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Sample records for ch npp accident

  1. Medical and biological aspects of ionizing radiation influence in consequence with accident at ChNPP

    International Nuclear Information System (INIS)

    Shidlovs'ka, T.A.

    2011-01-01

    This monograph presents the issues on systematic influence of ionizing radiation on the biological systems. The results of personal complex studies because of influence of ionizing radiation in consequence with accident at ChNPP on auditory analyzer, creating voice, cardiovascular system and central nervous system are submitted.

  2. The psychological results of the consequence of the ChNPP accident

    International Nuclear Information System (INIS)

    Salamatov, V.A.; Volodina, I.A.

    1992-01-01

    The ChNPP accident grought about the following stress reactions among the exposed population registered: psychosomatic reactions (headaches, gastro-intestinal tract disorders pains in the heart etc.), psychoemotional reactions (panic, sleep disturbance, restlessness etc.), behaviour reaction (aggressiveness, apathy) the whole structure of the human psychic is stated to have been affected by the Chernobyl' accident. The changes in the emotion-and-will sphere appear most distinctly. 2 tab

  3. The social and psychological aspects of the ChNPP accident

    International Nuclear Information System (INIS)

    Ferents, V.I.; Primenko, V.A.

    1992-01-01

    The conditions and the life style of the population living on the controlled areas and of the accident-result lequidators have been studied. As a base for the investigation the conception of the life style was taken into consideration as a factor forming the health. The process of forming a new artificial social and ecological focus characterized by the changes in the inhabitance among the population, the destruction of the routine life style, the high risk radiation incidence, the increase of the migration, the poor health has been found out to be taking place in the regions exposed to the ChNPP accident. 5 refs

  4. Epidemiological analysis of data on participants of liquidating the consequences of ChNPP accident that live in Russia

    International Nuclear Information System (INIS)

    Tsyb, A.F.; Ivanov, V.K.; Ajrapetov, S.A.; Gashp, E.A.; Maksyutov, M.A.; Rozhkov, O.V.; Stadnik, O.E.; Chekin, S.Yu.; Saakyan, A.K.

    1992-01-01

    To provide for long-term, automatized, personal registration of individuals that have been exposed to radiation as a result of ChNPP accident and their children; radiation doses as well as the participants health and alterations in health State register (SR) has been compiled. SR-multilevel system covering all regions of the country includes 3 subsystems relating to organization-and-medical provision; mathematical software and radiation monitoring. The current status of SR for the Russian Federation has been demonstrated; stochastic effects of radiation influence as well as the dynamics of the basic criteria of disease incidence have been evaluated. 2 refs.; 12 figs

  5. Exercise (effort) tolerance and factors affecting this tolerance for liquidators of consequences of the ChNPP accident

    International Nuclear Information System (INIS)

    Khomazyuk, I.N.

    1992-01-01

    Physical efficiency and factors affecting it for persons exposed to irradiation (the radiation dose being in the range up to 0.75 Gy) has been studied. 670 participants of liquidating the consequences of ChNPP accident have been examined. Depending on the radiation doses to which the people have been exposed the liquidators have been subdivided into 4 groups: for the 1st group the radiation doses ranging from 0.25 to 0.75 Gy; for the 2nd group the radiation doses ranging from 0.10 to 0.24 Gy; for the 3rd group the radiation doses ranging from 0.05 to 0.10 Gy; for the 4th group the radiation dose being up to 0.05 Gy. The physical load was ensured with veloergometer. The results have made it possible to estimate one of the basic health criterion for liquidators of consequences of ChNPP accident (i.e. exercise (effort) tolerance). No direct relationship of the exercise magnitude and the radiation dose within the range up to 0.75 Gy and the irradiation time have been observed. The correlation of the exercise magnitude with due account to age has been provided. 15 refs.; 2 tabs

  6. The problems of territory rehabilitation in the area of ChNPP accident

    International Nuclear Information System (INIS)

    Meshalkin, G.S.; Arkhipov, N.P.

    1994-01-01

    The mechanism is considered by which the forming of fuel, fuel-condensate and condensate fallout zones (having different radionuclides contents, different physic-chemical mobility and biological accessibility of radionuclides that constitute a part of radioactive contamination) proceeds. The works aimed at rehabilitation of the ChNPP area and adjacent territories are briefly characterised. Possible practical measures on rehabilitating the agricultural and forest tracts of the exclusive zone their total area being of more than 200,000 ha, are at issue. Emphasis is put on importance of special soil treatment that ensures efficient reduction of exposure dose rate (by an order of magnitude) and considerable diminution of radionuclide transfer to agriculture products

  7. Experience in construction of new safe confinement over ChNPP-4 damages in beyond design-basis accident: view in 30 year

    International Nuclear Information System (INIS)

    Nosovskij, A.V.

    2016-01-01

    Many organizations and institutions participated in the elimination of ChNPP-4 accident. However, the main efforts on conservation of the damaged unit and ChNPP-3 commissioning were performed in 1986-1987 by experts of the enterprises and organizations of the Ministry of Medium Machine Building of the Soviet Union, who have been sent to the staff of the specially created Construction Administration US-605. The paper presents the activity of US-605 experts, describes administrative and technical measures of radiation safety during construction of the Shelter in difficult radiation conditions. Such efforts enabled accumulation of significant and unique experience in mitigation of severe accident consequences, which shall be used to prevent any nuclear accidents and eliminate their consequences

  8. Medical and biological aspects of ionizing radiation influence in consequence with accident at ChNPP; Mediko-byiologyichnyi aspekti vplivu yionyizuyuchoyi radyiatsyiyi vnaslyidok avaryiyi na ChAES

    Energy Technology Data Exchange (ETDEWEB)

    Shidlovs' ka, T A [Institute for Safety Problems of Nuclear Power Plants, Chornobyl (Ukraine)

    2011-07-01

    This monograph presents the issues on systematic influence of ionizing radiation on the biological systems. The results of personal complex studies because of influence of ionizing radiation in consequence with accident at ChNPP on auditory analyzer, creating voice, cardiovascular system and central nervous system are submitted.

  9. Estimation and forecasting of the state of conifer forests in the area of the ChNPP accident

    International Nuclear Information System (INIS)

    Kozubov, G.M.; Taskaev, A.I.; Abaturov, Yu.D.

    1989-01-01

    Radiation monitoring of conifer forests was performed over the area of 15-20 hectare for all directions from the ChNPP. Biometric growth indices of pinetrees and sprucetrees during the period 1986-1988 were studied. The specific features of vegetative morphological changes in the mentioned trees were estimated for different absorbed dose rates. The quality factors of seeds were shown to be bioindicators of the absorbed doses in the case of highly chronic radiation injuries. In conclusion it was recommended to arrange a permanent radiation monitoring of radiation environment and to provide radiation protection of forests. figs. 2; tabs. 7

  10. Non-cancer thyroid and other endocrine disease in children and adults exposed to ionizing radiation after the ChNPP accident

    International Nuclear Information System (INIS)

    Kamyins'kij, O.V.; Kopilova, O.V.; Afanas'jev, D.Je.; Pronyin, O.V.

    2015-01-01

    The verified clinical and epidemiological data on the natural history of noncancer endocrine disease in remote period after the ChNPP accident in survivors of adult and children age was summarized. Retrospective estimation was carried out of data on 24,588 adult persons and 20,087 children survived after the ChNNP accident and being healthy or having any diseases. Data were retrieved from database of the Clinical Epidemiological Registry (CER), NRCRM for the 23 years (1992-2014) of survey. Average total external radiation dose in adults was 0.187 Gy, range of thyroid dose in children was 0.1-1.55 Gy. These data were verifies in a separate clinical study. Anthropomorphic, laboratory biochemical and hormonal assay values, thyroid ultrasound imaging patterns and radiation dose values were retrieved for the study. Noncancer endocrine disease in children and adults exposed to ionizing radiation is frequent and registered in 3-53% of persons. It occurs in most of survivors 10-15 years upon the impact of radiation factor as a result of manmade accident and continues to grow slowly in 30 years

  11. Evaluation of postpone Ch NPP accident consequences. Health state of children born in families of cleaners taking part in the Chernobyl accident consequences

    International Nuclear Information System (INIS)

    Koretskaya, L.S.; Kornesku, A.V.; Koretskaya, L.I.; Moldovanu, M.; Samotyya, E.E.; Etsko, L.A.

    2009-01-01

    The analysis of the results of the medical investigation during 1996-2008 years of the health of the about 200 children (107 girls, 115 boys 5-17 years old), which parents took part in liquidation of C NPP accident have been performed. Clinical, immunological disturbance and increased chromosome mutagenesis intensity in somatic cells of the investigated children gave reason to classify them among those with the increased risk of probability of the pathology with genetic component. This may be considerate as a well founded conclusion for elaboration of separated registry of the children born in families of liquidators. The immunological disturbance of children probably reflects the disturbance of the differential processes and maturity of cells of thymus and can be the consequences of the factors influence related with the clinic pathologies. The results permitted to select the group for feature cytogenesis and clinic investigations (authors)

  12. Chernobyl NPP accident. Overcoming experience. Acquired lessons

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Prister, B.S.

    2006-01-01

    This book is devoted to the 20 anniversary of accident on the Chernobyl NPP unit 4. History of construction, causes of the accident and its consequences, actions for its mitigation are described. Modern situation with Chernobyl NPP decommissioning and transferring of 'Ukryttya' shelter into ecologically safe system are mentioned. The future of Chernobyl site and exclusion zone was discussed

  13. Morbidity pattern of non-cancer endocrine disease in ChNPP accident emergency workers (1992-2013 Clinical/ Epidemiological Registry data)

    International Nuclear Information System (INIS)

    Kamyins'kij, O.V.; Pronyin, O.V.; Afanas'jev, D.Je.

    2014-01-01

    Effects of ionizing radiation and other hazardous factors on endocrine system in the ChNPP AEW appeared upon 15-25 years. There was a significant (2-10-fold) and reliable (p < 0.01) increase of the incidence of the nodular goiter, autoimmune thyroiditis, obesity, type 2 diabetes mellitus. And there is a trend to further increase

  14. Models of fuel masses transition during second stage of the accident on Chernobyl NPP

    International Nuclear Information System (INIS)

    Tarapon, A.

    2002-01-01

    In ISPE NASU of Ukraine are developed mathematical models and software, which allow to research the processes of fuel masses transition during the accident at ChNPP. We found out, that the main reason of accident on ChNPP is the happening in the reactor of crisis of heat exchange of the second sort, instead of the effect positive output of reactivity from displacers of rods of system of emergency protection, as is accepted in official version

  15. Jose Cabrera NPP severe accident management activities

    International Nuclear Information System (INIS)

    Blanco, J.; Almeida, P.; Saiz, J.; Sastre, J.L.; Delgado, R.

    1998-01-01

    To prepare a common acting plan with respect to Severe Accident Management, in 1994 was founded the severe accident management ''ad-hoc'' working group from the Spanish Westinghouse PWR Nuclear Power Plant Owners Group. In this group actively collaborated the Jose Cabrera NPP Training Centre and the Department of Nuclear Engineering of UNION FENOSA. From this moment, Jose Cabrera NPP began the planning of its specific Severe Accident Management Program, which main point are Severe Accident Management Guidelines (SAMG). To elaborate this guidelines, the Spanish translation of Westinghouse Owners Group (WOG) Severe Accident Management Guidelines were considered the reference documents. The implementation of this Guidelines to Jose Cabrera NPP started on January 1997. Once the specific guidelines have been implemented to the plant, training activities for the personnel involved in severe accident issues will be developed. To prepare the training exercises MAAP4 code will be used, and with this intention, a specific Jose Cabrera NPP MAAP-GRAAPH screen has been developed. Furthermore, a wide selection of MAAP input files for the simulation of different scenarios and accidental events is available. (Author)

  16. Aspects of accident management in Cernavoda NPP

    International Nuclear Information System (INIS)

    Dascalu, N.

    1999-01-01

    As a general conclusion, the accident management system as implemented at Cerna voda NPP is expected to be appropriate for handling a severe accident, should it occur, in such a way that the environmental radiological consequences would be insignificant and radiation exposure of the personnel be within recommendations. It is recognized, however, that continued development and verification of the system as well as effective personnel training programs are essential to maintain the safety level achieved. (author)

  17. Indicators of Chernobyl NPP personnel irradiation in 1986; Pokazateli obluchaemosti personala ChAEhS za 1986 g.

    Energy Technology Data Exchange (ETDEWEB)

    Vasil` chenko, V N; Nosovskij, A V; Il` ichev, S V; Snisar, I B [Virobniche Ob` jednannya Chernobil` s` ka AES, Chornobil` (Ukraine)

    1996-12-31

    The results of retrospective evaluation of ChNPP personnel irradiation during Chernobyl accident consequences mitigation are presented. Only occupational doses received within 30-km exclusion zone are considered.

  18. The accidents during shutdown conditions Temelin NPP

    International Nuclear Information System (INIS)

    Sykora, M.; Mlady, O.

