2016-01-01

The objective of the study is to investigate the frequency of cell aberration in lymphocytes of the Nuklear Malaysia radiation workers. A total of 58 blood samples were collected from the radiation workers during their routine medical examination. The donor age range is between 23 to 58 years, 31 male and 27 female. Blood samples were cultured according to the standard protocol recommended by the International Atomic Energy Agency. The mean micronuclei (MN) is 23.5 ± 0.9 MN/ 1000 binucleate, with the median value of 24 MN/ 1000 binucleate. The lowest number of MN was 9, and the highest was 43. There is no correlation between the number of MN in blood and yearly cumulative dose for radiation workers. The results indicate the MN expression due to small radiation exposure is almost negligible in Nuclear Malaysia radiation workers. (author)

Real-time assessment of exposure dose to workers in radiological environments during decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Jeong, KwanSeong; Choi, ByungSeon; Moon, JeiKwon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kim, GeunHo; Seo, JaeSeok; Jeong, SeongYoung; Lee, JungJun; Song, HaeSang; Lee, SangWha; Son, BongKi

2014-01-01

Highlights: • The method of exposure dose assessment to workers during decommissioning of nuclear facilities. • The environments of simulation were designed under a virtual reality. • To assess exposure dose to workers, human model was developed within a virtual reality. - Abstract: This objective of this paper is to develop a method to simulate and assess the exposure dose to workers during decommissioning of nuclear facilities. To simulate several scenarios, decommissioning environments were designed using virtual reality. To assess exposure dose to workers, a human model was also developed using virtual reality. The exposure dose was measured and assessed under the principle of ALARA in accordance with radiological environmental change. This method will make it possible to plan for the exposure dose to workers during decommissioning of nuclear facilities

Nuclear plant life extension

International Nuclear Information System (INIS)

Negin, C.A.

1989-01-01

The nuclear power industry's addressing of life extension is a natural trend in the maturation of this technology after 20 years of commercial operation. With increasing emphasis on how plants are operated, and less on how to build them, attention is turning on to maximizing the use of these substantial investments. The first studies of life extension were conducted in the period from 1978 and 1982. These were motivated by the initiation, by the Nuclear Regulatory Commission (NRC), of studies to support decommissioning rulemaking. The basic conclusions of those early studies that life extension is feasible and worth pursuing have not been changed by the much more extensive investigations that have since been conducted. From an engineering perspective, life extension for nuclear plants is fundamentally the same as for fossil plants

NUCLEAR POWER PLANT

Science.gov (United States)

Carter, J.C.; Armstrong, R.H.; Janicke, M.J.

1963-05-14

A nuclear power plant for use in an airless environment or other environment in which cooling is difficult is described. The power plant includes a boiling mercury reactor, a mercury--vapor turbine in direct cycle therewith, and a radiator for condensing mercury vapor. (AEC)

QA programs in nuclear power plants

International Nuclear Information System (INIS)

Ellingson, A.C.

1976-01-01

As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

Employment policies at the plant level : job and worker flows for heterogeneous labour in Norway

OpenAIRE

Salvanes, Kjell Gunnar

1999-01-01

Despite the large degree of plant-specific heterogeneity in turnover patterns recently found in the gross job and worker literature, very little is known about the sources of the heterogeneity in plant level employment policies. The present paper, studies in detail the employment management policies for heterogeneous plants and for heterogeneous labour, using a matched worker-employer data set for Norway. Within an econometric framework, I find that the job and worker flows above ...

Severe accident management: radiation dose control, Fukushima Daiichi and TMI-2 nuclear plant accidents

International Nuclear Information System (INIS)

Shaw, Roger

2014-01-01

This presentation presents valuable dose information related to the Fukushima Daiichi and Three Mile Island Unit 2 (TMI-2) Nuclear Plant accidents. Dose information is provided for what is well known for TMI-2, and what is available for Fukushima Daiichi. Particular emphasis is placed on the difference between the type of reactors involved, overarching plant damage issues, and radiation worker dose outcomes. For TMI-2, more in depth dose data is available for the accident and the subsequent recovery efforts. The comparisons demonstrate the need to understand the wide variation in potential dose management measures and outcomes for severe reactor accidents. (author)

Radiation dose assessment in nuclear plants through virtual simulations using a game engine

International Nuclear Information System (INIS)

Jorge, Carlos A.F.; Mol, Antonio C. A.; Aghina, Mauricio Alves C.

2008-01-01

Full text: This paper reports an R and D which has the purpose of performing dose assessment of workers in nuclear plants, through virtual simulations using a game engine. The main objective of this R and D is to support the planning of operational and maintenance routines in nuclear plants, aiming to reduce the dose received by workers. Game engine is the core of a computer game, that is usually made independent of both the scenarios and the original applications, and thus can be adapted for any other purposes, including scientific or technological ones. Computer games have experienced a great development in the last years, regarding computer graphics, 3D image rendering and the representation of the physics needed for the virtual simulations, such as gravity effect and collision among virtual components within the games. Thus, researchers do not need to develop an entire platform for virtual simulations, what would be a hard work itself, but they can rather take advantage of such well developed platforms, adapting them for their own applications. The game engine used in this R and D is part of a computer game widely used, Unreal, that has its source code partially open, and can be pursued for low cost. A nuclear plant in our Institution, Argonauta research reactor, has been virtually modeled in 3D, and trainees can navigate virtually through it, with realistic walking velocity, and experiencing collision. The modified game engine computes and displays in real-time the dose received by a virtual person, the avatar, as it walks through the plant, from the radiation dose rate distribution assigned to the virtual environment. In the beginning of this R and D, radiation dose rate measurements were previously collected by the radiological protection service, and input off-line to the game engine. Currently, on-line measurements can be also input to it, by taking advantage of the game's networking capabilities. A real radiation monitor has been used to collect real

Atucha I nuclear power plant transients analysis

International Nuclear Information System (INIS)

Castano, J.; Schivo, M.

1987-01-01

A program for the transients simulation thermohydraulic calculation without loss of coolant (KWU-ENACE development) to evaluate Atucha I nuclear power plant behaviour is used. The program includes systems simulation and nuclear power plants control bonds with real parameters. The calculation results show a good agreement with the output 'protocol' of various transients of the nuclear power plant, keeping the error, in general, lesser than ± 10% from the variation of the nuclear power plant's state variables. (Author)

Guidelines for nuclear plant response to an earthquake

International Nuclear Information System (INIS)

1989-12-01

Guidelines have been developed to assist nuclear plant personnel in the preparation of earthquake response procedures for nuclear power plants. The objectives of the earthquake response procedures are to determine (1) the immediate effects of an earthquake on the physical condition of the nuclear power plant, (2) if shutdown of the plant is appropriate based on the observed damage to the plant or because the OBE has been exceeded, and (3) the readiness of the plant to resume operation following shutdown due to an earthquake. Readiness of a nuclear power plant to restart is determined on the basis of visual inspections of nuclear plant equipment and structures, and the successful completion of surveillance tests which demonstrate that the limiting conditions for operation as defined in the plant Technical Specifications are met. The guidelines are based on information obtained from a review of earthquake response procedures from numerous US and foreign nuclear power plants, interviews with nuclear plant operations personnel, and a review of reports of damage to industrial equipment and structures in actual earthquakes. 7 refs., 4 figs., 4 tabs

Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

International Nuclear Information System (INIS)

Demick, L.E.

2011-01-01

This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

Energy Technology Data Exchange (ETDEWEB)

L.E. Demick

2011-10-01

This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

Medium-size nuclear plants

International Nuclear Information System (INIS)

Vogelweith, L.; Lavergne, J.C.; Martinot, G.; Weiss, A.