    1996-01-01

    Two parallel activities oriented for the accidents during shutdown conditions are performed at Temelin NPP: Development of symptom based emergency operating procedures (EOPs) applicable for the accidents which could occur during operational modes 1 through 4; independent evaluation of plant safety as part of the Temelin Shutdown probabilistic assessment to define the accidents which could occur during mode 5 and 6 for which the EOPs must be extended. Both these activities are in progress now because Temelin plant is still in the construction phase

  19. Accident management insights after the Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    Degueldre, Didier; Viktorov, Alexandre; Tuomainen, Minna; Ducamp, Francois; Chevalier, Sophie; Guigueno, Yves; Tasset, Daniel; Heinrich, Marcus; Schneider, Matthias; Funahashi, Toshihiro; Hotta, Akitoshi; Kajimoto, Mitsuhiro; Chung, Dae-Wook; Kuriene, Laima; Kozlova, Nadezhda; Zivko, Tomi; Aleza, Santiago; Jones, John; McHale, Jack; Nieh, Ho; Pascal, Ghislain; ); Nakoski, John; Neretin, Victor; Nezuka, Takayoshi; )

    2014-01-01

    The Fukushima Daiichi nuclear power plant (NPP) accident, that took place on 11 March 2011, initiated a significant number of activities at the national and international levels to reassess the safety of existing NPPs, evaluate the sufficiency of technical means and administrative measures available for emergency response, and develop recommendations for increasing the robustness of NPPs to withstand extreme external events and beyond design basis accidents. The OECD Nuclear Energy Agency (NEA) is working closely with its member and partner countries to examine the causes of the accident and to identify lessons learnt with a view to the appropriate follow-up actions to be taken by the nuclear safety community. Accident management is a priority area of work for the NEA to address lessons being learnt from the accident at the Fukushima Daiichi NPP following the recommendations of Committee on Nuclear Regulatory Activities (CNRA), Committee on the Safety of Nuclear Installations (CSNI), and Committee on Radiation Protection and Public Health (CRPPH). Considering the importance of these issues, the CNRA authorised the formation of a task group on accident management (TGAM) in June 2012 to review the regulatory framework for accident management following the Fukushima Daiichi NPP accident. The task group was requested to assess the NEA member countries needs and challenges in light of the accident from a regulatory point of view. The general objectives of the TGAM review were to consider: - enhancements of on-site accident management procedures and guidelines based on lessons learnt from the Fukushima Daiichi NPP accident; - decision-making and guiding principles in emergency situations; - guidance for instrumentation, equipment and supplies for addressing long-term aspects of accident management; - guidance and implementation when taking extreme measures for accident management. The report is built on the existing bases for capabilities to respond to design basis

  20. Feature article. Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    Ekarinai, Masashi; Ake, Yutaka; Narabayashi, Tadashi

    2011-01-01

    This special feature article consisted of five reports and the minutes of emergency discussion meeting on Fukushima Daiichi Nuclear Power Plant (NPP) accident. Effects of the accident on future electricity supply of electric utilities and also on business development of nuclear industries were discussed. Activities of senior network team of atomic energy society of Japan (AESJ) to conduct severe accident analysis and early restoration from the accident were introduced. Circulating injection reactor cooling system and zeolite decontamination system of accumulated contaminated water was proposed. Effects of the accident on overseas reaction on nuclear development were also reported as well as personal experience of the professor in the US west coast on communications. (T. Tanaka)

  1. Chernobyl NPP accident: a year later

    International Nuclear Information System (INIS)

    Asmolov, V.G.; Borovoj, A.A.; Demin, V.F.

    1988-01-01

    Consideration is being given to measures on liquidation of Chernobyl accident aftereffects, conducted since August, 1986. One of the most important measures lay in construction of the ''shelter'', which must provide long-term conservation of accidental unit. Works on decontamination of reactor area and contaminated populated regions were continued. Measures on providing safety of population and its health protection were performed. An attention was paid to long-term investigations on studying delayed aftereffects of the accident, monitoring of invironment, development and introduction of measures on improving NPP safety. Prospects of further development of nuclear power engeneering and possibilities of improving its safety are considered

  2. NPP Krsko Severe Accident Management Guidelines Implementation

    International Nuclear Information System (INIS)

    Basic, I.; Krajnc, B.; Bilic-Zabric, T.; Spiler, J.

    2002-01-01

    Severe Accident Management is a framework to identify and implement the Emergency Response Capabilities that can be used to prevent or mitigate severe accidents and their consequences. The USA NRC has indicated that the development of a licensee plant specific accident management program will be required in order to close out the severe accident regulatory issue (Ref. SECY-88-147). Generic Letter 88-20 ties the Accident management Program to IPE for each plant. The SECY-89-012 defines those actions taken during the course of an accident by the plant operating and technical staff to: 1) prevent core damage, 2) terminate the progress of core damage if it begins and retain the core within the reactor vessel, 3) maintain containment integrity as long as possible, and 4) minimize offsite releases. The subject of this paper is to document the severe accident management activities, which resulted in a plant specific Severe Accident Management Guidelines implementation. They have been developed based on the Krsko IPE (Individual Plant Examination) insights, Generic WOG SAMGs (Westinghouse Owners Group Severe Accident Management Guidances) and plant specific documents developed within this effort. Among the required plant specific actions the following are the most important ones: Identification and documentation of those Krsko plant specific severe accident management features (which also resulted from the IPE investigations). The development of the Krsko plant specific background documents (Severe Accident Plant Specific Strategies and SAMG Setpoint Calculation). Also, paper discusses effort done in the areas of NPP Krsko SAMG review (internal and external ), validation on Krsko Full Scope Simulator (Severe Accident sequences are simulated by MAAP4 in real time) and world 1st IAEA Review of Accident Management Programmes (RAMP). (author)

  3. The demographic cequence of the Chernobyl' NPP accident

    International Nuclear Information System (INIS)

    Fashchevskij, N.I.; Palij, T.M.; Starostenko, A.G.; Nemchenko, M.P.

    1992-01-01

    In 1990 the total population evacuated due to the ChNPP accident was questionared. The analysis of the data obtained became the initial base for the demographic characteristics of this population. In 1991 about 40.000 people were planned to move. The estimation of the age of the moved, their marital status makes it possible to prognose their social child-bearing and economic value for the places where they were moved. In 1991 it was supposed that not only the moved population might have given birth to regenerations the necessary rate but also their mortality might play a significant role in the increase of the death rate

  4. Age peculiarities of reproductive morbidity in female participants of the ChNPP accident consequences clean-up (according to the figures from SRU, 1988-2012 survey period)

    International Nuclear Information System (INIS)

    Majevs'ka, Yo.O.; Buzunov, V.O.

    2015-01-01

    Data on the Chernobyl disaster survivors received from the State Registry of Ukraine are out line in the paper. Review of the level and pattern of genital system morbidity was carried out for the 17,237 female participants of the ChNPP accident cleanup works in 1986-1987 depending on time under risk upon radiation expo sure and reproductive age at exposure. Survey period lasted since 1988 till 2012. Assessment of morbidity level, confidential intervals, and statistical significance was carried out using the trial version of OpenEpiversion 2.3.1. software. Statistical significance was also rated using the z-score and t- criterion. The results of this cohort epidemiological study showed that there are some peculiarities of natural course of the female genital system disease depending on reproductive age at exposure and time under risk upon radiation impact. Comparative statistical review of the level and pattern of genital system morbidity at different times within a survey period. Exposure to ionizing radiation in the childbearing age (18-45 years old) can be a risk factor of elevated incidence of uterine leiomyoma, benign mammary dysplasia (i.e. benign breast disease), and salpingooophoritis. It is far to assume that uterine and mammary tissues are more sensitive to impact of ionizing radiation in females of the childbearing age vs. in persons exposed in premenopause or menopause

  5. Study of risc factors affecting the number of mental disorders and nervous system diseases for people who participated in liquidation of consequences of ChNPP accident

    International Nuclear Information System (INIS)

    Ivanov, V.K.; Chekin, S.Yu.; Mikhal'skij, A.I.; Petrovskij, A.M.

    1992-01-01

    Interrelation of disease incidence for liquidators and factors affecting it has been studied. The diseases (mental disorders and nervous system diseases) have been taken into account provided more than 10% of people have suffered of the above diseases. Date of getting into the accident zone; duration of work within the zone; the radiation dose accumulated were considered to be risc factors. Getting into the accident zone and duration of work within the zone of accident have been though to be the main risc factors. 3 figs.; 2 tabs

  6. Simulation of << Hot >> particles formation during the accident at the Chernobyl NPP.; Modelirovanie obrazovaniya << goryachikh >> chastits vo vremya avarii na ChAEhS.

    Energy Technology Data Exchange (ETDEWEB)

    Kashparov, V A; Ivanov, Yu A; Prister, B S; Zvarich, S I; Protsak, V P; Khomutinin, Yu V; Polyakov, V D; Gudkov, A N; Kurepin, A D; Pazukhin, Eh M [Yinstitut Syil` s` kogospodars` koyi Radyiologyiyi, Kyiv (Ukraine); [Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)

    1994-12-31

    Dispersal composition of fuel << hot >> particles formed after oxidation of real Chernobyl nuclear fuel in the air for 3-21 hours at 673-1173 K was obtained. Mechanism of ruthenium particles formation during the accident (with dispersion of nuclear fuel) as a result of ruthenium oxidation, its sublimation, condensation and restoration on materials, presented by the elements of iron group was modelled. Dynamics of relative release of fission products, as well as of transuranium and transplutonium elements from real and modeled << hot >> particles at their high temperature incineration (1273-2273 K) in the inert media was measured.

  7. Some problems connected with the Chernobyl NPP Unit 4 Accident

    International Nuclear Information System (INIS)

    Bar'yakhtar, V.G.

    1994-01-01

    The description of the eruption of radionuclides caused by the Chernobyl NPP Unit 4 Accident, including the effective time of the accident, quality and quantity of radio waste, is presented. A particular attention is given to the spotty structure of Chernobyl's contamination. The assumption that the spots distribution may be a consequence of the turbulent processes in the atmosphere is made

  8. Review of accident analyses performed at Mochovce NPP

    International Nuclear Information System (INIS)

    Siko, D.

    2000-01-01

    In this paper the review of accident analysis performed in NPP Mochovce V-1 is presented. The scope of these safety measures was defined and development in the T SSM for NPP Mochovce Nuclear Safety Improvements Report' issued in July 1995. The main objectives of these safety measures were the followings: (a) to establish the criteria for selection and classification of accidental events, as well as defining the list of initiating events to be analysed. Accident classification to the individual groups must be performed in accordance with RG 1.70 and IAEA recommendations 'Guidelines for Accidental Analysis of WWER NPP' (IAEA-EBR-WWER-01) to select boundary cases to be calculated from the scope of initiating events; (b ) to elaborate the accident analysis methodology that also includes acceptance criteria for their result evaluation, initial and boundary conditions, assumption related with the application of the single failure criteria, requirements on the analysis quality, used computer codes, as well as NPP models and input data for the accident analysis; (c) to perform the accident analysis for the Pre-operational Safety Report (POSAR); (d) to provide a synthetic report addressing the validity range of codes models and correlations, the assessment against relevant tests results, the evidence of the user qualification, the modernisation and nodding scheme for the plant and the justification of used computer codes. Analyses results showed that all acceptance criteria were met with satisfactory margin and design of the NPP Mochovce is accurate. (author)

  9. Identification of NPP accidents using support vector classification

    Energy Technology Data Exchange (ETDEWEB)

    Back, Ju Hyun; Yoo, Kwae Hwan; Na, Man Gyun [Chosun University, Gwangju (Korea, Republic of)

    2016-10-15

    In case of the accidents that happens in a nuclear power plants (NPPs), it is very important to identify its accidents for the operator. Therefore, in order to effectively manage the accidents, the initial short time trends of major parameters have to be observed and NPP accidents have to accurately be identified to provide its information to operators and technicians. In this regard, the objective of this study is to identify the accidents when the accidents happen in NPPs. In this study, we applied the support vector classification (SVC) model to classify the initiating events of critical accidents such as loss of coolant accidents (LOCA), total loss of feedwater (TLOFW), station blackout (SBO), and steam generator tube rupture (SGTR). Input variables were used as the initial integral value of the signal measured in the reactor coolant system (RCS), steam generator, and containment vessel after reactor trip. The proposed SVC model is verified by using the simulation data of the modular accident analysis program (MAAP4) code. In this study, the proposed SVC model is verified by using the simulation data of the modular accident analysis program (MAAP4) code. We used an initial integral value of the simulated sensor signals to identify the NPP accidents. The training data was used to train the SVC model. And, the trained model was confirmed using the test data. As a result, it was known that it can accurately classify five events.

  10. NPP Krsko containment environmental conditions during postulated accident

    International Nuclear Information System (INIS)

    Kozaric, M.; Cavlina, N.; Spalj, S.

    1989-01-01

    This paper presents NPP Krsko containment pressure and temperature increase during Loss of Coolant Accident (LOCA) and Main Steam Line Break (MSLB). Containment environmental condition calculation was performed by CONTEMPT4/MOD4 computer code. Design accident calculations were performed by RELAP4/MOD6 and RELAP5/MOD1 computer codes. Calculational abilities and application methodology of these codes are presented. The CONTEMPT code is described in more detail. The containment pressure and temperature time distribution are presented as well. (author)

  11. The post-accidents exploitation of Chernobyl NPP

    International Nuclear Information System (INIS)

    Nosovskij, A.V.

    1996-01-01

    Problems facing the Chernobyl NPP personnel since its commissioning and during its post-accident operation are considered. The accomplished measures on improving the power units safety, normalization of the radiation situation as well as the impact of psychological factor at the safety culture level are discussed

  12. Chernobylsk NPP accident and its medical effects

    International Nuclear Information System (INIS)

    Gus'kova, A.K.

    2000-01-01

    Medical effects of the Chernobyl accident for various groups of people engaged in liquidation of the accident aftereffects and residents of the regions affected are assessed. Specific medical and social recommendations for each of the five groups of patients are made. Special attention is paid to the health of children who were exposed to external radiation in combination with intake of iodine isotopes. Extremely unfavourable influence of the mass media on the health of people involved in the Chernobyl accident is painted out. The necessity of adequate rehabilitation measures for various categories of patients involved in a large-scale accident is emphasized [ru

  13. Intelligent system for accident identification in NPP

    International Nuclear Information System (INIS)

    Hernandez, J.L.

    1998-01-01

    Accidental situations in NPP are great concern for operators, the facility, regulatory bodies and the environmental. This work proposes a design of intelligent system aimed to assist the operator in the process of decision making initiator events with higher relative contribution to the reactor core damage occur. The intelligent System uses the results of the pre-operational Probabilistic safety Assessment and the Thermal hydraulic Safety Analysis of the NPP Juragua as source for building its knowledge base. The nucleus of the system is presented as a design of an intelligent hybrid from the combination of the artificial intelligence techniques fuzzy logic and artificial neural networks. The system works with variables from the process of the first circuit, second circuit and the containment and it is presented as a model for the integration of safety analyses in the process of decision making by the operator when tackling with accidental situations

  14. NPP Krsko Severe Accident Management Guidelines Upgrade

    International Nuclear Information System (INIS)

    Mihalina, Mario; Spalj, Srdjan; Glaser, Bruno; Jalovec, Robi; Jankovic, Gordan

    2014-01-01

    Nuclear Power Plant Krsko (NEK) has decided to take steps for upgrade of safety measures to prevent severe accidents, and to improve the means to successfully mitigate their consequences. The content of the program for the NEK Safety Upgrade is consistent with the nuclear industry response to Fukushima accident, which revealed many new insights into severe accidents. Therefore, new strategies and usage of new systems and components should be integrated into current NEK Severe Accident Management Guidelines (SAMG's). SAMG's are developed to arrest the progression of a core damage accident and to limit the extent of resulting releases of fission products. NEK new SAMG's revision major changes are made due to: replacement of Electrical Recombiners by Passive Autocatalytic Recombiners (PARs) and the installation of Passive Containment Filtered Vent System (PCFV); to handle a fuel damage situation in Spent Fuel Pool (SFP) and to assess risk of core damage situation during shutdown operation. (authors)

  15. Robot dispatching Scenario for Accident Condition Monitoring of NPP

    International Nuclear Information System (INIS)

    Kim, Jongseog

    2013-01-01

    In March of 2011, unanticipated big size of tsunami attacks Fukushima NPP, this accident results in explosion of containment building. Tokyo electric power of Japan couldn't dispatch a robot for monitoring of containment inside. USA Packbot robot used for desert war in Iraq was supplied to Fukushima NPP for monitoring of high radiation area. Packbot also couldn't reach deep inside of Fukushima NPP due to short length of power cable. Japanese robot 'Queens' also failed to complete a mission due to communication problem between robot and operator. I think major reason of these robot failures is absence of robot dispatching scenario. If there was a scenario and a rehearsal for monitoring during or after accident, these unanticipated obstacles could be overcome. Robot dispatching scenario studied for accident of nuclear power plant was described herein. Study on scenario of robot dispatching is performed. Flying robot is regarded as good choice for accident monitoring. Walking robot with arm equipped is good for emergency valve close. Short time work and shift work by several robots can be a solution for high radiation area. Thin and soft cable with rolling reel can be a good solution for long time work and good communication

  16. Assistance to the Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    Sakuma, Minoru

    2012-01-01

    Immediately after the reactor accident of Fukushima Daiichi Nuclear Power Plant occurring on March 11, 2011, JAEA started and continues to work with its every possible effort for remediation and has established the head quarter for countermeasure in Fukushima prefecture. The present paper includes main activities of assisting Fukushima area such as environmental monitoring and decontamination, technical advises to Japanese and local government, and others. Some are in cooperation with universities and others with Tokyo Electric Power Company. Towards closing the reactor accident, JAEA is joining the integrated activities for cooling the damaged reactor core and management of storing and disposal of radioactive wastes produced and large amount of remaining contaminated water to find out an adequate method for decontamination and preparing the manual for it. (S. Ohno)

  17. Radioactive waste management after NPP accident: Post-Chernobyl experience

    International Nuclear Information System (INIS)

    Mikhalevich, A.; Grebenkov, A.

    2000-01-01

    As a result of the Chernobyl NPP accident a very large amount of so-called 'Chernobyl waste' were generated in the territory of Belarus, which was contaminated much more than all other countries. These wastes relate mainly to two following categories: low-level waste (LLW) and new one 'Conventionally Radioactive Waste' (CRW). Neither regulations nor technology and equipment were sufficiently developed for such an amount and kind of waste before the accident. It required proper decisions in respect of regulations, treatment, transportation, disposal of waste, etc. (author)

  18. NPP accident scenario. Which emergency measures are planned in Switzerland?

    International Nuclear Information System (INIS)

    Flury, Christoph

    2016-01-01

    As a consequence of the reactor accident in Fukushima the Swiss government has ordered an extensive analysis of emergency planning in case of a NPP accident Switzerland. A special working group has analyzed the possible improvements of Swiss emergency planning based on the experiences in Japan. Under the special direction of the Bundesamt fuer Bevoelkerungsschutz (BABS) the agreed improvements were integrated into the emergency concept. The reference scenarios have been re-assessed and the zone concept adapted. The emergency measures include shelter-type rooms (basement or window-less rooms), the preventive distribution of iodine pills, measures concerning agriculture, aquatic systems, preventive evacuation, traffic regulations, and delayed evacuation.

  19. Some results of liquidation of accident effects at the Chernobyl' NPP

    International Nuclear Information System (INIS)

    Ignatenko, E.I.; Komarov, V.I.; Zverkov, V.V.; Proskuryakov, A.G.

    1989-01-01

    The results of works dealing with liquidation of accident effects at the Chernobyl' NPP are generalized. Some measures realized are estimated. Suggestions directed to efficiency increase when eliminating such accident effects are formulated

  20. Radionuclide migration in soil within the estrangement zone of ChNPP

    International Nuclear Information System (INIS)

    Mikhalkin, G.S.; Arkhipov, A.N.; Arkhipov, N.P.; Sukhoruchkin, A.K.

    1992-01-01

    The problems of the radionuclide migration and redistribution in soil within the estrangement zone of ChNPP have been discussed. It has been demonstrated that the surface radioactive contamination of soil that has been represented principally by the particles of the waste nuclear fuel eventually migrates into soil depth. In this case the radionuclides remain principally the fuel matrix components, the fuel matrix decomposing gradually and releasing the radionuclides. The mechanisms of the radionuclide migration can be described with the quasi-diffusion migration model in most cases. On the 5th year since the accident the major portion of the radionuclides (95-99%) is still kept within 0-5 cm layer of soil. 3 figs.; 7 tabs

  1. Development of filter module for passive filtration and accident gas release confinement system for NPP

    International Nuclear Information System (INIS)

    Yelizarov, P.G.; Efanov, A.D.; Martynov, P.N.; Masalov, D.P.; Osipov, V.P.; Yagodkin, I.V.

    2005-01-01

    Full text of publication follows: One of the urgent problems of the safe NPP operation is air cleaning from radioactive aerosols and volatile iodine compounds under the accident operation conditions of NPP. A principally new passive accident gas release confinement system is used as the basis of the designs of new generation reactor power blocks under the-beyond-design-basis accident conditions with total loss of current. The basic structural component of the passive filtration system (PFS) is the filter-sorber being heated up to 300 deg. C. The filter-sorber represents a design consisting of 150 connected in parallel two-step filtering modules. The first step is intended to clean air from radioactive aerosols, the second one - to clean air from radioactive iodine and its volatile compounds. The filter-sorber is located in the upper point of the exterior protection shell. Due to natural convection, it provides confinement of r/a impurities and controlled steam-gas release from the inter-shell space into atmosphere. The basic specific design feature is the two-section design of the PFS filter module consisting of a coarse-cleaning section and a fine-cleaning section. A combination of layer-by-layer put filtering materials on the basis of glass fiber and metal fiber. The pilot PFS filter module specimen tests run in conditions modeling accident situation indicated that at a filtration rate of 0,3 cm/s the aerodynamic resistance of the module does not exceed 12 Pa, the filtration effectiveness equals 99,99 % in terms of aerosol, no less than 99,9% in terms of radioactive 131 I and no less than 99,0% in terms of organic compounds of iodine (CH 3 131 I); the dust capacity amounts to a value above 50 g/m 2 . The obtained results of tests comply with the design requirements imposed on the PFS filter-sorber module. (authors)

  2. Radionuclides contamination of fungi after accident on the Chernobyl NPP

    Energy Technology Data Exchange (ETDEWEB)

    Zarubina, Nataliia E.; Zarubin, Oleg L. [Institute for Nuclear Research of National Academy of Sciense, 03680, pr-t Nauki, 47, Kiev (Ukraine)

    2014-07-01

    Accumulation of radionuclides by the higher fungi (macromycetes) after the accident on the Chernobyl atomic power plant in 1986 has been studied. Researches were spent in territory of the Chernobyl alienation zone and the Kiev region. Our research has shown that macromycetes accumulate almost all types of radionuclides originating from the accident ({sup 131}I, {sup 140}Ba /{sup 140}La, {sup 103}Ru, {sup 106}Ru, {sup 141}Ce, {sup 144}Ce, {sup 95}Nb, {sup 95}Zr, {sup 137}Cs and {sup 134}Cs). They accumulate the long-living {sup 90}Sr in much smaller (to 3 - 4 orders) quantities than {sup 137}Cs. We have established existence of two stages in accumulation of {sup 137}Cs by higher fungi after the accident on the Chernobyl NPP: the first stage resides in the growth of the concentration, the second - in gradual decrease of levels of specific activity of this radionuclide. Despite reduction of {sup 137}Cs specific activity level, the content of this radionuclide at testing areas of the 5-km zone around the Chernobyl NPP reaches 1,100,000 Bq/kg of fresh weight in 2013. We investigated dynamics of accumulation of Cs-137 in higher fungi of different ecological groups. One of the major factors that influence levels of accumulation of {sup 137}Cs by fungi is their nutritional type (ecological group). Fungi that belong to ecological groups of saprotrophes and xylotrophes accumulate this radionuclide in much smaller quantities than symbio-trophic fungi. As a result of the conducted research it has been established that symbio-trophic fungi store more {sup 137}Cs than any other biological objects in forest ecosystems. Among the symbio-trophic fungi species, species showing the highest level of {sup 137}Cs contamination vary in different periods of time after the deposition. It is connected with variability of quantities of these radio nuclides accessible for absorption at the depth of localization of the main part of mycelium of each species in a soil profile. Soil contamination

  3. Generalization of Nuclear Safety and Course of Accident Events Research in the Ignalina NPP

    International Nuclear Information System (INIS)

    Kaliatka, A.; Uspuras, E.

    2001-01-01

    The safety analysis shown that after implementation of SAR recommendations Ignalina NPP is adequately protected against accidents which required fast initiation of automatic protections. In case of accidents with long-term loss of core cooling additional operator actions are required. Accident management in case long-term core cooling are analyzed in this paper. (author)

  4. Lessons learned and implications of the Fukushima NPP accidents

    Energy Technology Data Exchange (ETDEWEB)

    Tokuhiro, A., E-mail: tokuhio@uidaho.edu [Univ. of Idaho, Idaho Falls, ID (United States)

    2014-07-01

    The global nuclear 'enterprise' is now 3-1/2 years (March 11, 2011) beyond the historic Tohoku earthquake (M9.0), subsequent tsunami (~14-15m waves), and unfortunately, the continuing consequences of the 'Fukushima nuclear power plant (NPP) accident. We now live in the post-Fukushima nuclear era. First let us pay our respects to this tragic loss-of-life (~16,000 fatalities) as a result of the earthquake and tsunami; also 10-years earlier in 2004, centered further south in the Indian Ocean (230,000+ fatalities). The movie, 'The Impossible', was a reminder that indeed, energy provides sustenance and socio-economic development for humankind. Energy will determine the state of AsiaPacific (AP) in years to come. Over the past 15-years, AP has clearly had increasing means to lead global economic growth, relative to stagnating economies of scale in Europe and U.S. AP also has both existing and emerging larger-scale industrial ambitions and capital to construct new nuclear power plants (NPPs). China has some 25-28 units under construction at 11 sites; the near-term goal is to establish 40GW of generating capacity by 2020 and to reach some 70-75GW approximately 10 years later. Although some investments are also being made in renewable energy, the demand for capacity clearly dictates further growth in nuclear power. However, unless high expectations for safety, safety culture are concurrently encouraged, we may face the next nuclear accident again in Asia. This work looks at the technical and non-technical lessons learned from the Fukushima Daiichi accident and the implications that we cannot afford to ignore. (author)

  5. Lessons learned and implications of the Fukushima NPP accidents

    International Nuclear Information System (INIS)

    Tokuhiro, A.

    2014-01-01

    The global nuclear 'enterprise' is now 3-1/2 years (March 11, 2011) beyond the historic Tohoku earthquake (M9.0), subsequent tsunami (~14-15m waves), and unfortunately, the continuing consequences of the 'Fukushima nuclear power plant (NPP) accident. We now live in the post-Fukushima nuclear era. First let us pay our respects to this tragic loss-of-life (~16,000 fatalities) as a result of the earthquake and tsunami; also 10-years earlier in 2004, centered further south in the Indian Ocean (230,000+ fatalities). The movie, 'The Impossible', was a reminder that indeed, energy provides sustenance and socio-economic development for humankind. Energy will determine the state of AsiaPacific (AP) in years to come. Over the past 15-years, AP has clearly had increasing means to lead global economic growth, relative to stagnating economies of scale in Europe and U.S. AP also has both existing and emerging larger-scale industrial ambitions and capital to construct new nuclear power plants (NPPs). China has some 25-28 units under construction at 11 sites; the near-term goal is to establish 40GW of generating capacity by 2020 and to reach some 70-75GW approximately 10 years later. Although some investments are also being made in renewable energy, the demand for capacity clearly dictates further growth in nuclear power. However, unless high expectations for safety, safety culture are concurrently encouraged, we may face the next nuclear accident again in Asia. This work looks at the technical and non-technical lessons learned from the Fukushima Daiichi accident and the implications that we cannot afford to ignore. (author)

  6. Vertical Migration of Radionuclides in Soils on the Chernobyl Nuclear Power Plant (ChNPP) Exclusion Zone (1987-2007)

    Science.gov (United States)

    Jannik, G. T.; Ivanov, Y. A.; Kashparov, V. A.; Levchuk, S. E.; Bondarkov, M. D.; Maksymenko, A. M.; Farfan, E. B.; Marra, J. C.