1977-01-01

CEA (TECHNICATOME) has developed a range of pressurized water reactors of the type ''CAS compact'' which are adapted to civil ship propulsion, or to electric power production, combined possibly with heat production, up to outputs equivalent to 125 MWe. Nuclear plants equipped with these reactors are suitable to medium-size electric networks. Among the possible realizations, two types of plants are mentioned as examples: 1) Floating electron-nuclear plants; and 2) Combined electric power and desalting plants. The report describes the design characteristics of the different parts of a 125 MWe unit floating electro-nuclear plant: nuclear steam system CAS 3 G, power generating plant, floating platform for the whole plant. The report gives attention to the different possibilities according to site conditions (the plant can be kept floating, in a natural or artificial basin, it can be put aground, ...) and to safety and environment factors. Such unit can be used in places where there is a growing demand in electric power and fresh water. The report describes how the reactor, the power generating plant and multiflash distillation units of an electric power-desalting plant can be combined: choice of the ratio water output/electric power output, thermal cycle combination, choice of the gain ratio, according to economic considerations, and to desired goal of water output. The report analyses also some technical options, such as: choice of the extraction point of steam used as heat supply of the desalting station (bleeding a condensation turbine, or recovering steam at the exhaust of a backpressure turbine), design making the system safe. Lastly, economic considerations are dealt with: combining the production of fresh water and electric power provides usually a much better energy balance and a lower cost for both products. Examples are given of some types of installations which combine medium-size reactors with fresh water stations yielding from 10000 to 120000 m 3 per day

Regulatory issues for nuclear power plant life management

International Nuclear Information System (INIS)

Roe, J.

2000-01-01

The workshop of 26-27 june 2000, on nuclear power Plant LIfe Management (PLIM), also included working groups in which major issues facing PLIM activities for nuclear power plants were identified and discussed. The second group was on Regulation. The Regulatory Working Group will attempt to identify some of the more pertinent issues affecting nuclear plant regulation in a changing PLIM environment, to identify some possible actions to be taken to address these issues, and to identify some of the parties responsible for taking these actions. Some preliminary regulatory issues are noted below. This is not intended to be a comprehensive list of such issues but rather is intended to stimulate discussion among the experts attending this Workshop. One of the concerns in the regulatory arena is how the structural integrity of the plants can be assured for an extended lifetime. Technological advances directed toward the following are likely to be important factors in the regulatory process of life extension. - Preventive and corrective maintenance (e.g., water chemistry control, pressure vessel annealing, and replacement of core internals). - Ageing and degradation mechanisms and evaluation (e.g., embrittlement, wear, corrosion/erosion, fatigue, and stress corrosion). - Monitoring, surveillance, and inspection (e.g., fatigue monitoring and non-destructive testing). - Optimisation of maintenance (e.g., using risk-based analysis). On the business side, there is concern about technical support by manufacturers, fuel companies, and construction companies. Maintaining a strong technical base and skilled workers in a potentially declining environment is another concern in the regulatory community. Waste management and decommissioning remain significant issue regarding PLIM. These issues affect all three areas of concern - technology, business, and regulation. It is against this background, that the issues put forth in this paper are presented. The objective of presenting these

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-03-01

Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1990-12-01

During the second quarter of 1990 the Finnish nuclear plant units Loviisa 1 and 2 and TVO and II were in commercial operation for most of the time. The feedwater pipe rupture at Loviisa 1 and the resulting inspections and repairs at both Loviisa plant units brought about an outage the overall duration of which was 32 days. The annual maintenance outages of the TVO plant units were arranged during the report period and their combined duration was 31.5 days. Nuclear electricity accounted for 35.3% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 83.0%. Three events occurred during the report period which are classified as Level 1 on the International Nuclear Event Scale: feedwater pipe rupture at Loviisa 1, control rod withdrawal at TVO I in a test during an outage when the hydraulic scram system was rendered inoperable and erroneous fuel bundle transfers during control rod drives maintenance at TVO II. Other events during this quarter are classified as Level Zero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. Only small amounts of nuclides originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

Modelling of nuclear power plant decommissioning financing.

Science.gov (United States)

Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

2015-06-01

Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Epidemiological studies of radiation workers in nuclear facilities

International Nuclear Information System (INIS)

Iwai, Satoshi; Semba, Tsuyoshi; Ishida, Kenji; Takagi, Syunji; Igari, Takafumi

2017-01-01

Regarding workers at nuclear facilities, this paper described INWORKS epidemiological research published in 2015, cooperative cohort epidemiological research of IARC 15 countries 10 years before that (15-country study), and the flow of radiation epidemiological research in the period from 15-country study to INWORKS. INWORKS is a retrospective cohort study to investigate the correlation between mortality due to solid cancer, blood cancer, and cardiovascular diseases in workers in three countries of France / the U.K. / the U.S. and low dose exposure through long-term photon external exposure. It obtained the data showing the statistical significance of increased cancer death rate. However, from the subjects of the analysis, no significant evaluation was made on neutron exposure and internal exposure. Statistically significant cancer mortality was confirmed in 15-country study at low dose, low dose rate, and prolonged exposure, but significant cancer mortality rate could not be confirmed excluding Canadian data, which had problems in dose evaluation. In the epidemiological studies of cancer mortality rates of radiation workers in nuclear power industries performed in France / the U.K. / the U.S. in the period ranging from 15-country study to INWORKS, significant difference was not recognized between cancer death rate and excessive relative risk (ERR) compared with LSS epidemiological research studies that handled acute exposure. Several tasks are still remaining. (A.O.)

Radiation protection training for personnel at light-water-cooled nuclear power plants

International Nuclear Information System (INIS)

Anon.

1981-01-01

Section 19.12 Instructions to Workers, of 10 CFR Part 19, Notices, Instructions, and Reports to Workers; Inspections, requires that individuals be given instruction in radiation protection that is commensurate with the potential radiation protection problems they may encounter in restricted areas as defined in para. 19.3(e) of 10 CFR Part 19. Para. 20.1(c) of 10 CFR Part 20, Standards for Protection Against Radiation, states that occupational radiation exposure should be kept as low as is reasonably achievable (ALARA). Appropriate training is an essential aspect of an ALARA program. This guide describes a radiation protection training program consistent with the ALARA objective and acceptable to the NRC staff for meeting the training requirements of 10 CFR Part 19 with respect to individuals that enter restricted areas at nuclear power plants

IAEA Concludes Safety Review at Gravelines Nuclear Power Plant, France

International Nuclear Information System (INIS)

2012-01-01

Full text: An IAEA-led international team of nuclear safety experts noted a series of good practices and made recommendations to reinforce some safety measures during a review of operational safety at France's Gravelines Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 12 November 2012, focused on aspects essential to the safe operation of the NPP. The team was composed of experts from Bulgaria, China, Germany, Hungary, Japan, Romania, Slovakia, South Africa, Spain, Ukraine and the IAEA. The review covered the areas of management, organization and administration; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their possible use elsewhere. Examples include the following: - The Power Plant uses a staff-skills mapping process that significantly enhances knowledge of the facility's collective and individual skills and provides proactive management to address the loss of such skills; - As a measure to reduce the risk of workers' radiation exposure, the Power Plant uses a system to ensure that dose rate measurements are carried out at a precise distance from the source of radiation; and - Flood protection of the Power Plant is supported by special technical guidance documents and associated arrangements. The team identified a number of proposals for improvements to operational safety at Gravelines NPP. Examples include the following: - The Power Plant should reinforce its measures to prevent foreign objects from entering plant systems; - The Power Plant should ensure the 24-hour presence of an operator