    2009-12-01

    In 1986-1987, a set of experimental sites for studies of vertical migration of radionuclides released from the ChNPP was established in the ChNPP Exclusion Zone for various fallout plumes. The sites were selected considering local terrain and geo-chemical conditions, as well as physical and chemical characteristics of the fallout. The experimental sites included grasslands, and pre-Chernobyl cultivated meadows and croplands. Vertical migration of radionuclides in the ChNPP Exclusion Zone grasslands was evaluated. Parameters of 137Cs, 90Sr, and 239,240Pu transfer were calculated and the periods during which these radionuclides reach their ecological half-life in the upper 5 cm soil layer were estimated. Migration capabilities of these radionuclides in the grassland soils tend to decrease as follows: 90Sr >137Cs ≥ 239,240Pu. A significant retardation of the 137Cs vertical migration was shown in the grasslands long after the Chernobyl accident. During the 21st year after the fallout, average Tecol values for 137Cs (the period of time it takes in the environment for 137Cs to reach half the value of its original concentration in the upper 5 cm soil layer, regardless of physical decay) are as follows: 180 - 320 years for grassland containing automorphous mineral soils of a light granulometric composition; and 90 - 100 years for grassland containing hydromorphous organogenic soils. These values are significantly higher than those estimated for the period of 6-9 years after the fallout: 60 - 150 years and 11 - 20 years, respectively. The absolute 137Cs Tecol values are by factors of 3-7 higher than 137Cs radiological decay values long after the accident. Changes in the exposure dose resulting from the soil deposited 137Cs only depend on its radiological decay. This factor should necessarily be considered for development of predictive assessments, including dose exposures for the hypothetical population in case of their re-evacuation to the exclusion areas. The obtained

  7. Issues on safe radioactive waste management at ChNPP site in International Shelter Implementation Plan

    International Nuclear Information System (INIS)

    Bykov, V.; Kilochytska, T.; Gromyko, S.; Kadkin, Y.; Kondratiev, S.; Pavlenko, A.; Bogorinski, P.

    2003-01-01

    The International Shelter Implementation Plan (SIP) [1], is aimed to convert the ChNPP unit 4, destroyed by a beyond-design accident in 1986, into an environmentally safe facility by means of large-scale projects such as stabilization of the existing Sarcophagus (Shelter), construction of a New Safe Confinement (NSC), and installation of engineering and monitoring systems. This report presents some important safety issues concerning radioactive waste (RAW) management at the Shelter. One of the main problems of RAW management is to dispose of large volumes of RAW generated during ground preparation work. It is necessary that RAW be sorted carefully to separate low-active radioactive waste (LLW), which will be the majority, from high-level waste. Considering the fact that the Shelter is in the exclusion zone, the interim storage of LLW in this zone is possible, but a set of safety measures is required, e.g. prevention of dust generation or spreading of radioactivity with water. Another problem is high level RAW management. Highly radioactive fragments of the core, including fuel were ejected during the accident and are now buried under the man-made layer around the Shelter. Unanticipated disclosure of such fragments may happen during any ground preparation work as well as during clearing of premises inside the damaged buildings. Therefore, permanent radiation monitoring is required to prevent any intolerable exposure of workers. Unanticipated disclosure of high-active radioactive waste (HLW) could lead to considerable delay of any work. Since it is particularly difficult to remove HLW from those locations, which can not be easily accessed with removal equipment, such waste needs to be confined and properly shielded at in situ. Due to absence of a permanent HLW storage, an interim storage needs to be provided for in the territory of the Sarcophagus. (author)

  8. NPP physical protection and information security as necessary conditions for reducing nuclear and radiation accident risks

    International Nuclear Information System (INIS)

    Pogosov, O.Yu.; Derevyanko, O.V.

    2017-01-01

    The paper focuses on the fact that nuclear failures and incidents can lead to radioactive contamination of NPP premises. Nuclear and radiation hazard may be caused by malefactors in technological processes when applying computers or inadequate control in case of insufficient level of information security.The researchers performed analysis of factors for reducing risks of nuclear and radiation accidents at NPPs considering specific conditions related to information security of NPP physical protection systems. The paper considers connection of heterogeneous factors that may increase the risk of NPP accidents, possibilities and ways to improve adequate modelling of security of information with limited access directly related to the functioning of automated set of engineering and technical means for NPP physical protection. Within the overall Hutchinson formalization, it is proposed to include additional functional dependencies on indicators specific for NPPs into analysis algorithms.

  9. Analysis of heavy radiological accidents in NPP and gamma-irradiators

    International Nuclear Information System (INIS)

    Angelov, V.; Semova, T.; Bonchev, Ts.

    1995-01-01

    A review of several heavy radiological accidents, their cause, character, radioactivity emission, victims and economical impact is presented in the form of uniform tables. Eleven cases of incidents in power plants and 4 cases of accidents involving powerful gamma irradiators are considered. Radiological accidents in Bulgaria, not connected with the Kozloduy NPP, are listed. The human factor has been identified as the main cause for most of the accidents. It is stressed that the probability of heavy accident increases at the time of reactor refuelling, repair or testing. Technical failures could be eliminated by improved check and diagnostics procedures. 2 tabs., 12 refs

  10. Analysis of heavy radiological accidents in NPP and gamma-irradiators

    Energy Technology Data Exchange (ETDEWEB)

    Angelov, V [Civil Defence Administration, Sofia (Bulgaria); Semova, T; Bonchev, Ts [Sofia Univ. (Bulgaria). Fizicheski Fakultet

    1996-12-31

    A review of several heavy radiological accidents, their cause, character, radioactivity emission, victims and economical impact is presented in the form of uniform tables. Eleven cases of incidents in power plants and 4 cases of accidents involving powerful gamma irradiators are considered. Radiological accidents in Bulgaria, not connected with the Kozloduy NPP, are listed. The human factor has been identified as the main cause for most of the accidents. It is stressed that the probability of heavy accident increases at the time of reactor refuelling, repair or testing. Technical failures could be eliminated by improved check and diagnostics procedures. 2 tabs., 12 refs.

  11. Fission product source from Ignalina NPP in case of loss-of-coolant accidents

    International Nuclear Information System (INIS)

    Ubonavicius, E.; Rimkevicius, S.

    2001-01-01

    The release of radioactive materials to the environment is of special importance in the case of any accident at Nuclear Power Plants (NPP). The integrated analysis of thermal-hydraulic parameters behavior and radioactive fission products (FP) transport and deposition in the compartments play an important role in the evaluation of FP release to the environment and determines the irradiation dozes of personnel and public. In this report the transport and the deposition of radioactive material in the Ignalina NPP unit 1 compartments as well as the FP source term to the environment in the case of design basis loss-of-coolant accidents are discussed. The calculation models for the evaluation of FP transport and deposition as well as the results of performed calculations of several accidents at Ignalina NPP are presented. (author)

  12. Accidents with nuclear power plants, ch. 11

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    A recalculation of the consequences of nuclear power plant accidents is presented taking into account different parameters or different quantities than those usually accepted. A case study of a nuclear power plant planned for the Eems-river estuary in the Netherlands is presented

  13. Diversity of microflora at the fourth destroyed unit of the ChNPP

    International Nuclear Information System (INIS)

    Parenyuk, O.Yu.; Shavanova, K.Je.; Yilljenko, V.V.; Gudkov, Yi.M.; Nanba, K.; Takasi, T.; Syimutyin, Yi.O.; Samofalova, D.O.; Ribalka, V.B.

    2017-01-01

    DNA of the substrate, sampled from six points in the destroyed 4-th power unit of ChNPP, where the dose rate on the microorganisms ranges from 0.008 to 0.12 Gy/h, was analyzed by New Generation Sequencing technology. It was found that the most diverse and stable microbiome occurs in sample, located outside of the ''Ukryttya'' object on the industrial site (conditional control). There are no dominants in it, which means that it is the most balanced and approximate to the general state of the soil microbiome of ecosystems surrounding the ChNPP. As for the sample, taken from the spot, where the dose rate was the highest, total number of species represented appeared eight times smaller, but dominance index was the highest, which indicates the formation of distinct microbiome dominants.

  14. RADIATION HYGIENIC CONSEQUENCES OF THE ACCIDENT AT THE CHERNOBYL NPP AND THE TASKS OF THEIR MINIMIZATION

    Directory of Open Access Journals (Sweden)

    G. G. Onischenko

    2009-01-01

    Full Text Available The paper presents data on the role and results of activities of Rospotrebnadzor bodies and institutions in the field of ensuring population radiation protection during various periods since accident at the Chernobyl NPP. Radiation hygienic characterization of territories affected by radioactive contamination from the accident, population exposure dose range, issues of ensuring radiological well-being of population and ways of their solution are being presented in the paper.

  15. Analysis of the behaviour of the Kozloduy NPP Unit 3 under severe accident conditions

    International Nuclear Information System (INIS)

    Velev, V.; Saraeva, V.

    2004-01-01

    The objective of the analysis is to study the behaviour of the Kozloduy NPP Unit 3 under severe accident conditions. The analysis is performed using computer code MELCOR 1.8.4. This report includes a brief description of Unit 3 active core as well as description and comparison of the key events

  16. The intelligent system for accident identification in NPP

    International Nuclear Information System (INIS)

    Hernandez, Jorge Luis.

    1998-01-01

    Accidental situations in NPP are of greet concern for operators, the facility, regulatory bodies and the environment. This work proposes a design of intelligent system aimed to assist the operator in the process of decision making when initiator events with higher relative contribution to the reactor core damage occur. The intelligent System uses the results of the pre operational Probabilistic Safety Assessment and the Thermal hydraulic Safety Analyses of the NPP Juragua as source for building its knowledge base. The nucleus of the system is presented as a design of an intelligent hybrid system from the combination of the artificial intelligence techniques: fussy logic and artificial neural networks. The system works with variables from the process of the firsts circuit, second circuit and the containment and it is presented as a model for the integration of safety analyses in the process of decision making by the operator when tackling with accidental situations

  17. Crisis communication at NPP-Fukushima 1 accident

    International Nuclear Information System (INIS)

    Tsuchida, S.

    2012-01-01

    The crisis communication at the TEPCO Fukushima Daiichi Nuclear Power Plant accident in the disaster 3.11 was examined. I discussed the nature of crisis communication which is information exchange between the persons responsible to the accident and the public. And Myth of Panic and Elite Panic were also discussed. (author)

  18. Reasons for the RBMK reactor accident at the Chernobyl NPP

    International Nuclear Information System (INIS)

    Novikov, I.I.; Kruzhilin, G.N.; Anan'ev, E.P.

    1995-01-01

    This analysis of the reasons for the Chernobyl Reactor accident in 1986 places the blame firmly with the reactor operators, who, it is argued, made a number of dramatic mistakes while controlling the reactor. The report also included an additional analysis of the causes of the accident. (UK)

  19. Comparison of HRA methods based on WWER-1000 NPP real and simulated accident scenarios

    International Nuclear Information System (INIS)

    Petkov, Gueorgui

    2010-01-01

    Full text: Adequate treatment of human interactions in probabilistic safety analysis (PSA) studies is a key to the understanding of accident sequences and their relative importance in overall risk. Human interactions with machines have long been recognized as important contributors to the safe operation of nuclear power plants (NPP). Human interactions affect the ordering of dominant accident sequences and hence have a significant effect on the risk of NPP. By virtue of the ability to combine the treatment of both human and hardware reliability in real accidents, NPP fullscope, multifunctional and computer-based simulators provide a unique way of developing an understanding of the importance of specific human actions for overall plant safety. Context dependent human reliability assessment (HRA) models, such as the holistic decision tree (HDT) and performance evaluation of teamwork (PET) methods, are the so-called second generation HRA techniques. The HDT model has been used for a number of PSA studies. The PET method reflects promising prospects for dealing with dynamic aspects of human performance. The paper presents a comparison of the two HRA techniques for calculation of post-accident human error probability in the PSA. The real and simulated event training scenario 'turbine's stop after loss of feedwater' based on standard PSA model assumptions is designed for WWER-1000 computer simulator and their detailed boundary conditions are described and analyzed. The error probability of post-accident individual actions will be calculated by means of each investigated technique based on student's computer simulator training archives

  20. Environmental and agricultural impacts of the Chernobyl NPP accident on the countries of the northern hemisphere

    International Nuclear Information System (INIS)

    Yang Xuexian

    1990-12-01

    The accident at the Chernobyl Nuclear Power Plant (NPP) on April 26, 1986 resulted in large quantities of radioactive materials being released into the atmosphere. The environmental contaminations and agricultural impacts of the accident on the countries of the northern hemisphere were reviewed. Radiological consequences of the accident were briefly assessed. The data were presented on the results of radioactivity monitoring for air, ground and water, average individual effective dose commitment for each county, and levels of contamination on plant cover, milk, meat in live animals, food, aquatic, and other agricultural products etc. The transfer coefficients of radionuclides in grass-(cow)-milk were listed. Finally, problems on radioecology were discussed

  1. Integral thermal model of severe accident dynamics of NPP with containment

    International Nuclear Information System (INIS)

    Arutyunyan, R.V.; Bol'shov, L.A.; Vasil'ev, A.D.; Kamennov, G.P.

    1991-01-01

    An analytical model of the interaction of reactor core remains with concrete during severe accidents at nuclear power plants is considered. Time dependences of side and radial concrete melting are plotted. Time dependences of containment atmosphere temperature and pressure during a severe accident at nuclear power plants are investigated analytically and numerically. The sensitivity of the results to the coefficient values in the problem is studied within the range of their concertainty. The Kaverna-1 is described. The results of modelling a severe NPP accident which have been obtained using the Kaverna-1 package are presented

  2. Environmental Impact Assessment following a Nuclear Accident to a Candu NPP

    International Nuclear Information System (INIS)

    Margeanu, C.A.; Margeanu, S.; Olteanu, Gh.

    2009-01-01

    The paper presents calculations of nuclear accident consequences to public and environment, for a Candu NPP using advanced fuel in two hypothetical accident scenarios: (1) large LOCA followed by partial core melting with early containment failure; (2) late core disassembly and containment bypass through ECCS. During both accidents a release occurs, radioactive contaminants being dispersed into atmosphere. As reference, estimations for Candu standard UO 2 fuel were used. The radioactive core inventory was obtained by using ORIGEN-S computer code included in ORNL,SCALE 5 programs package. Radiological consequences assessment to public and environment was performed by means of PC COSYMA computer code

  3. Sensitivity Analysis of Evacuation Speed in Hypothetical NPP Accident by Earthquake

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung-yeop; Lim, Ho-Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Effective emergency response in emergency situation of nuclear power plant (NPP) can make consequences be different therefore it is regarded important when establishing an emergency response plan and assessing the risk of hypothetical NPP accident. Situation of emergency response can be totally changed when NPP accident caused by earthquake or tsunami is considered due to the failure of roads and buildings by the disaster. In this study evacuation speed has been focused among above various factors and reasonable evacuation speed in earthquake scenario has been investigated. Finally, sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Evacuation scenario can be entirely different in the situation of seismic hazard and the sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Various references were investigated and earthquake evacuation model has been developed considering that evacuees may convert their evacuation method from using a vehicle to walking when they face the difficulty of using a vehicle due to intense traffic jam, failure of buildings and roads, and etc. The population dose within 5 km / 30 km have been found to be increased in earthquake situation due to decreased evacuation speed and become 1.5 - 2 times in the severest earthquake evacuation scenario set up in this study. It is not agreed that using same emergency response model which is used for normal evacuation situations when performing level 3 probabilistic safety assessment for earthquake and tsunami event. Investigation of data and sensitivity analysis for constructing differentiated emergency response model in the event of seismic hazard has been carried out in this study.

  4. Sensitivity Analysis of Evacuation Speed in Hypothetical NPP Accident by Earthquake

    International Nuclear Information System (INIS)

    Kim, Sung-yeop; Lim, Ho-Gon

    2016-01-01

    Effective emergency response in emergency situation of nuclear power plant (NPP) can make consequences be different therefore it is regarded important when establishing an emergency response plan and assessing the risk of hypothetical NPP accident. Situation of emergency response can be totally changed when NPP accident caused by earthquake or tsunami is considered due to the failure of roads and buildings by the disaster. In this study evacuation speed has been focused among above various factors and reasonable evacuation speed in earthquake scenario has been investigated. Finally, sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Evacuation scenario can be entirely different in the situation of seismic hazard and the sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Various references were investigated and earthquake evacuation model has been developed considering that evacuees may convert their evacuation method from using a vehicle to walking when they face the difficulty of using a vehicle due to intense traffic jam, failure of buildings and roads, and etc. The population dose within 5 km / 30 km have been found to be increased in earthquake situation due to decreased evacuation speed and become 1.5 - 2 times in the severest earthquake evacuation scenario set up in this study. It is not agreed that using same emergency response model which is used for normal evacuation situations when performing level 3 probabilistic safety assessment for earthquake and tsunami event. Investigation of data and sensitivity analysis for constructing differentiated emergency response model in the event of seismic hazard has been carried out in this study

  5. About the causes and circumstances of the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Shteynberg, N.

    1992-01-01

    The Chernobyl accident is the product of unsatisfactory solutions to scientific-technical, socio-economic and human problems. The documentarily recorded power excursion of the reactor and its rise velocity as well as the quick pressure rise in the separator drum admit the conclusion that the cause of the accident was the rapid power excursion of the reactor and not some external influence. (DG) [de

  6. Advances in safety countermeasures at the Tomari NPP of Hokkaido Electric Power on the basis of Fukushima Daiichi NPP accident. Fire protection and other advances

    International Nuclear Information System (INIS)

    Shibata, Taku; Dasai, Katsumi

    2014-01-01

    Fire protections for the nuclear power plants have been based on the fire laws and the conventional guide. After Fukushima Daiichi NPP accident, many safety countermeasures - also about Fire Protection - have been discussed in the Japanese authorities. This paper shows our present activities in the Tomari NPP about the fire protections from the view points of Fire Prevention, Fire Detection/Suppression Systems and Fire Protection, and other advances. (author)

  7. Checking of seismic and tsunami hazard for coastal NPP of Chinese continent after Fukushima nuclear accident

    Institute of Scientific and Technical Information of China (English)

    Chang Xiangdong; Zhou Bengang; Zhao Lianda

    2013-01-01

    A checking on seismic and tsunami hazard for coastal nuclear power plant (NPP) of Chinese continent has been made after Japanese Fukushima nuclear accident caused by earthquake tsunami.The results of the checking are introduced briefly in this paper,including the evaluations of seismic and tsunami hazard in NPP siting period,checking results on seismic and tsunami hazard.Because Chinese coastal area belongs to the continental shelf and far from the boundary of plate collision,the tsunami hazard is not significant for coastal area of Chinese continent.However,the effect from tsunami still can' t be excluded absolutely since calculated result of Manila trench tsunami source although the tsunami wave is lower than water level from storm surge.The research about earthquake tsunami will continue in future.The tsunami warning system and emergency program of NPP will be established based on principle of defense in depth in China.

  8. 137Cs and 90Sr in the water of the ChNPP cooling pond

    Directory of Open Access Journals (Sweden)

    V. V. Kanivets

    2014-12-01

    Full Text Available Results of long-term observations on 137Cs and 90Sr concentration in water mass of the ChNPP Cooling Pond are presented. Drastic transformation of the intrinsic trend in changes with time of averaged radionuclides con-tent in water is clearly demonstrated alongside with the spatial heterogeneity of radioactive contamination of water body. The cycling character of seasonal changes of 137Cs activity concentration in water is being linked to hydrochemical, temperature and oxygen regimes of the Cooling Pond.

  9. Information on the Chernobyl NPP accident and its consequencies prepared for IAEA

    Energy Technology Data Exchange (ETDEWEB)

    1986-11-01

    The information on the accident at the 4th power unit of the Chernobyl NPP and its consequences prepared for IAEA on the basis of the conclusions made by the Government commission constituted for investigating the accident causes and implementing the necessary emergency and reconstruction measures is given. The accident with reactor core disruption and partial destruction of the building Lappened on 26.04.86 at 1 hour and 23 minutes. The accident occurred before reactor shut-down for planned repairs during the testing of one of turbogenerators. The design features of the RBMK-1000 reactor plant, its main physical characteristics and parameters of the NPP safety system are considered. The chronology of the accident development and the results of analysis carried out using a mathematical model are given. The causes of the accident are analyzed. The measures for preventing the accident development and lessening its consequences as well as those for the environment radioactive contamination control and sanitary provisions are described in detail. The conclusion is made that the original cause of the accident is highly improbable combination of disorder and errors in operational conditions made by the personnel of the power unit. It is emphasized that development of the world nuclear engineering, besides advantages in the field of power supply and natural resources conservation, incurs also damages of international character. Among these are transboundary radioactivity transport, in particular, during serious radiation accidents and the danger of international terrorism and specific radiation hazard of nuclear objects under war conditions. All this defines the key necessity of deep international cooperation in the field of nuclear power engineering and its safeguarding.

  10. Characteristics of border nervous-mental disorders for victims connected with the Chernobyl' NPP accident

    International Nuclear Information System (INIS)

    Sapsaj, S.A.

    1992-01-01

    It is revealed that border nervouse-mental disorders for victims connected with the Chernobyl' NPP accident are the most widely spread diseases. Their specific features are the following: prevalence of the disorders from asthenic and psycho-organic circles; relatively small positive dynamics in the cause of treatment; uniformity in symptoms, which do not depend on psychological characteristics of a person. Particular efforts should be concentrated on developing psychosocial programs for rendering the victims help. 3 refs

  11. New methods for rapid data acquisition of contaminated land cover after NPP accident

    International Nuclear Information System (INIS)

    Hulka, J.; Cespirova, I.

    2008-01-01

    Aim of the research project is the analysis of the modem and rapid reliable data acquisition methods for agricultural countermeasures, feed-stuff restrictions and clean-up of large contaminated areas after NPP accident. Acquiring agricultural reliable data especially based on satellite technology and analysis of landscape contamination (based on computer code vs. in situ measurements, airborne and/or terrestrial mapping of contamination) are discussed. (authors)

  12. New methods for rapid data acquisition of contaminated land cover after NPP accident

    International Nuclear Information System (INIS)

    Hulka, J.; Cespirova, I.

    2009-01-01

    Aim of the research project is the analysis of the modem and rapid reliable data acquisition methods for agricultural countermeasures, feed-stuff restrictions and clean-up of large contaminated areas after NPP accident. Acquiring agricultural reliable data especially based on satellite technology and analysis of landscape contamination (based on computer code vs. in situ measurements, airborne and/or terrestrial mapping of contamination) are discussed. (authors)

  13. Investigation and evaluation for environmental impact at Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    2012-01-01

    In 2012, JNES investigated the weather data and the environmental monitoring data and constructed the method to specify contribution of the environmental impact from each plant based on the dose analysis result at Unit 1-3 of Fukushima Daiichi NPP accident. JNES calculated the dose rate in an accident early stage based on analysis of a monitoring data. Moreover, JNES evaluated the dose by additional release of the radioactive material in case of assuming the loss of coolant injection to a nuclear reactor by the request of NISA. (author)

  14. Radiological environment within an NPP after a severe nuclear accident

    Science.gov (United States)

    Andgren, Karin; Fritioff, Karin; Buhr, Anna Maria Blixt; Huutoniemi, Tommi

    2017-09-01

    The radiological environment following a severe nuclear accident can be visualised on building layouts. The direct radiation in an area (or room) can be visualized on the layout by a colouring scheme depending on the dose rate level (for example orange for high gamma dose rate level and purple for an intermediate gamma dose rate level). Following the Fukushima accident, a need for update of these layouts has been identified at the Swedish nuclear power plant of Forsmark. Shielding calculations for areas where access is desired for severe accident management have been performed. Many different sources of radiation together with different types of shielding material contribute to the dose that would be received by a person entering the area. External radiation from radioactivity within e.g. pipes and components is considered and also external radiation from radioactivity in the air (originating from diffuse leakage of the containment atmosphere). Results are presented as dose rates for relevant dose points together with a method for estimating the dose rate levels for each of the rooms of the reactor building.

  15. Radiological environment within an NPP after a severe nuclear accident

    Directory of Open Access Journals (Sweden)

    Andgren Karin

    2017-01-01

    Full Text Available The radiological environment following a severe nuclear accident can be visualised on building layouts. The direct radiation in an area (or room can be visualized on the layout by a colouring scheme depending on the dose rate level (for example orange for high gamma dose rate level and purple for an intermediate gamma dose rate level. Following the Fukushima accident, a need for update of these layouts has been identified at the Swedish nuclear power plant of Forsmark. Shielding calculations for areas where access is desired for severe accident management have been performed. Many different sources of radiation together with different types of shielding material contribute to the dose that would be received by a person entering the area. External radiation from radioactivity within e.g. pipes and components is considered and also external radiation from radioactivity in the air (originating from diffuse leakage of the containment atmosphere. Results are presented as dose rates for relevant dose points together with a method for estimating the dose rate levels for each of the rooms of the reactor building.

  16. Health of the population having suffered after the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Stozharov, A.N.; Zubovich, V.K.; Lazyuk, G.I.; Stel'makh, V.A.

    1997-01-01

    Are given the results of researches carried out in Belarus in 1996 on the following directions: study of influence of radiological consequences of the Chernobyl accident on health of the people; development of methods and means of diagnostics, treatment and preventive maintenance of diseases at various categories of victims; development and introduction in practice of effective methods of preventive maintenance and treatment of diseases of both mother and child in conditions of influence of the Chernobyl accident consequences; study of genetic consequences caused by the Chernobyl NPP accident and development of effectual measures of their prevention; creation of effective preventive means and food additives for treatment and rehabilitation of the persons having suffered after the Chernobyl accident; optimization of system of measures for health saving of the having suffered population and development of ways of increase of its efficiency

  17. Control assembly ejection accident analysis for WWER-440 (Armenian NPP)

    International Nuclear Information System (INIS)

    Bznuni, S.; Malakyan, Ts.; Amirjanyan, A.; Ghasabyan, L.

    2007-01-01

    Control Assembly ejection in WWER-440 initiated by the loss of integrity of the Control Assemblies drive housing has been analyzed. This event causes a very rapid reactivity insertion to the core and small break LOCA which potentially could lead to rapid power increase and redistribution of heat release in the core resulting in a fuel, cladding and coolant temperature rise; primary pressure increase, radiological consequences due to loss of primary coolant and potential loss of cladding integrity and fuel disintegration (if applicable). Methodology of the analysis is based on conservative assumptions as well as on deterministic approach for selection of functioning logic of systems and equipment's to maximize reactor core power and minimize power decreasing reactivity feedback. Computational analyses were performed by 3D kinetics PARCS-RELAP coupled code. WWER-440 fuel cross-section libraries, diffusion coefficients and kinetics parameters were calculated by HELOS code. In this paper analysis of accident for Hot Full Power was presented. Results of analysis show that ANPP WWER-440 reactor design meets acceptance criteria prescribed for RIA type design based accidents (Authors)

  18. Accident localization system with jet condensers for VVER 440-V 230 NPP at Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Murani, J.

    1995-01-01

    The operational safety of the V1 nuclear power plant (NPP) is unsatisfactory and does not correspond to present requirements as to nuclear safety. Further NPP operation after 1995 is conditional on nuclear safety enhancement to a level comparable with that in West European countries. This aim should be achieved by a principal reconstruction involving in addition to others also backfitting the V1 NPP with technical facilities aimed at coping with a design basis accident (DBA).To cope with such an accident the Power Equipment Research Institute (VUEZ) designed an accident localization system with jet condensers. This system consists of (a) an air trap (one for each unit, mutually interconnected) with an expansion bell enclosed within, placed on a plate with 200 pipes of jet condensers passing through, and (b) a connecting duct between the hermetic zone and the air trap. The vertical jet condenser is an essential element of the system designed for steam condensation. Apart from condensation it serves as a water seal separating units 1 and 2.Demonstration tests of the jet condenser (model 1:1) condensing function were carried out at the testing unit of the All-Union Research Institute for NPP Operation (VNIIAES), Moscow in Kashir, 11-22 September 1992. These experiments proved the jet condenser ability to ensure complete condensation of the steam produced. Experimental verification of the sealing function (model 1:1) was carried out at the testing unit of the VUEZ Tlmace. These experiments concerning the dynamics and overpressure in the free space above the pool were close to the conditions in the air trap during DBA. The jet condenser height was proved to be sufficient to ensure the sealing function. Design and experimental work has been implemented in close cooperation with Russian experts Mr. V.N. Bulynin from the VNIIAES, Moscow, and Mr. M.V. Kuznecov from the Scientific and Engineering Center for Nuclear and Radiological Safety, Moscow. (orig.)

  19. Sensitivity and uncertainty analysis for Ignalina NPP confinement in case of loss of coolant accident

    International Nuclear Information System (INIS)

    Urbonavicius, E.; Babilas, E.; Rimkevicius, S.