World nuclear power plant capacity

International Nuclear Information System (INIS)

1991-01-01

This report provides the background information for statistics and analysis developed by NUKEM in its monthly Market Report on the Nuclear Fuel Cycle. The assessments in this Special Report are based on the continuous review of individual nuclear power plant projects. This Special Report begins with tables summarizing a variety of nuclear power generating capacity statistics for 1990. It continues with a brief review of the year's major events regarding each country's nuclear power program. The standard NUKEM Market Report tables on nuclear plant capacity are given on pages 24 and 25. Owing to space limitations, the first year shown is 1988. Please refer to previous Special Reports for data covering earlier years. Detailed tables for each country list all existing plants as well as those expected by NUKEM to be in commercial operation by the end of 2005. An Appendix containing a list of abbreviations can be found starting on page 56. Only nuclear power plants intended for civilian use are included in this Special Report. Reactor lifetimes are assumed to be 35 years for all light water reactors and 30 years for all other reactor types, unless other data or definite decommissioning dates have been published by the operators. (orig./UA) [de

Development of nuclear power plant Risk Monitor

International Nuclear Information System (INIS)

Yang Xiaoming; Sun Jinlong; Ma Chao; Wang Lin; Gu Xiaohui; Bao Zhenli; Qu Yong; Zheng Hao

2014-01-01

Risk Monitor is a tool to monitor the real-time risk of a nuclear power plant for risk management and comprehensive decision-making, which has been widely used all over the world. The nuclear power plant Risk Monitor applies the real-time risk model with low-complicacy that could reflect the plant's actual configuration, automatically reads the plant's configuration information from the engineering system through the developed interface, and efficiently analyzes the plant's risk Dy the intelligent parallel-computing method in order to provide the risk basement for the safety management of nuclear power plant. This paper generally introduces the background, architecture, functions and key technical features of a nuclear power plant Risk Monitor, and validates the risk result, which could well reflect the plant's risk information and has a significant practical value. (authors)

Risks associated with low level ionizing radiation (with special reference to nuclear power workers)

International Nuclear Information System (INIS)

1989-01-01

This document describes a project to use epidemiological studies of workers in the nuclear industry to estimate the cancer risk associated with low-dose chronic exposure to ionizing radiation. The project aims both to improve the basis for radiation risk assessment and to test the validity of currently used models for the extrapolation of radiation risk. This report focusses on the former aim, and summarizes discussions at two meetings held in June 1988. One of these was a small working group consisting mainly of epidemiologists who had carried out studies of nuclear workers; the other included nominees of the nuclear industries of eleven countries as well as epidemiologists and radiation physicists and biologists. As a result of the meetings, efforts are underway to pool existing data and a feasibility study is addressing the possibility of an international collaborative study of unstudied groups of nuclear workers

HVDC transmission from nuclear power plant

International Nuclear Information System (INIS)

Yoshida, Yukio; Takenaka, Kiyoshi; Taniguchi, Haruto; Ueda, Kiyotaka

1980-01-01

HVDC transmission directly from a nuclear power plant is expected as one of the bulk power transmission systems from distant power generating area. Successively from the analysis of HVDC transmission from BWR-type nuclear power plant, this report discusses dynamic response characteristics of HVDC transmission (double poles, two circuits) from PWR type nuclear power plant due to dc-line faults (DC-1LG, 2LG) and ac-line faults (3LG) near inverter station. (author)

Aircraft industry workers in evacuation: conditions of life of evacuated plants' workers in 1941-1945

Directory of Open Access Journals (Sweden)

Михаил Юрьевич Мухин

2010-09-01

Full Text Available The article is devoted to the work of the factories in 1941-1945 in the evacuation. The author analyzes the living conditions of workers in evacuated aviation plants, their daily life, maintenance, etc. The author concludes that in the early years of the War the conditions of life of the aviation industry's workers were very difficult, and the welfare and financial situation improved in 1944, the sure sign of fracture in the Second world war.

The application of plant information system on third Qinshan nuclear power plant

International Nuclear Information System (INIS)

Liu Wangtian

2005-01-01

Plant overall control has been applied in Qinshan Nuclear Power Plant, which enhances the security of plant operation, but it is not enough to improve the technical administration level. In order to integrate the overall information and to improve the technical administration level more. Third Qinshan Nuclear Power Plant applies the plant information system. This thesis introduces the application of plant information system in Third Qinshan Nuclear Power Plant and the effect to the plant after the system is carried into execution, in addition, it does more analysis and exceptions for application of plant information system in the future. (authors)

Safety criteria for nuclear chemical plants

International Nuclear Information System (INIS)

Ball, P.W.; Curtis, L.M.

1983-01-01

Safety measures have always been required to limit the hazards due to accidental release of radioactive substances from nuclear power plants and chemical plants. The risk associated with the discharge of radioactive substances during normal operation has also to be kept acceptably low. BNFL (British Nuclear Fuels Ltd.) are developing risk criteria as targets for safe plant design and operation. The numerical values derived are compared with these criteria to see if plants are 'acceptably safe'. However, the criteria are not mandatory and may be exceeded if this can be justified. The risk assessments are subject to independent review and audit. The Nuclear Installations Inspectorate also has to pass the plants as safe. The assessment principles it uses are stated. The development of risk criteria for a multiplant site (nuclear chemical plants tend to be sited with many others which are related functionally) is discussed. This covers individual members of the general public, societal risks, risks to the workforce and external hazards. (U.K.)

Development on database for foreign nuclear power plants

International Nuclear Information System (INIS)

Okuda, Yasunori; Yanagi, Chihiro

1999-01-01

The Nuclear Information Project in Institute of Nuclear Technology, Institute of Nuclear Safety Systems, Inc. (INSS) has been carrying out two activities related to technical information about nuclear power plants. The first is collection and analysis of accidents and incidents (troubles) of nuclear power plants in U.S.A. and West Europe and making draft of action proposals. The second is collection of main laws, government ordinances, regulatory guides, standard and domestic and international technical news connected with nuclear power plants. This report describes these two data bases about nuclear power plants details. (author)

Chemistry management system for nuclear power plants

International Nuclear Information System (INIS)

Nagasawa, Katsumi; Maeda, Katsuji

1998-01-01

Recently, the chemistry management in the nuclear power plants has been changing from the problem solution to the predictive diagnosis and maintenance. It is important to maintain the integrity of plant operation by an adequate chemistry control. For these reasons, many plant operation data and chemistry analysis data should be collected and treated effectively to evaluate chemistry condition of the nuclear power plants. When some indications of chemistry anomalies occur, quick and effective root cause evaluation and countermeasures should be required. The chemistry management system has been developed as to provide sophisticate chemistry management in the nuclear power plants. This paper introduces the concept and functions of the chemistry management system for the nuclear power plants. (author)

Role definition among public officials and emergency workers in a nuclear evacuation

International Nuclear Information System (INIS)

Metz, W.C.

1983-01-01

How public officials and emergency workers will resolve conflict between their official duties and assigned tasks and their family and conscience responsibilities is discussed in the context of the Indian Point nuclear station, and the Shoreham nuclear station

Life management plants at nuclear power plants PWR; Planes de gestion de vida en centrales nucleares PWR

Energy Technology Data Exchange (ETDEWEB)

Esteban, G.