    2003-01-01

    At present the best-estimate approach in the safety analysis of nuclear power plants is widely used around the world. The application of such approach requires to estimate the uncertainty of the calculated results. Various methodologies are applied in order to determine the uncertainty with the required accuracy. One of them is the statistical methodology developed at GRS mbH in Germany and integrated into the SUSA tool, which was applied for the sensitivity and uncertainty analysis of the thermal-hydraulic parameters inside the confinement (Accident Localisation System) of Ignalina NPP with RBMK-1500 reactor in case of Maximum Design Basis Accident (break of 900 mm diameter pipe). Several parameters that could potentially influence the calculated results were selected for the analysis. A set of input data with different initial values of the selected parameters was generated. In order to receive the results with 95 % probability and 95 % accuracy, 100 runs were performed with COCOSYS code developed at GRS mbH. The calculated results were processed with SUSA tool. The performed analysis showed a rather low dispersion of the results and only in the initial period of the accident. Besides, the analysis showed that there is no threat to the building structures of Ignalina NPP confinement in case of the considered accident scenario. (author)

  20. Development of Highly Survivable Power and Communication System for NPP Instruments under Severe Accident

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Seung J.; Gu, Beom W.; Nguyen, Duy T.; Choi, Bo H.; Rim, Chun T. [KAIST, Daejeon (Korea, Republic of); Lee, So I. [KHNP CRI, Daejeon (Korea, Republic of)

    2014-10-15

    According to the detail report from the Fukushima nuclear accident, the failure of conventional instruments is mainly due to the following reasons. 1) Insufficient backup battery capacity after the station black out (SBO) 2) The malfunction or damage of instruments due to the extremely harsh ambient condition after the severe accident 3) The cut-off of power and communication cable due to the physical shocks of hydrogen explosion after the severe accident Since the current equipment qualification (EQ) for the NPP instruments is based on the design basis accident such as loss of coolant accident (LOCA), conventional instruments, which are examined under EQ condition, cannot guarantee their normal operation during the severe accident. A 7m-long-distance wireless power transfer and a radio frequency (RF) communication were introduced with conventional wired system to increase a redundancy. A heat isolation box and a harness are adopted to provide a protection from the expected physical shocks such as missiles and drastic increase of ambient temperature and pressure. A detail design principle of the highly survivable power and communication system, which has 4 sub-systems of a DCRS wireless power transfer, a Zigbee wireless communication, a GFRP harness, and a passive type router with a fly back regulator, has been presented in this paper. Each sub-system has been designed to have a robust operation characteristic regardless of the estimated physical shocks after the severe accident.

  1. Development of Highly Survivable Power and Communication System for NPP Instruments under Severe Accident

    International Nuclear Information System (INIS)

    Yoo, Seung J.; Gu, Beom W.; Nguyen, Duy T.; Choi, Bo H.; Rim, Chun T.; Lee, So I.

    2014-01-01

    According to the detail report from the Fukushima nuclear accident, the failure of conventional instruments is mainly due to the following reasons. 1) Insufficient backup battery capacity after the station black out (SBO) 2) The malfunction or damage of instruments due to the extremely harsh ambient condition after the severe accident 3) The cut-off of power and communication cable due to the physical shocks of hydrogen explosion after the severe accident Since the current equipment qualification (EQ) for the NPP instruments is based on the design basis accident such as loss of coolant accident (LOCA), conventional instruments, which are examined under EQ condition, cannot guarantee their normal operation during the severe accident. A 7m-long-distance wireless power transfer and a radio frequency (RF) communication were introduced with conventional wired system to increase a redundancy. A heat isolation box and a harness are adopted to provide a protection from the expected physical shocks such as missiles and drastic increase of ambient temperature and pressure. A detail design principle of the highly survivable power and communication system, which has 4 sub-systems of a DCRS wireless power transfer, a Zigbee wireless communication, a GFRP harness, and a passive type router with a fly back regulator, has been presented in this paper. Each sub-system has been designed to have a robust operation characteristic regardless of the estimated physical shocks after the severe accident

  2. Carrying out and planning measures for improvement of radiation situation in alienation zone after accident at Chernobyl NPP

    International Nuclear Information System (INIS)

    Kazakov, S.V.

    1994-01-01

    Technogenic radionuclides that were released into environment as the result of the Chernobyl accident joined the energy and mass transfer processes, which to a great extent are determined by the specificity of natural and climatic conditions of Ukrainian woodlands. The state of the spread of radioactive materials, and the data furnished by the Dosimetric Monitoring Board of the NPO 'Pripyat' over the zone territory are reported. After the primary radioactive contamination of the terrain, with meteorfactors superimposed on the physical and chemical conditions of radioactivity release and topographic factors, a new type of vegetation has developed, as well as a pattern of the economic exploitation of the territory. The process of radioactivity redistribution by water, wind and technogenic transport must be carefully investigated. The studies on radionuclide migration and the results are discussed. The estimation of dynamic capacitance in soil in the nearby zone of the ChNPP, the studies of hydrogeological condition in the 10 km zone, the analysis of groundwater condition, the studies on the wind-lift transport and fallout of radionuclides in 30 km zone and others are reported. Decontamination measures, one of the most large scale and labor-intensive operations in the elimination of the accident effects, and the burial of radioactive waste are described. The requirements for executing the project are summarized. (K.I.)

  3. Carrying out and planning measures for improvement of radiation situation in alienation zone after accident at Chernobyl NPP

    Energy Technology Data Exchange (ETDEWEB)

    Kazakov, S.V. [Nauchno-Proizvodstvennoe Ob``edinenie Pripyat`, Chernobyl` (Ukraine)

    1994-11-01

    Technogenic radionuclides that were released into environment as the result of the Chernobyl accident joined the energy and mass transfer processes, which to a great extent are determined by the specificity of natural and climatic conditions of Ukrainian woodlands. The state of the spread of radioactive materials, and the data furnished by the Dosimetric Monitoring Board of the NPO `Pripyat` over the zone territory are reported. After the primary radioactive contamination of the terrain, with meteorfactors superimposed on the physical and chemical conditions of radioactivity release and topographic factors, a new type of vegetation has developed, as well as a pattern of the economic exploitation of the territory. The process of radioactivity redistribution by water, wind and technogenic transport must be carefully investigated. The studies on radionuclide migration and the results are discussed. The estimation of dynamic capacitance in soil in the nearby zone of the ChNPP, the studies of hydrogeological condition in the 10 km zone, the analysis of groundwater condition, the studies on the wind-lift transport and fallout of radionuclides in 30 km zone and others are reported. Decontamination measures, one of the most large scale and labor-intensive operations in the elimination of the accident effects, and the burial of radioactive waste are described. The requirements for executing the project are summarized. (K.I.).

  4. The contents of Cs 137 in ichthyofauna of cooling pond after removing of ChNPP from operation

    International Nuclear Information System (INIS)

    Zarubin, O.L.

    2002-01-01

    As a result of removing of ChNPP from operation, temperature and hydrological parameters of its cooling pond considerably have changed, that, in turn, has affected the earlier usual characteristic by this ecosystem and Cs 137 content in some its components

  5. Safety assessment and improvement of Ignalina NPP against downcomer ruptures outside Accident Localisation System

    International Nuclear Information System (INIS)

    Rimkevicius, S.; Urbonavicius, E.

    2002-01-01

    Accident Localisation System (ALS) of Ignalina NPP is a pressure suppression type confinement, designed to prevent the release of contaminated steam-water mixture to the environment in case of Loss-of-Coolant Accident (LOCA). One of the peculiarities of Ignalina NPP with RBMK-1500 reactors is that not all of the reactor coolant circuit is enclosed within ALS. Some part of downcomers, that connect Drum Separator (DS) and suction header of main circulation pump is located outside ALS. In case of downcomer rupture in DS compartment the discharge is not confined, but flows to the environment through the safety panels installed in the ceiling of DS compartments. Numerous safety analyses were performed to assess the safety of Ignalina NPP against downcomer break outside ALS, and results were used for different applications in order to improve the safety of the plant. This paper presents the overview of the performed analyses, recommendations raised and safety improvements made to enhance the safety level of NPP. One of the applications is to present the recommendations for safety improvement if maximal allowable pressure limits are exceeded. The calculations results demonstrate that in the case of two downcomers rupture in drum separators compartment the maximum permissible pressure in the reactor hall could be exceeded. The knock-out panels from the reactor hall to the environment were recommended and installed for reactor hall overpressure protection. The evaluation of the drainage system efficiency from DS compartments was performed. In this case the especial attention was paid to analyse the water collection and drainage system behaviour in long term after postulated breaks. The analysis results showed that the modernization of the drainage system prevents the accumulation of the released water in the compartments even in the case of two downcomer pipes ruptures, and decreases the release of radioactive fission products (FP) to the environment.(author)

  6. Development of a dose assessment computer code for the NPP severe accident

    International Nuclear Information System (INIS)

    Cheong, Jae Hak

    1993-02-01

    A real-time emergency dose assessment computer code called KEDA (KAIST NPP Emergency Dose Assessment) has been developed for the NPP severe accident. A new mathematical model which can calculate cloud shine has been developed and implemented in the code. KEDA considers the specific Korean situations(complex topography, orientals' thyroid metabolism, continuous washout, etc.), and provides functions of dose-monitoring and automatic decision-making. To verify the code results, KEDA has been compared with an NRC officially certified code, RASCAL, for eight hypertical accident scenarios. Through the comparison, KEDA has been proved to provide reasonable results. Qualitative sensitivity analysis also the been performed for potentially important six input parameters, and the trends of the dose v.s. down-wind distance curve have been analyzed comparing with the physical phenomena occurred in the real atmosphere. The source term and meteorological conditions are turned out to be the most important input parameters. KEDA also has been applied to simulate Kori site and a hyperthetical accident with semi-real meteorological data has been simulated and analyzed

  7. External Reactor Vessel Cooling Evaluation for Severe Accident Mitigation in NPP Krsko

    International Nuclear Information System (INIS)

    Mihalina, M.; Spalj, S.; Glaser, B.

    2016-01-01

    The In-Vessel corium Retention (IVR) through the External Reactor Vessel Cooling (ERVC) is mean for maintaining the reactor vessel integrity during a severe accident, by cooling and retaining the molten material inside the reactor vessel. By doing this, significant portion of severe accident negative phenomena connected with reactor vessel failure could be avoided. In this paper, analysis of NPP Krsko applicability for IVR strategy was performed. It includes overview of performed plant related analysis with emphasis on wet cavity modification, plant's site specific walk downs, new applicable probabilistic and deterministic analysis, evaluation of new possibilities for ERVC strategy implementation regarding plant's post-Fukushima improvements and adequacy with plant's procedures for severe accident mitigation. Conclusion is that NPP Krsko could perform in-vessel core retention by applying external reactor vessel cooling strategy with reasonable confidence in success. Per probabilistic and deterministic analysis, time window for successful ERVC strategy performance for most dominating plant damage state scenarios is 2.5 hours, when onset of core damage is observed. This action should be performed early after transition to Severe Accident Management Guidance's (SAMG). For loss of all AC power scenario, containment flooding could be initiated before onset of core damage within related emergency procedure. To perform external reactor vessel cooling, reactor water storage tank gravity drain with addition of alternate water is needed to be injected into the containment. ERVC strategy will positively interfere with other severe accident strategies. There are no negative effects due to ERVC performance. New flooding level will not threaten equipment and instrumentation needed for long term SAMGs performance and eventually diluted containment sump borated water inventory will not cause return to criticality during eventual recirculation phase due to the

  8. Rupture of DN 500 - design basic accident at units 3 and 4 of Kozloduy NPP

    International Nuclear Information System (INIS)

    Uruchev, V.; Vassilev, P.; Ivanova, A.; Sartmadjiev, A.

    2005-01-01

    The original design of Kozloduy NPP Units 3 and 4 assumes as Design Basis Accident (DBA) the rupture of DN 32 mm primary pipeline, while an initial event of double-sided guillotine break of primary pipeline with maximal diameter is not considered. In the course of units modernization it have been demonstrated once and again that both the emergency core cooling systems and the localization systems can cope with larger and larger primary circuit leaks. After the installation of a Jet-Vortex Condenser (JVC) at Units 3 and 4 it was substantiated that, the integrity of the hermetic rooms is ensured even in case of double-sided guillotine break of a primary circuit pipeline with maximal diameter (DEGB). The technical justification of the jet-vortex condenser, elaborated by VNIAEC, contains calculations determining both the source term and the doses obtained outside the NPP site after LOCA DN 500. LOCA DN 500 is considered in these analyses as a beyond design basis accident and it is so included in the SAR and approved by the Nuclear Regulatory Agency (NRA). The thermo-hydraulic calculations performed later on show that the emergency core cooling systems can cope with this initial event at conservative assumptions. In order to classify this initiating event as a design basis accident it is necessary to demonstrate that the core cooling criteria are fulfilled and the internal and external doses outside the NPP site are within the permissible limits fixed for design basis accident by the Bulgarian regulatory body (NRA), when using conservative assumptions. For this purpose two consecutive studies were performed - evaluation of the DEGB probability and categorization of the initial event according to the contemporary regulations acting in Republic of Bulgaria. The presented report summarizes the results of the performed conservative analyses of double-sided guillotine break accident of main circulation line taking into account the probability of rupture of large diameter

  9. Transuranium elements intake during works connected with the Chernobyl' NPP accident effect elimination

    International Nuclear Information System (INIS)

    Popov, V.I.; Kukhta, B.A.; Kononykhina, N.N.

    1992-01-01

    The materials of studies realized in 1989, 1990, 1991 and dealing with internal irradiation control caused by intake of transuranium elements (TUE) for the Chernobyl' NPP personnel and persons engaged in the accident effect elimination are generalized. the leading part of TUE inhalation intake in formation of internal irradiation doses is revealed. Evaluation of TUE inhalation intake hazards is made according to the results of measuring TUE activity in urine samples for the personnel examined (271 persons). The results of surveillance shows the effect of organism internal irradiation connected with TUE intake through respiratory organs. 23 refs.; 1 tab

  10. Radioecological monitoring of the Black Sea basin following the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Kulebakina, L.G.; Polikarpov, G.G.