2014-10-01

Since in 2009 the CSN published the Safety Instruction IS-22 (1) which established the regulatory framework the Spanish nuclear power plants must meet in regard to Life Management, most of Spanish nuclear plants began a process of convergence of their Life Management Plants to practice 10 CFR 54 (2), which is the current standard of Spanish nuclear industry for Ageing Management, either during the design lifetime of the plant, as well as for Long-Term Operation. This article describe how Life Management Plans are being implemented in Spanish PWR NPP. (Author)

The sanitary officer: first aid coordinator on EDF nuclear power plant

International Nuclear Information System (INIS)

Masson, A.

2000-01-01

The internal organisation for first aid to the injured in case of an accident on E.D.F. nuclear power plant calls for the immediate assistance of a first aid team, consisting of five workers, under the direction of a principal first aid officer; one of the first aid workers, the sanitary officer who instructs the first aid workers intervention awaiting the arrival of an external medical. When the 'Sanitary on-site Emergency Plan' was up' dated, twenty medical doctors and seventy members of staff from five different sites were questioned as to the function of the sanitary officer. The conclusions revealed a notable difference of training amongst the different sites, and concerning first aid organisation, difference of priority of actions, extent of their participation once the medical team arrives and their participation in case of decontamination treatment. The medical doctors and staff lay a particular stress on importance of defining on a national scale the limits of role and responsibilities of the sanitary officer and establish a more specific training in this field, consequently motivating commitment and professionalism involvement. There is a great difference between the training and coaching of the first aid assistance and fire protection teams. To conclude, we propose that the first aid officer be known as first aid coordinator and the qualification of 'Certificat de Formation aux Premiers Secours en Equipe' in compliance with the current legislation together with a specific nuclear module and they should undergo regular on-site drills. (author)

Nuclear power plant V-1

International Nuclear Information System (INIS)

1998-01-01

The nuclear power plant Bohunice V -1 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - 24 April 1972; first controlled reactor power - 27 November 1978, 15 March 1980; connection to the grid - 17 December 1978, 26 March 1980; commercial operation - 1 April 1980, 7 January 1981. This leaflet contains: NPP V-1 construction; Major technological equipment (Primary circuit: Nuclear reactor [WWER 440 V230 type reactor];Steam generator; Reactor Coolant Pumps; Primary Circuit Auxiliary Systems. Secondary circuit: Turbine generators, Nuclear power plant electrical equipment; power plant control) and technical data

Mortality of workers at the Chapelcross plant of British Nuclear Fuels

International Nuclear Information System (INIS)

Binks, K.; Thomas, D.I.; McElvenny, D.

1989-01-01

Standardised Mortality Ratio (SMR) and trend analysis results are reported for those 1796 Chapelcross worker first employed before 1 January 1976 with follow up to the end of 1983. 221 workers were found to have died, 42 (19%) of them from cancer. None of the SMRs are significantly greater than 100, but trends in mortality with increasing whole body exposure are of borderline significance for two disease groupings; malignant neoplasm of the lung and non malignant respiratory diseases. (author)

Man and nuclear power plants

International Nuclear Information System (INIS)

Anon.

1978-01-01

According to the Inst. fuer Unfallforschung/TUeV Rheinland, Koeln, the interpretation of empirical data gained from the operation of nuclear power plants at home and abroad during the period 1967-1975 has shown that about 38% of all reactor accidents were caused by human failures. These occured either during the design and construction, the commissioning, the reconditioning or the operation of the plants. This very fact stresses human responsibility for the safety of nuclear power plants, in spite of those plants being automated to a high degree and devices. (orig.) [de

75 FR 16524 - FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption

Science.gov (United States)

2010-04-01

... Company, Perry Nuclear Power Plant; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC... the Perry Nuclear Power Plant, Unit 1 (PNPP). The license provides, among other things, that the... date for all operating nuclear power plants, but noted that the Commission's regulations provide...

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-09-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost all the time in the first quarter of 1992. The load factor average was 99.8%. All events which are classified on the International Nuclear Event Scale were level 0/below scale on the Scale. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure, originating from the nuclear power plants, were detected in samples collected in the vicinity of the nuclear power plants

Challenges for new nuclear plants

International Nuclear Information System (INIS)

Bruschi, H.J.

2000-01-01

In the past 20 years, numerous new nuclear plant designs have been introduced in the hope of generating a mixture of features and benefits that generated enough enthusiasm amongst the utility industry decision makers to move forward with a new nuclear generation. Not only has there not been enough enthusiasm, there has been little interest in building new plants with advanced features, especially in the U.S. Compounding this predicament are the changing paradigms to which a new plant would be measured. The near hiatus on new plant orders is the clear cause of the significant consolidation in the nuclear industry. Regardless whether the disappearance of old-line nuclear companies is over or not, some paradigms for new generation designs are unmovable, while others are still under discussion as to their role in future plant designs. This paper will address those design goals that Westinghouse deems already having earned the rank of exemplar, and those still open to debate. Because it is my hope that this paper will lead to a fruitful discussion period, I will provide a list of what I feel are the champion design requirements, and those I consider the contenders. (author)

Safety culture in nuclear power plants

International Nuclear Information System (INIS)

Weihe, G. von; Pamme, H.

2003-01-01

Experience shows that German nuclear power plants have always been operated reliably and safely. Over the years, the safety level in these plants has been raised considerably so that they can stand any comparison with other countries. This is confirmed by the two reports published by the Federal Ministry for the Environment on the nuclear safety convention. Behind this, there must obviously stand countless appropriate 'good practices' and a safety management system in nuclear power plants. (orig.) [de

Elecnuc - Nuclear power plants in the world - 2009 edition

International Nuclear Information System (INIS)

2009-01-01

This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2008 highlights, Main characteristics of reactor types, Map of the French nuclear power plants on 2008/01/01, Worldwide status of nuclear power plants (12/31/2008), Units distributed by countries, Nuclear power plants connected to the Grid- by reactor type groups, Nuclear power plants under construction on 2008, Evolution of nuclear power plants capacities connected to the grid, First electric generations supplied by a nuclear unit in each country, Electrical generation from nuclear powe plants by country at the end 2008, Performance indicator of french PWR units, Evolution of the generation indicators worldwide by type, Nuclear operator ranking according to their installed capacity, Units connected to the grid by countries at 12/31/2008, Status of licence renewal applications in USA, Nuclear power plants under construction at 12/31/2008, Shutdown reactors, Exported nuclear capacity in net MWe, Exported and national nuclear capacity connected to the grid, Exported nuclear power plants under construction, Exported and national nuclear capacity under construction, Nuclear power plants ordered at 12/31/2008, Long term shutdown units at 12/31/2008, COL applications in the USA, Recycling of Plutonium in reactors and experiences, Mox licence plants projects, Appendix - historical development, Meaning of the used acronyms, Glossary

ELECNUC Nuclear power plants in the world - 2013 edition

International Nuclear Information System (INIS)

2013-01-01

This small booklet summarizes in a series of tables the figures relative to the nuclear power plants worldwide. Data come from the IAEA's PRIS database and from specific I-tese studies. The following aspects are reviewed: 2012 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2012/01/01; Worldwide status of nuclear power plants (12/31/2012); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2012; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2012; Performance indicator of french PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2012; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2012; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2012; Long term shutdown units at 12/31/2012; COL (Combined Licence) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary

Implication of dual-purpose nuclear desalination plants

International Nuclear Information System (INIS)

Kutbi, I.I.

1983-01-01

Available dual purpose nuclear desalination schemes are reviewed. Three specific issues namely, impact of availability and reliability of the desalination stage of the plant, integration of the desalination and power production stages and new safety concerns of dual system, relating to desalination schemes are discussed. Results of operational and reliability studies of nuclear power stations, reverse osmosis and multistage flash distillation desalination plants are considered. Operational aspects of nuclear-multistage flash distillation, nuclear-reverse osmosis and nuclear-multistage flash distillation-reverse osmosis are compared. Concludes that the combined nuclear-multistage flash distillation-reverse osmosis plant arrangement permits very large production capacity, high availability, improvement of plant reliability and proovision of savings on the cost of water and power produced. 23 Ref

Developing the next generation of nuclear workers at OPG

International Nuclear Information System (INIS)

Spekkens, P.

2007-01-01

This presentation is about developing the next generation of nuclear workers at Ontario Power Generation (OPG). Industry developments are creating urgent need to hire, train and retain new staff. OPG has an aggressive hiring campaign. Training organization is challenged to accommodate influx of new staff. Collaborating with colleges and universities is increasing the supply of qualified recruits with an interest in nuclear. Program for functional and leadership training have been developed. Knowledge retention is urgently required

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1993-12-01

Quarterly reports on the operation of Finnish nuclear power plants describe events and observations related to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Safety-enhancing plant modifications and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and the environment, and tabulated data on the plants' production and their load factors are also given. At the Loviisa 1 plant unit one of two specially-backed AC busbars was lost during the second quarter of 1993. A ca. 30 minute voltage break caused malfunctions in the plant unit's electrical equipment and rendered inoperable certain components important to safety. The event is rated on the International Nuclear Event Scale (INES) at level 1. In inspections carried out at TVO II during the annual maintenance outage, the number of cracks detected in control rod structural material was higher than usual. When cracks occur, part of boron carbide, the power regulating medium in control rods, may wash into the reactor water and control rod shutdown capability may be impaired. The event is rated on the INES at level 1. Other events in the second quarter of 1993 had no bearing on nuclear or radiation safety. (4 figs., 5 tabs.)

Radiological impact of diagnostic nuclear medicine technology on the Quebec population (patients and workers) in 1989

International Nuclear Information System (INIS)

Renaud, L.; Blanchette, J.

1992-01-01

Using the results of a six month survey on the doses received by non-monitored hospital workers from diagnostic nuclear medicine patients (DNMP) in three hospitals and published statistics on Quebec's workers and hospitals, an evaluation of the radiological impact of DNMP has been calculated on the Quebec's population. In 1989, diagnostic nuclear medicine gave an average of 6.4 mSv/act or a total of 2,800 sv-man. The diagnostic nuclear medicine technologists' community received 0.4 Sv-man and the non-monitored hospital workers 1.7 Sv-man from the DNMP in the same year. (author)

Nuclear power plants: 2009 atw compact statistics

International Nuclear Information System (INIS)

Anon.

2010-01-01

At the turn of 2009/2010, nuclear power plants were available for energy supply in 30 countries of the world. A total of 437 nuclear power plants, which is one plant less than at the 2008/2009 turn, were in operation with an aggregate gross power of approx. 391 GWe and an aggregate net power, respectively, of 371 GWe. The available gross power of nuclear power plants did not changed noticeably from 2008 to the end of 2009. In total 2 nuclear generating units were commissioned in 2009. One NPP started operation in India and one in Japan. Three nuclear generating units in Japan (2) und Lithuania (1) were decomissioned in 2009. 52 nuclear generating units, i.e. 10 plants more than at the end of 2008, with an aggregate gross power of approx. 51 GWe, were under construction in 14 countries end of 2009. New or continued projects are notified from (number of new projects): China (+9), Russia (1), and South Korea (1). Some 84 new nuclear power plants are in the concrete project design, planning and licensing phases worldwide; on some of them, contracts have already been awarded. Another units are in their preliminary project phases. (orig.)

Nuclear power plants: 2008 atw compact statistics

International Nuclear Information System (INIS)

Anon.

2009-01-01

At the turn of 2008/2009, nuclear power plants were available for energy supply in 31 countries of the world. A total of 438 nuclear power plants, which is one plant less than at the 2007/2008 turn, were in operation with an aggregate gross power of approx. 393 GWe and an aggregate net power, respectively, of 372 GWe. The available gross power of nuclear power plants didn't changed noticeabely from 2007 to the end of 2008. No nuclear generating unit was commissioned in 2008. One nuclear generating unit in the Slovak Republic was decomissioned in 2008. 42 nuclear generating units, i.e. 10 plants more than at the end of 2007, with an aggregate gross power of approx. 38 GWe, were under construction in 14 countries end of 2008. New or continued projects are notified from (in brackets: number of new projects): Bulgaria (2), China (5), South Korea (2), Russia (1), and the Slovak Republic (2). Some 80 new nuclear power plants are in the concrete project design, planning and licensing phases worldwide; on some of them, contracts have already been awarded. Another approximately 120 units are in their preliminary project phases. (orig.)

Fire scenarios in nuclear power plant

International Nuclear Information System (INIS)

Asp, I.B.; MacDougall, E.A.; Hall, R.E.

1978-01-01

This report defines a Design Base Fire and looks at 3 major areas of a hypothetical model for a Nuclear Power Plant. In each of these areas a Design Base Fire was developed and explained. In addition, guidance is given for comparing fire conditions of a given Nuclear Power Plant with the model plant described. Since there is such a wide variation in nuclear plant layouts, model areas were chosen for simplicity. The areas were not patterned after any existing plant area; rather several plant layouts were reviewed and a simplified model developed. The developed models considered several types of fires. The fire selected was considered to be the dominant one for the case in point. In general, the dominant fire selected is time dependent and starts at a specific location. After these models were developed, a comparison was drawn between the model and an operating plant for items such as area, cable numbers and weight, tray sizes and lengths. The heat loads of the model plant are summarized by area and compared with those of an actual operating plant. This document is intended to be used as a guide in the evaluation of fire hazards in nuclear power stations and a summarization of one acceptable analytical methodology to accomplish this

The nuclear peninsula

International Nuclear Information System (INIS)

Zonabend, F.

1993-01-01

This book reports a study of the social and psychological implications for the people who work in or live near a high-risk industrial establishment. The establishment focussed on the studies is the nuclear reprocessing plant at la Hague on the Cotentin Peninsula in Normandy, France. The ways in which those working in the plant and living nearby come to terms with the risks in their daily lives is described. A sociology of the nuclear work place with its diversions and hierarchies is developed and an explanation offered for the often unexpected responses of the workers to the fear of irradiation and contamination. By analysing work practices and the language of the work-place it is shown how workers and locals can recognise the possibility of nuclear catastrophe while, at the same time, denying that it could ever happen to them. (UK)

In vivo monitoring of nuclear research centre (NRC) workers. Vol. 4

Energy Technology Data Exchange (ETDEWEB)

Gomaa, M A; Ali, E M; Taha, T M [Radiation Protection Departion, Nuclear Research Center, Atomic Energy Authority, Cairo (Egypt)

1996-03-01

Occupational workers of Nuclear research center (NRC) of atomic energy authority (AEA) working with radio-nuclides such as (Cs-137, I-131, and I-125) are monitored yearly. Individuals involved in routine work in hot laboratories are examined every three months. When an incident occurs, the workers involved are examined promptly. In order to measure internal contamination, the modified NRC-AEA whole body counter is used. More than hundred occupational workers had been examined in 1994. Results indicated that the annual limit of intake as recommended by ICRP was not exceeded. 3 figs., 3 tabs.

Big five general contractors dominate civil construction market of nuclear power plants

International Nuclear Information System (INIS)

Anon.