    1991-01-01

    A monitoring programme was drawn up to study the radioecological situation of the Black Sea basin following the Chernobyl NPP accident, with studies being carried out from May 1986 onwards to determine the levels of radioactive contamination in various parts of the Black Sea, the Sea of Azov and the Aegean Sea, including the estuaries of major rivers (Dnieper, Danube, Dniester and Don) and shelf areas of the Black Sea and the Sea of Azov. The work focused on long-lived radionuclides ( 90 Sr and 137 Cs), with the migration dynamics of these radionuclides in the aquatic environment, bed sediments and aquatic biota (including plants, molluscs, crustacea and fish) being studied. We compared the behaviour of radionuclides in the aquatic environment of the Dnieper reservoirs following the Chernobyl accident (our data) with the behaviour of radionuclides in lakes in the Urals following the Kyshtym accident (published data). As in the case of the lakes in the Urals, the Dnieper waters contain substantial concentrations of 90 Sr as a result of the Chernobyl accident, and 90 Sr therefore enters the Black Sea with the Dnieper waters. The paper compares the contribution of the Chernobyl accident to radioactive contamination of the Black Sea with that of global fallout. (author)

  11. RADIATION CONDITIONS IN KALUGA REGION 30 YEARS AFTER CHERNOBYL NPP ACCIDENT

    Directory of Open Access Journals (Sweden)

    A. G. Ashitko

    2016-01-01

    Full Text Available The article describes radiation conditions in the Kaluga region 30 years after the Chernobyl NPP accident. The Chernobyl NPP accident caused radioactive contamination of nine Kaluga region territories: Duminichsky, Zhizdrinsky, Kuibyshevsky, Kirovsky, Kozelsky, Ludinovsky, Meshchovsky, Ulyanovsky and Hvastovichsky districts. Radioactive fallout was the strongest in three southern districts: Zhizdrinsky, Ulyanovsky and Hvastovichsky, over there cesium-137 contamination density is from 1 to 15Ci/km. According to the Russian Federation Government Order in 2015 there are 300 settlements (S in the radioactive contamination zone, including 14 settlements with caesium-137 soil contamination density from 5 to 15 Ci/ km2 and 286 settlements with the contamination density ranging from 1 to 5 Ci/km2. In the first years after the Chernobyl NPP accident in Kaluga region territories, contaminated with caesium-137, there were introduced restrictive land usage, were carried out agrochemical activities (ploughing, mineral fertilizer dressing, there was toughened laboratory radiation control over the main doze-forming foodstuff. All these measures facilitated considerable decrease of caesium-137 content in local agricultural produce. Proceeding from the achieved result, in 2002 there took place the transition to more tough requirements SanPiN 2.3.2.1078-01. Analysis of investigated samples from Zhizdrinsky, Ulyanovsky and Hvastovichsky districts demonstrated that since 2005 meat samples didn’t exceed the standard values, same for milk samples since 2007. Till the present time, the use of wild-growing mushrooms, berries and wild animals meat involves radiation issues. It was demonstrated that average specific activity of caesium-137 in milk samples keeps decreasing year after year. Long after the Chernobyl NPP accident, the main products forming internal irradiation doses in population are the wild-growing mushrooms and berries. Population average annual

  12. Radiation safety of the helicopter air crow-liquidators of the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Davydov, B.I.; Ponomarenko, V.A.; Ushakov, I.B.

    1992-01-01

    Three aspects of the radiation safety of the helicopter air crew who took part in the elimination of the Chernobyl NPP accident after-effects during the period from the 27-th of April to July 1986 were considered: dosimetry, physical protection and radioprotector use. 1125 subjects from the flight and engineer personnel were irradiated: 6%-2.5 mSv and more, 32%-2.1-2.5 mSv and about 60% - up to 2.0 mSv. It is stated that the use of physical protection (local screening of a pilot seat and use of special antiradiation belts) makes irradiation doe 2-3 times less. In the intense conditions of flight activity the pilots preferred the radioprotector adrenaline to cystamin. Alimentary aids in the earlier and later periods after the accident influenced favourably somatic and psychic states. 16 refs.; 1 tab

  13. Use of nonstatistical techniques for pattern recognition to detect risk groups among liquidators of the Chernobyl NPP accident aftereffects

    International Nuclear Information System (INIS)

    Blinov, N.N.; Guslistyj, V.P.; Misyurev, A.V.; Novitskaya, N.N.; Snigireva, G.P.

    1993-01-01

    Attempt of using of the nonstatistical techniques for pattern recognition to detect the risk groups among liquidators of the Chernobyl NPP accident aftereffects was described. 14 hematologic, biochemical and biophysical blood serum parameters of the group of liquidators of the Chernobyl NPP accident impact as well as the group of donors free of any radiation dose (controlled group) were taken as the diagnostic parameters. Modification of the nonstatistical techniques for pattern recognition based on the assessment calculations were used. The patients were divided into risk group at the truth ∼ 80%

  14. Beyond designed functional margins in CANDU type NPP. Radioactive nuclei assessment in an LOCA type accident

    Directory of Open Access Journals (Sweden)

    Budu Andrei Razvan

    2015-01-01

    Full Text Available European Union's energy roadmap up to year 2050 states that in order to have an efficient and sustainable economy, with minimum or decreasing greenhouse gas emissions, along with use of renewable resources, each constituent state has the option for nuclear energy production as one desirable option. Every scenario considered for tackling climate change issues, along with security of supply positions the nuclear energy as a recommended option, an option that is highly competitive with respect to others. Nuclear energy, along with other renewable power sources are considered to be the main pillars in the energy sector for greenhouse gas emission mitigation at European level. European Union considers that nuclear energy must be treated as a highly recommended option since it can contribute to security of energy supply. Romania showed excellent track-records in operating in a safe and economically sound manner of Cernavoda NPP Units 1&2. Both Units are in top 10 worldwide in terms of capacity factor. Due to Romania's need to ensure the security of electricity supply, to meet the environmental targets and to move to low carbon generation technologies, Cernavoda Units 3&4 Project appears as a must. This Project was started in 2010 and it is expected to have the Units running by 2025. Cost effective and safety operation of a Nuclear Power Plant is made taking into consideration functional limits of its equipment. As common practice, every nuclear reactor type (technology used is tested according to the worse credible accident or equipment failure that can occur. For CANDU type reactor, this is a Loss of Cooling Accident (LOCA. In a LOCA type accident in a CANDU NPP, using RELAP/SCDAP code for fuel bundle damage assessment the radioactive nuclei are to be quantified. Recently, CANDU type NPP accidents are studied using the RELAP/SCDAP code only. The code formerly developed for PWR type reactors was adapted for the CANDU geometry and can assess the

  15. The radioactive contamination level in Croatia by means of radioactive rainwaters, caused by the accident in NPP 'Lenin'

    International Nuclear Information System (INIS)

    Barishicj, D.; Koshuticj, K.; Kvastek, K.; Lulicj, S.; Tuta, J.; Vertachnik, A.; Vrhovac, A.

    1987-01-01

    In this paper, the radioactive contamination level in Croatia by means of radioactive rainwaters, caused by the accident in NPP 'Lenin', has been described. The results represent the sum of measured and evaluated data, the map of the radioactive contamination in Croatia caused by radioactive rainwaters between April, 28 to May, 20 1986 has been constructed. (author) 3 tabs.; 5 figs

  16. Modelling of melting and solidification transport phenomena during hypothetical NPP severe accidents

    International Nuclear Information System (INIS)

    Sarler, B.

    1992-01-01

    A physical and mathematical framework to deal with the transport phenomena occuring during melting and solidification of the hypothetical NPP severe accidents is presented. It concentrates on the transient temperature, velocity, and species concentration distributions during such events. The framework is based on the Mixture Continuum Formulation of the components and phases, cast in the boundary-domain integral shape structured by the fundamental solution of the Laplace equation. The formulation could cope with various solid-liquid sub-systems through the inclusion of the specific closure relations. The deduced system of boundary-domain integral equations for conservation of mass, energy, momentum, and species could be solved by the boundary element discrete approximative method. (author) [sl

  17. Criterion for adoption of urgent decision on population protection measures in case of NPP accident

    International Nuclear Information System (INIS)

    Konstantinov, Yu.O.

    1985-01-01

    The main table of a criterion for making decision about population protection measures in case of NPP accident is reconsidered. In comparison with the previous data the table doesn't contain contact irradiation and food-stuff contamination with 90 Sr and 137 Cs because of their insignificance relatively to external irradiation as a result of inert radioactive gaseous and halogen release and internal irradiation by iodine radioisotopes. Defining more exactly the criterion one should pay more attention to the discussion of numerical values of internal irradiation dose of thyroid gland. The choice of hazard-levels giving the foundation for making decision concerning protection measures should be determined both by biological radiation risk and scale of hazard relative protection urgebcy the degree of accuracy of potential irradiation or contamination evaluation by possibilities of measures carried out in time, difficulties, unfavourable psychologic effect and risk for population health. The criterion should permit flexibility in decision making according to concrete conditions

  18. Peculiarities of forming and dissemination of radioactive contamination in Iput' river after the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Zhukova, O.M.; Shiryaeva, N.M.; Myshkina, N.K.; Shagalova, Eh.D.; Denisova, V.V.; Skurat, V.V.

    2001-01-01

    The process of radiation contamination forming of the river systems by Cs 137 and Sr 90 after the Chernobyl NPP accident was analyzed. It was shown that before 1990-1994 the river system contamination was formed by the initial falling out of radionuclides on the aquatic surface. After 2000 the contamination will form by means of entrance of radionuclides with surface flowing off from columbines. It was determined that the transboundary transport of radionuclides from the Russia territories influences essentially on contamination of Iput' river on the territory of Belarus. On the authors estimations such input was 30% for Cs 137 and 96% for Sr 90 in 1986, 86% for Cs 137 and 65% for Sr 90 at present

  19. NIRS external dose estimation system for Fukushima residents after the Fukushima Dai-ichi NPP accident

    Science.gov (United States)

    Akahane, Keiichi; Yonai, Shunsuke; Fukuda, Shigekazu; Miyahara, Nobuyuki; Yasuda, Hiroshi; Iwaoka, Kazuki; Matsumoto, Masaki; Fukumura, Akifumi; Akashi, Makoto

    2013-04-01

    The great east Japan earthquake and subsequent tsunamis caused Fukushima Dai-ichi Nuclear Power Plant (NPP) accident. National Institute of Radiological Sciences (NIRS) developed the external dose estimation system for Fukushima residents. The system is being used in the Fukushima health management survey. The doses can be obtained by superimposing the behavior data of the residents on the dose rate maps. For grasping the doses, 18 evacuation patterns of the residents were assumed by considering the actual evacuation information before using the survey data. The doses of the residents from the deliberate evacuation area were relatively higher than those from the area within 20 km radius. The estimated doses varied from around 1 to 6 mSv for the residents evacuated from the representative places in the deliberate evacuation area. The maximum dose in 18 evacuation patterns was estimated to be 19 mSv.

  20. Radiation doses estimation for hypothetical NPP Krsko accidents without and with PCFV using RASCAL software

    International Nuclear Information System (INIS)

    Vukovic, Josip; Konjarek, Damir; Grgic, Davor

    2014-01-01

    Calculation is done using Source Term to Dose module of RASCAL (Radiological Assessment System Consequence Analysis) software to estimate projected radiation doses from a radioactive plume to the environment. Utilizing this module, it is possible to do preliminary assessment of consequences to the environment in case of adverse reactor conditions or releases from other objects containing radioactive materials before the emergency situation has happened or in the early phase. RASCAL is simple, easy to use, fast-running tool able to provide initial estimate of radiological consequences of nuclear accidents. Upon entering rather limited amount of input parameters for the Krsko NPP, mostly key plant parameters, time dependent source term calculation is executed to determine radioactive inventory release rates for different plant conditions, release paths and availability of protective measures. These rates given for each radionuclide as a function of time are used as an input to atmospheric dispersion and transport model. Together with release rates, meteorological conditions dataset serve as input to determine the behavior of the radioactive releases that is plume in the atmosphere. So as an output, RASCAL produces a 'dispersion envelope' of radionuclide concentrations in the atmosphere. These concentrations of radionuclides in the atmosphere are further used for estimating the doses to the environment and the public downwind the release point. Throughout this paper, dose assessment is performed for two distances, close-in distance and distance out to 40 km from the source, for hypothetical NPP Krsko accidents without and with Passive Containment Filtered Vent (PCFV) system used. Obvious difference is related to released radioactivity of Iodine isotopes. Results of radioactive effluents deposition in the environment are displayed via various doze parameters, radionuclide concentrations and materials exposure rates in this particular case. (authors)

  1. Experience in reconstruction of psychological reality for persons engaged in elimination of the Chernobyl' NPP accident effects

    International Nuclear Information System (INIS)

    Salamatov, V.A.; Nyagu, A.T.

    1990-01-01

    The results of psichosemantic studies of adaptation process are discussed, i.e. the consciousness contents for personnel (120 persons) engaged in works connected with the Chernobyl' NPP accident effect elimination and reconstruction of the subjective image of the Chernobyl' NPP 30-km zone on this basis are described. The mental tension for the zone personnel is estimated. The results obtained testify to the presence of chronic stress and exceeding the level of psychoemotional tension. Increases in the uneasiness level and emotional instability for the personnel are revealed

  2. Chernobyl NPP accident consequences cleaning up participants in Ukraine -health status epidemiologic study main results

    International Nuclear Information System (INIS)

    Buzunov, V.; Omelyanetz, N.; Strapko, N.; Ledoschuck, B.; Krasnikova, L.; Kartushin, G.

    1996-01-01

    The Epidemiologic Studies System for Chernobyl NPP Accident consequences cleaning up participants (CNPP ACCP) health status was worked out and than improving in Ukraine after the CNPP Accident. The State Register of Ukraine both with several other Registers are the organizational, methodological and informational basis here. The ACCP health status worsening ,-was registered in dynamics through the post-accidental period i.e. the nervous system, digestive system, blood circulation system, respiratory system, bone-muscular system, endocrine and genitourinary systems chronic non-tumoral pathology both with mental disorders amount increase. In cohort study the differences of morbidity formation were fixed among emergency workers with different radiation exposure doses. The dependence of leukemia morbidity on presence in 30-km zone duration was noticed, it's access manifested 5 years after the participance in ACC. The ACCP disablement increase with main reason of general somatic diseases, and annual mortality growth are registered. But that doesn't exceed the mortality rate among population of working age in Ukraine

  3. Analysis of the first stage in the reactor accident development at the Chernobyl NPP fourth unit

    International Nuclear Information System (INIS)

    Adamov, E.O.; Vasilevskij, V.P.; Ionov, A.I.