1985-01-01

The Japanese construction industry is a key industry accounting for about 20 % of the GNP, and the investment in construction amounted to 51,200 billion yen in fiscal 1984. 515,000 firms employing about 5.5 million workers belong to the industry. 99.4 % of these firms is the enterprises capitalized at less than 100 million yen, and most of them are small self-employment enterprises. The Construction Business Law provides that those who wish to engage in construction are required to obtain a permit from the Construction Ministry or from a local prefectural governor. There are big five and seven sub-major construction companies in Japan. The big five formed the tie-up relations with three nuclear reactor manufacturers. 76 civil engineering and construction companies recorded the sales related to nuclear power in 1983 amounting to 330.9 billion yen, equivalent to 21 % of the total nuclear-related sales. The construction of nuclear power plants and the characteristics of the construction, and the activities of the big five in the field of nuclear industry are reported. (Kako, I.)

Standard Specification for Nuclear Facility Transient Worker Records

CERN Document Server

American Society for Testing and Materials. Philadelphia

1995-01-01

1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. 1.2 This specification applies to records to be used for in-processing only. 1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications). 1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility. Note 1—Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD...

Ventilation-air conditioner system in nuclear power plant

International Nuclear Information System (INIS)

Kubota, Ryuji; Sugisaki, Toshihiko.

1989-01-01

This invention concerns a ventilation-air conditioner system which enables, upon occurrence of accidents in a nuclear power plant, continuous operation for other adjacent nuclear power plants with no effect of accidents. Air supply system and exhaust system are operated during usual operaiton. If loss of coolants accidents should occur in an adjacent nuclear power plants, operation is switched from ventilation operaiton to the operation of re-cycling system based on an AND logic of three signals, that is, a pressure HIGH signal for the reactor container, a water level LOW signal for the reactor and a radioactivity signal of the ventilation-air conditioner sytem on the side of air supply in the nuclear power plant. Thus, nuclear reactor buildings of the nuclear power plant are from the external atmosphere. Therefore, the radioactivity HIGH signal for switching to the emergency air conditioner system of the nuclear power plant is not actuated due to the loss of coolant accidents in the adjacent nuclear power plant. In addition, since the atmospheric temperature in the nuclear reactor building can be maintained by a cooling device disposed to the recycling system, reactor shutdown can be prevented. (I.S.)

Vital areas at nuclear power plants

International Nuclear Information System (INIS)

Cameron, D.F.

1985-01-01

Vital area analysis of nuclear power plants has been performed for the Nuclear Regulatory Commission by the Los Alamos National Laboratory from the late 1970's through the present. The Los Alamos Vital Area Study uses a fault-tree modeling technique to identify vital areas and equipment at nuclear power plants to determine their vulnerability. This technique has been applied to all operating plants and approximately one-half of those under construction in the US. All saboteur-induced loss-of-coolant accidents and transients and the systems needed to mitigate them are considered. As a result of this effort, security programs at nuclear power plants now include vulnerability studies that identify targets in a systematic manner, and thus unnecessary protection has been minimized. 1 ref., 8 figs., 1 tab

78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

Science.gov (United States)

2013-06-27

... Systems for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... Guide (RG) 5.29, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants... material control and accounting. This guide applies to all nuclear power plants. ADDRESSES: Please refer to...

Female Regulatory Inspectors at Nuclear Power Plants: A Constant Challenge and Opportunities

International Nuclear Information System (INIS)

Maree, V.

2015-01-01

The South African National Nuclear Regulator (NNR) was established in 1999 to provide for the protection of persons, environment and properties from the harmful effects arising from ionizing radiation produced by radioactive materials. It is the responsibility of the licencee to have in place the necessary safety measures and resources in order to protect the public, workers and the environment against possible harmful effects of ionizing radiation caused by the operations of the Nuclear Power Stations. To fulfill its mission, the NNR employs 61 females with scientific and engineering qualifications to support and perform compliance assurance activities at the Nuclear Power Plant in accordance with the National Nuclear Regulator Act, 1999 (Act No. 47 of 1999). This Act describes the following in terms of duties of an inspector: “An Inspector may carry out inspections and use any applicable equipment during such inspections at any of the nuclear installations, sites or places and conduct such investigations as are necessary for the purpose of monitoring or enforcing compliance with this Act”. The Regulator has two offices, the Head office is located in Pretoria and the Site office is located in Cape Town. Regulatory Inspectors at the Site Office are responsible for performing compliance inspections at Nuclear Power Plant. Women at the Site office play an important role in fulfilling the mandate of the NNR, 3/5 inspectors are women. One is The Chief Inspector responsible for executing the compliance assurance programme and one of the female Inspectors is the South Africa Lead Representative at the International Atomic Energy Agency Waste Safety Standards Committee (IAEA–WASSC). This poster addresses the following challenges: – Plant facilities and personnel protective equipment, • Environment created by historical male domination, • Overcoming conscious and unconscious biases against women (by both genders). (author)

Preliminary study on the relation between the coping patterns and mental health of radiation control personnel and nondestructive inspectors engaged in the periodic inspections of nuclear power plants.

Science.gov (United States)

Nagaoka, Chika; Uchida, Yukiko

2014-01-01

In order to safely manage nuclear power plants, their workforce should be mentally healthy. This study clarifies the coping strategies of radiation control personnel and nondestructive inspectors engaged in the periodic inspection of nuclear power plants, the effect of the coping strategies on their mental health, as well as any effect based on whether or not they had worked after the nuclear disaster caused by the Great East Japan Earthquake and tsunami in March 2011. A questionnaire survey was administered to 133 technicians attending a certification course, and among them, our subjects of analysis were 104 people with work experience in radiation control and/or nondestructive inspection. The results indicated that even among workers of the same company who were assigned to similar duties in the periodic inspections of nuclear power plants, the group that had worked at a nuclear plant after the disaster had a tendency to use coping strategies, such as giving up and avoidance-like thinking, which was dissimilar to the group that had not worked at a nuclear plant after the disaster. Further, the former group had higher levels of distress than those who tended to use other coping strategies. In addition, the results suggested that the plan-drafting strategy adopted by the group that had not worked after the disaster did not result in stress reduction. Based on these results, we propose a stress management program specifically for radiation workers.

China’s Nuclear Power Plants in Operation

Institute of Scientific and Technical Information of China (English)

无

2011-01-01

Qinshan Plant Phase I Located in Haiyan,Zhejiang Province,Qinshan Nuclear Power Plant Phase I is t he first 300-megawatt pressurized water reactor (PWR) nuclear power plant independently designed,constructed,operated and managed by China.The plant came into commercial operation in April 1994.

Internal exposure monitoring of personnel of a nuclear power plant with pressurized-water reactors

International Nuclear Information System (INIS)

Krueger, F.W.; Poulheim, K.F.; Rueger, G.; Schreiter, W.D.

1982-01-01

In the GDR a programme for monitoring the internal radiation exposure of personnel has been established in the Bruno Leuschner Nuclear Power Plant, Greifswald, which allows one to estimate the effective dose equivalent in the way recommended by the ICRP. The measuring equipment used, and the methods of calibration and of evaluation of results are described. At present about 400 persons are monthly monitored with a thorax monitor in the nuclear power plant. If an investigation level - corresponding to an effective dose equivalent of 0.3mSv/month - is exceeded, a more exact measurement is made in the whole-body counter at the National Board for Nuclear Safety and Radiation Protection of the GDR. In addition, a selected group of 50 persons is measured twice yearly in the whole-body counter. The measurements show the high effectiveness of the protective measures against radionuclide intake by workers in the nuclear power plant, resulting in a contribution of less than 1% to the collective dose of the personnel. A correlation has been found between external and internal exposure indicating that, in general, there will be a higher intake only under conditions resulting also in higher external exposures. The highest individual values of internal exposure found are below 0.5mSv/month and thus within the range of the lower detection limit of dosimeter films used for monitoring the external exposure. (author)

Commissioning of the nuclear power plant

International Nuclear Information System (INIS)

Furtado, P.M.; Rolf, F.

1984-01-01

Nuclear Power Plant Angra 2, located at Itaorna Beach-Angra dos Reis is the first plant of the Brazilian-German Agreement to be commissioned. The Nuclear Power Plant is a pressurized water reactor rated at 3765 Mw thermal/1325 Mw electrical. For commissioning purpose the plant is divided into 110 systems. Plant commissioning objective is to demonstrate the safe and correct operation of each plan component, system and of the whole plant in agreement with design conditions, licensing requirements and contractual obligations. This work gives a description of plant commissioning objectives, activities their time sequence, and documentation. (Author) [pt

Partner of nuclear power plants

International Nuclear Information System (INIS)

Gribi, M.; Lauer, F.; Pauli, W.; Ruzek, W.

1992-01-01

Sulzer, the Swiss technology group, is a supplier of components and systems for nuclear power plants. Important parts of Swiss nuclear power stations, such as containments, reactor pressure vessels, primary pipings, are made in Winterthur. Sulzer Thermtec AG and some divisions of Sulzer Innotec focus their activities on servicing and backfitting nuclear power plants. The European market enjoys priority. New types of valves or systems are developed as economic solutions meeting more stringent criteria imposed by public authorities or arising from operating conditions. (orig.) [de

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1990-08-01

During the first quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. Nuclear electricity accounted for 32.5% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 99.0%. An international nuclear event scale has been introduced for the classification of nuclear power plant events according to their nuclear and radiation safety significance. The scale first undergoes about a year long trial period in several countries. on the scale, events are divided into levels from 1 to 7 of which events at Level 7 are the most serious. Furthermore, Level 0 (Below Scale) is used for events with no safety significance. All events which occurred at the Finnish nuclear power plants this quarter are classified as Level 0. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. At the Loviisa plant, a back-up emergency feedwater system independent of the plant's other systems has been introduced which offers a new, alternative means of removing residual heat from the reactor. Owing to this system, the risk of a severe accident has been further reduced. At the TVO plants, systems have been introduced by which accident sequences which lead to containment failure could be eliminated and the consequences of a potential severe accident could be mitigated. In this report, also the release of short-lived radioactive materials along the transfer route of an irradiated sample is described which occured at the FiR 1 research reactor. The amounts of radioactive materials individuals received in their bodies in connection with this event were very low

Development of web-based integrity evaluation system for primary components in a nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Lee, S.M.; Kim, J.C.; Choi, J.B.; Kim, Y.J. [SAFE Research Center, Sungkyunkwan Univ., Suwon (Korea); Choi, S.N.; Jang, K.S.; Hong, S.Y. [Korea Electronic Power Research Inst., Daejeon (Korea)

2004-07-01

A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including periodical in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage integrity issues on a nuclear power plant. In this paper, a web-based integrity evaluation system for primary components in a nuclear power plant is proposed. The proposed system, which is named as WEBIES (web-based integrity evaluation system), has been developed in the form of 3-tier system architecture. The system consists of three servers; application program server, user interface program server and data warehouse server. The application program server includes the defect acceptance analysis module and the fracture mechanics analysis module which are programmed on the basis of ASME sec. XI, appendix A. The data warehouse server provides data for the integrity evaluation including material properties, geometry information, inspection data and stress data. The user interface program server provides information to all co- workers in the field of integrity evaluation. The developed system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant. (orig.)

Development of web-based integrity evaluation system for primary components in a nuclear power plant

International Nuclear Information System (INIS)

Lee, S.M.; Kim, J.C.; Choi, J.B.; Kim, Y.J.; Choi, S.N.; Jang, K.S.; Hong, S.Y.

2004-01-01

A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including periodical in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage integrity issues on a nuclear power plant. In this paper, a web-based integrity evaluation system for primary components in a nuclear power plant is proposed. The proposed system, which is named as WEBIES (web-based integrity evaluation system), has been developed in the form of 3-tier system architecture. The system consists of three servers; application program server, user interface program server and data warehouse server. The application program server includes the defect acceptance analysis module and the fracture mechanics analysis module which are programmed on the basis of ASME sec. XI, appendix A. The data warehouse server provides data for the integrity evaluation including material properties, geometry information, inspection data and stress data. The user interface program server provides information to all co- workers in the field of integrity evaluation. The developed system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant. (orig.)

The safety of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

1988-01-01

Do nuclear power plants present an unjustifiable risk Can there be confidence in their safety The Uranium Institute invited a group of senior safety experts from eight different Western countries operating different types of reactors to provide an authoritative explanation for non-specialists of the basic principles of reactor safety, their application and their implications. The report presents the group's opinion on the level of safety achieved in the Western nuclear power plants with which the authors are directly familiar. Although many of the points made may well also be true for non-Western reactors, the report does not cover them except where specifically stated. It does describe and discuss the causes of the Chernobyl disaster. It does not compare nuclear power with other fuels, nor does it deal with its benefits, since however great the benefits from the peaceful use of nuclear power, and its own advantages over other fuels, they could not compensate for lack of safety. The conclusion reached is that the risk associated with electricity production at nuclear power plants can be kept very low. Proper use of the extensive knowledge available today can guarantee operation of nuclear power plants at very high safety levels, carrying very low risks, both to health and of contamination of the environment: risks that are continually lowered by upgrading existing plants and their operation, and by the design of future power plants. (author).

Radioactive waste management at nuclear power plant Cernavoda

International Nuclear Information System (INIS)

Raducea, D.

2002-01-01

Many human activities generate waste, but people are worried about wastes produced in nuclear power plants (NPPs). Their concern is an unjustified fear toward the hazards from radioactive waste, probably because in any country generating electric power by NPPs a lot of attention is paid to relevant parties involved in radioactive waste management. Significant attention is also given to the management of radioactive waste at the Cemavoda NPP. The general approach required for the collection, handling, conditioning and storage of radioactive wastes, while maintaining acceptable levels of safety for workers, members of the public and the environment, is conceptually established. The overall programme provides the necessary facilities to adequately manage solid radioactive waste from Cemavoda NPP Unit 1 and will be capable of expansion when other units are brought into service. (author)

Countermeasures to earthquakes in nuclear plants

International Nuclear Information System (INIS)

Sato, Kazuhide

1979-01-01

The contribution of atomic energy to mankind is unmeasured, but the danger of radioactivity is a special thing. Therefore in the design of nuclear power plants, the safety has been regarded as important, and in Japan where earthquakes occur frequently, the countermeasures to earthquakes have been incorporated in the examination of safety naturally. The radioactive substances handled in nuclear power stations and spent fuel reprocessing plants are briefly explained. The occurrence of earthquakes cannot be predicted effectively, and the disaster due to earthquakes is apt to be remarkably large. In nuclear plants, the prevention of damage in the facilities and the maintenance of the functions are required at the time of earthquakes. Regarding the location of nuclear plants, the history of earthquakes, the possible magnitude of earthquakes, the properties of ground and the position of nuclear plants should be examined. After the place of installation has been decided, the earthquake used for design is selected, evaluating live faults and determining the standard earthquakes. As the fundamentals of aseismatic design, the classification according to importance, the earthquakes for design corresponding to the classes of importance, the combination of loads and allowable stress are explained. (Kako, I.)

Nuclear reactor kinetics and plant control

CERN Document Server

Oka, Yoshiaki

2013-01-01

Understanding time-dependent behaviors of nuclear reactors and the methods of their control is essential to the operation and safety of nuclear power plants. This book provides graduate students, researchers, and engineers in nuclear engineering comprehensive information on both the fundamental theory of nuclear reactor kinetics and control and the state-of-the-art practice in actual plants, as well as the idea of how to bridge the two. The first part focuses on understanding fundamental nuclear kinetics. It introduces delayed neutrons, fission chain reactions, point kinetics theory, reactivit

Nuclear safety in France

International Nuclear Information System (INIS)

Servant, J.

1979-12-01

The main areas of nuclear safety are considered in this paper, recalling the laws and resolutions in force and also the appropriate authority in each case. The following topics are reviewed: radiological protection, protection of workers, measures to be taken in case of an accident, radioactive effluents, impact on the environment of non-nuclear pollution, nuclear plant safety, protection against malicious acts, control and safeguard of nuclear materials, radioisotopes, transport of radioactive substances, naval propulsion, waste management, nuclear plant decommissioning and export of nuclear equipment and materials. Finally, the author describes the role of the general Secretariat of the Interdepartmental Committee on Nuclear Safety

Elecnuc. Nuclear power plants in the world. 1997

International Nuclear Information System (INIS)

Maubacq, F.; Tailland, C.

1997-04-01

This small booklet provides information about all type of nuclear power plants worldwide. It is based on the data taken from the CEA/DSE/SEE Elecnuc database. The content comprises: the 1996 highlights, the main characteristics of the different type of reactors in operation or under construction, the map of the French nuclear power plant sites, the worldwide status of nuclear power plants at the end of 1996, the nuclear power plants in operation, under construction or on order (by groups of reactor-types), the power capacity evolution of power plants in operation, the net and gross capacity of the power plants on the grid, the commercial operation and grid connection forecasts, the first achieved or expected power generation supplied by a nuclear reactor for each country and the power generation from nuclear reactors, the performance indicator of the PWR units in France, the trends of the power generation indicator worldwide, the nuclear power plants in operation, under construction, on order, planned, cancelled, decommissioned and exported worldwide, the schedule of steam generator replacements, and the MOX fuel plutonium recycling programme. (J.S.)

Sensitivity analysis on the priority order of the radiological worker allocation model using goal programming

International Nuclear Information System (INIS)

Jung, Hae Yong; Lee, Kun Jai

1998-01-01

In nuclear power plant, it has been the important object to reduce the occupational radiation exposure (ORE). Recently, the optimization concept of management science has been studied to reduce the ORE in nuclear power plant. In optimization of the worker allocation, the collective dose, working time, individual dose, and total number of worker must be considered and their priority orders must be thought because the main constraint is necessary for determining the constraints variable of the radiological worker allocation problem. The ultimate object of this study is to look into the change of the optimal allocation of the radiological worker as priority order changes. In this study, the priority order is the characteristic of goal programming that is a kind of multi-objective linear programming. From a result of study using goal programming, the total number of worker and collective dose of worker have changed as the priority order has changed and the collective dose limit have played an important role in reducing the ORE

Nuclear plant aging research program

International Nuclear Information System (INIS)

Eissenberg, D.M.

1987-01-01

The U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, has established the Nuclear Plant Aging Research (NPAR) program in its Division of Engineering Technology. Principal contractors for this program include Oak Ridge National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, and Pacific Northwest Laboratory. The program goals are: to identify and characterize time-dependent degradation (aging) of nuclear plant safety-related electrical and mechanical components which could lead to loss of safety function; to identify and recommend methods for detecting and trending aging effects prior to loss of safety function so that timely maintenance can be implemented; and to recommend maintenance practices for mitigating the effects of aging. Research activities include prioritization of system and component aging in nuclear plants, characterization of aging degradation of specific components including identification of functional indicators useful for trending degradation, and testing of practical methods and devices for measuring the functional indicators. Aging assessments have been completed on electric motors, snubbers, motor-operated valves, and check valves. Testing of trending methods and devices for motor-operated valves and check valves is in progress

Decommissioning and back working of Greifswald nuclear power plant

International Nuclear Information System (INIS)

Rittscher, D.; Leushacke, D.F.; Meyer, R.

1998-01-01

At Nuclear Power Plant Greifswald, the Energiewerke Nord are carrying out the presently world's largest decommissioning project. This requires the gathering up of experience from the operation of the nuclear power plants at Greifswald, the decommissioning of other nuclear power plants, waste management, project management and licensing procedures for the decommissioning of nuclear power plants. That confirmed that the back working of nuclear plants is not a technical problem but a challenge for project management and logistics. It shows that the dismantling and disposal of nuclear plants is an ordinary process in our economic life. (orig.) [de

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

1988-04-01

This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tubulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Heimburger, H.

1988-08-01

This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Ottosson, C.

1989-05-01

This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Haenninen, R.; Koponen, H.; Nevander, O.; Paltemaa, R.; Poellaenen, I.; Rannila, P.; Valtonen, K.; Vilkamo, O.

1988-02-01

This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Haenninen, R.

1988-09-01

This general review of the operation of the Finnish nuclear power plants concentrates on such events and discoveries related to nuclear and radiation safety as the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hzard to the personnel or the environment

Increasing reliability of nuclear energy equipment and at nuclear power plants

International Nuclear Information System (INIS)

Ochrana, L.

1997-01-01

The Institute of Nuclear Energy at the Technical University in Brno cooperates with nuclear power plants in increasing their reliability. The teaching programme is briefly described. The scientific research programme of the Department of Heat and Nuclear Power Energy Equipment in the field of reliability is based on a complex systematic concept securing a high level of reliability. In 1996 the Department prepared a study dealing with the evaluation of the maintenance system in a nuclear power plant. The proposed techniques make it possible to evaluate the reliability and maintenance characteristics of any individual component in a nuclear power plant, and to monitor, record and evaluate data at any given time intervals. (M.D.)

TVA's nuclear power plant experience

International Nuclear Information System (INIS)

Willis, W.F.

1979-01-01

This paper reviews TVA's nuclear power plant design and construction experience in terms of schedule and capital costs. The completed plant in commercial operation at Browns Ferry and six additional plants currently under construction represent the nation's largest single commitment to nuclear power and an ultimate investment of $12 billion by 1986. The presentation is made in three separate phases. Phase one will recapitulate the status of the nuclear power industry in 1966 and set forth the assumptions used for estimating capital costs and projecting project schedules for the first TVA units. Phase two describes what happened to the program in the hectic early 1979's in terms of expansion of scope (particularly for safety features), the dramatic increase in regulatory requirements, vendor problems, stretchout of project schedules, and unprecedented inflation. Phase three addresses the assumptions used today in estimating schedules and plant costs for the next ten-year period

Academic training for nuclear power plant operators

International Nuclear Information System (INIS)

Jones, D.W.

1982-01-01

In view of the increasing emphasis being placed upon academic training of nuclear power plant operators, it is important that institutions of higher education develop and implement programs which will meet the educational needs of operational personnel in the nuclear industry. Two primary objectives must be satisfied by these programs if they are to be effective in meeting the needs of the industry. One objective is for academic quality. The other primary objective is for programs to address the specialized needs of the nuclear plant operator and to be relevant to the operator's job. The Center for Nuclear Studies at Memphis State University, therefore, has developed a total program for these objectives, which delivers the programs, and/or appropriate parts thereto, at ten nuclear plant sites and with other plants in the planning stage. The Center for Nuclear Studies program leads to a Bachelor of Professional Studies degree in nuclear industrial operations, which is offered through the university college of Memphis State University