    1988-01-01

    Results of analyzing possible development of the first stage of the accident at the Chernobyl NPP fourth unit from the moment of pressing the Az-5 push button are presented. Calculations were conducted using the TRIADA three-dimensional dynamic program both for conditions without pump switching off and with their switching off. Distribution of neutron field over the core volume was determined according to actual readings of in-core detectors immediately before turbogenerator switching off. It is shown that sufficient reconstruction of neutron field begins immediately after pressing the Az-5 push button. Prohibitive decrease of operative reactivity margin which was admitted by personnel in the accident resulted in the growth of neutron power in reactor lower part within 1.5 s, predominating over power decrease in the upper part. Thus, the average integral power grows achieving the maximum during 7.5 s, after which its sharp decrease begins. Conditions with switching off of 4 circulating pumps lead to intesive growth of power and reactor runaway, initiated in the lower part of the core, which safety rods have not managed to reach. Fuel element temperature at that exceeds fuel melting point in the most power-intensive regions. This causes extremely intensive process of steam generation and overheating, pressure growth in the circuit, short-time decrease of the rate of operating pumps, destruction of fuel channels and the whole reactor. Primary measures assuring RBMK ractor safety were formulated on the basis of conducted investigation

  4. Generalization of Nuclear Safety and Course of Accident Events Research in the Ignalina NPP; Branduolines saugos ir avariju eigos Ignalinos AE tyrimu apibendrinimas

    Energy Technology Data Exchange (ETDEWEB)

    Kaliatka, A; Uspuras, E [Lithuanian Energy Institute, Kaunas (Lithuania)

    2001-07-01

    The safety analysis shown that after implementation of SAR recommendations Ignalina NPP is adequately protected against accidents which required fast initiation of automatic protections. In case of accidents with long-term loss of core cooling additional operator actions are required. Accident management in case long-term core cooling are analyzed in this paper. (author)

  5. Severe accident management at the Loviisa NPP - Application of integrated ROAAM and PSA level 2

    International Nuclear Information System (INIS)

    Siltanen, S.; Routamo, T.; Tuomisto, H.; Lundstrom, P.

    2007-01-01

    The Risk Oriented Accident Analysis Methodology (ROAAM) was developed for assessment and management of rare, high consequence hazards. The purpose of most ROAAM applications has been to solve major, isolated severe accident issues related to early containment failure such as Mark-I Liner Attack and Direct Containment Heating. In addition to ROAAM in the issue resolution context, the so called Integrated ROAAM approach can be used to provide an overall frame of safety evaluation that allows determination of whether an adequate level of safety has been achieved for a plant. Integrated ROAAM approach brings together quantifications of probabilistic elements based on statistical inference and treatment of deterministic elements based on identification of dominant physics, for severe accident phenomenology, in a well defined and clearly structured way. Fortum, as an owner of the Loviisa NPP, used the Integrated ROAAM approach when developing and implementing a comprehensive severe accident management (SAM) strategy for the Loviisa NPP. The SAM strategy is based on unique features of this VVER-440 plant with ice condenser containment and it includes hardware modifications at the plant, substantial new I and C qualified for severe accident conditions, new SAM guidelines, a SAM Handbook, revision of emergency preparedness organization, and versatile training approaches. It could be argued that the resolution of individual severe accident issues is not sufficient for assessing the overall safety of a nuclear power plant, and thus the ROAAM (in an issue resolution context) is not performing the same function as a PSA study (level 2 included). Actually the Integrated ROAAM approach takes on even a more ambitious task than the PSA, since it determines how a balance can be achieved between accident prevention and mitigation of containment-threatening physical phenomena. Thus it provides a tool for implementing a sound diverse defence-in-depth strategy at a plant. Integrated

  6. Selection of optimal treatment procedures for non-standard radioactive waste arising from decommissioning of NPP after accident

    Energy Technology Data Exchange (ETDEWEB)

    Strážovec, Roman, E-mail: strazovec.roman@javys.sk [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia); JAVYS, a.s., Tomášikova 22, 821 02 Bratislava (Slovakia); Hrnčíř, Tomáš [DECOM, a.s., Sibírska 1, 917 01 Trnava (Slovakia); Lištjak, Martin [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia); VUJE, a.s., Okružná 5, 918 64 Trnava (Slovakia); Nečas, Vladimír [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia)

    2016-05-15

    The decommissioning of nuclear power plants is becoming a standard industrial activity where the optimization processes of partial activities are inevitable mainly for technical and economic reasons. In Slovakia, the decommissioning of A1 NPP is very specific case because A1 NPP is rare type of NPP (prototype) and furthermore its operation was affected by the accident. A large number of specific non-standard radioactive waste, such as long-time storage cases (hereinafter LSC), that is not usually present within the decommissioning projects of NPP with a regular termination of operation, represent one of the significant consequences of the accident and issues arisen from follow-up activities. The presented article describes the proposal of processing and conditioning of non-standard radioactive waste (such as LSC), together with description of methodology applied in the proposal for update of waste acceptance criteria for the processing and conditioning of radioactive waste (hereinafter RAW) within Bohunice Radioactive waste Treatment and Conditioning Centre (hereinafter RWTC). The results of performed detailed analysis are summarized into new waste acceptance criteria for technological lines keeping in mind safety principles and requirements for protection of operating personnel, the public and the environment.

  7. Chernobyl'-90. Reports of the 1. International conference on biological and radioecological aspects of the Chernobyl' NPP accident effects. V. 2, part 2. Radiation sanitary. Radiobiology. Agricultural radioecology

    International Nuclear Information System (INIS)

    Senin, E.V.

    1990-01-01

    The results of works done in 1988-1990 within the ecology part of the complex program dealing with elimination of the Chernobyl' NPP accident effect in regions of Ukraine, Belarus and Russia, as well as the data of foreign specialists on the Chernobyl' radioactive fallout effects in many countries are analyzed. Comparative analysis of the methods, means and results of acitivities dealing with accident effect eliminations on South Urals and at the Chernobyl' NPP is given

  8. Chernobyl'-90. Reports of the 1. International conference on biological and radioecological aspects of the Chernobyl' NPP accident effects. V. 2, part 1. Radiation sanitary. Radiobiology. Agricultural radioecology

    International Nuclear Information System (INIS)

    Senin, E.V.

    1990-01-01

    The results of works done in 1988-1990 within the ecology part of the complex program dealing with elimination of the Chernobyl' NPP accident effects in regions of Ukraine, Belarus and Russia, as well as the data of foreign specialists on the Chernobyl' radioactive fallout effects in many countries are analyzed. Comparative analysis of the methods, means and results of activities dealing with accident effect eliminations on South Urals and at the Chernobyl' NPP is given

  9. Calculation of an accident with delayed scram at NPP Greifswald using the coupled code DYN3D/ATHLET

    Energy Technology Data Exchange (ETDEWEB)

    Kliem, S

    1998-10-01

    Complex computer codes modeling the whole reactor system including 3D neutron kinetics in combination with advanced thermohydraulic plant models become more and more important for the safety assessment of nuclear reactors. Transients or experiments with both neutron kinetic and thermalhydraulic data are needed for the validation of such coupled codes like DYN3D/ATHLET. First of all measured results from nuclear power plant (NPP) transients should be used, because the experimental thermalhydraulic facilities do not offer the possibility to model space-dependent neutron kinetic effects and research reactors with reliably measured 3D neutron kinetic data do not allow to study thermalhydraulic feedback effects. In this paper, an accident with delayed scram which occurred in 1989 at the NPP Greifswald is analyzed. Calculations of this accident were carried out with the goal to validate the coupled code DYN3D/ATHLET. (orig.)

  10. Dynamics of Sr-90 content in environmental objects of Ukrainian-Byelorussian Poles'e after the Chernobyl' NPP accident

    International Nuclear Information System (INIS)

    Likhtarev, I.A.; Kajro, I.A.; Shandala, N.K.; Los', I.N.; Repin, V.S.; Gul'ko, G.M.; Chepurnoj, N.I.; Berkovskij, V.B.; Tsygankov, N.Ya.; Pozhivalova, S.B.

    1990-01-01

    Ecological, dosemetric and radiation-sanitary aspects of the problem of Sr-90 contamination of environmental objects and food in Ukrainian-Byelorussian Poles'e in three-year period after the Chernobyl' NPP accident are discussed. Analysis of the materials collected shows that efficient equivalent radiation doses from Sr-90 being intaken into the region of Urkainian-Byelorussian Poles'e after the Chernobyl' NPP accident expected to be gained during 70 years of critical population group life are not exceed 1 mSv; this value is by the factor of 10-100 smaller than the dose values connected with radioactive cesium. The problem of environment contamination with Sr-90 transforms from hot radiation-sanitary situation into more quiet radioecological one

  11. Calculation of an accident with delayed scram at NPP Greifswald using the coupled code DYN3D/ATHLET

    International Nuclear Information System (INIS)

    Kliem, S.

    1998-01-01

    Complex computer codes modeling the whole reactor system including 3D neutron kinetics in combination with advanced thermohydraulic plant models become more and more important for the safety assessment of nuclear reactors. Transients or experiments with both neutron kinetic and thermalhydraulic data are needed for the validation of such coupled codes like DYN3D/ATHLET. First of all measured results from nuclear power plant (NPP) transients should be used, because the experimental thermalhydraulic facilities do not offer the possibility to model space-dependent neutron kinetic effects and research reactors with reliably measured 3D neutron kinetic data do not allow to study thermalhydraulic feedback effects. In this paper, an accident with delayed scram which occurred in 1989 at the NPP Greifswald is analyzed. Calculations of this accident were carried out with the goal to validate the coupled code DYN3D/ATHLET. (orig.)

  12. Observation of radioactive aerosol particle sizes in 30-km zone of the ChNPP in 1986-1987 years

    International Nuclear Information System (INIS)

    Skitovich, V.I.; Budyka, A.K.; Ogorodnikov, B.I.

    1989-01-01

    Investigation into disperse composition of radioactive aerosols was conducted in the ChNPP spaces, over ruins of 4 block, on job site and separate points of the 30-km zone by multilayer filters from ultrathin fibers. In probes taken from the job site radioactive isotopes were grouped on the particles with more than 2,5 μcm diameter. Particle sizes in the room were less than near terrestrial layer of atmosphere on job site. It is shown that the aerosol sizes containing alpha active nuclides are idential with gamma radiating isotopes of refractory elements. 4 refs., 1 fig., 2 tabs

  13. Assessment of forms finding of Chernobyl radionuclides in bottom sediments of cooling pond of the ChNPP

    Directory of Open Access Journals (Sweden)

    V. P. Protsak

    2014-09-01

    Full Text Available Assessment of forms finding of radionuclides 90Sr, 137Cs, 238Pu, 239,240Pu, 241Am and dispersal composition of fuel particles in bottom sediments of cooling pond of the ChNPP is carried out. According to the results of re-search in the year of 2012 more than 98 % of radionuclides in bottom sediments were in non-exchange (ex-changeable state, while in the composition of the fuel particles can be contained about 70% 90Sr and more than 80 % 241Am and of the plutonium isotopes. Obtained results indicate the selective leaching of radionuclides from the matrix of fuel particles.

  14. Assessment of effectiveness of anti-seismic measures in stabilization project of ChNPP shelter object

    International Nuclear Information System (INIS)

    Kondrat'ev, S.N.; Kritskij, V.B.; Ryzhov, D.I.; Shugajlo, A.P.; Shugajlo, Al.P.; Prabkhakara, M.

    2004-01-01

    The major factors, which may lead to the collapse of the Shelter object (SO) civil structures, are extreme natural phenomena and among them earthquake. In order to raise the resistance of the SO civil structure to seismic and other significant loads and to reduce the risk of their collapse ChNPP requested KSK Consortium to develop the SO Detailed Design for stabilization. At the present work the results of assessment of anti-seismic measures are given based on results of a technical review of the Detailed Design

  15. Safety requirement of the nuclear power plants, after TMI-2 accident and their possible implementation on Bushehr NPP

    International Nuclear Information System (INIS)

    Mirhabibi, N.; Tochai, M.T.M.; Ashrafi, A.; Farnoudi, E.

    1985-01-01

    Based on the lessons learned from the TMI-2 accident and other research and developments, many improvements have been required for the design, manufacturing and operation of nuclear power plants in recent years. These requirements have already been implemented to the plants in operation and considered as new safety requirements for new plants. In the present paper these requirements and their possible implementation on Bushehr NPP are discussed. (Author)

  16. Modelling of Cs-137 availability in soils subjected to contamination after the accident at the Chernobyl NPP

    International Nuclear Information System (INIS)

    Fesenko, S.V.; Spiridonov, S.I.; Sanzharova, N.I.; Aleksakhin, R.M.

    1996-01-01

    Results of the application of the model describing behaviour of the radionuclide in meadow ecosystems for the analysis of the factors governing of the radionuclide availability in soils are presented. The estimation of characteristics of fuel particles in near zone of the Chernobyl NPP is given. It is shown that in the first period after the accident the main factors determining Cs-137 availability in soil are property of soil and mat as well as fallout characteristics. Refs. 6, figs. 5

  17. Lessons learned from the decommissioning process affected by an accident during operation. The case of A1 NPP in Slovakia

    International Nuclear Information System (INIS)

    Daniska, Vladimir; Timulak, Jan; Pekar, Anton; Niznansky, Vojtech; Konecny, Ladislav

    2007-01-01

    Decommissioning of NPP's with standard shutdown is currently well known process. The A1 NPP in Slovakia was shutdown in 1977 after the accident in the core which caused the damage of the fuel and contamination of systems. Long period from 1977 to 2008 was needed to manage issues resulting from affecting the systems and structures of A1 NPP and the environment by the accident. Management of the damaged spent fuel, decontamination of the primary circuit and other processes generated large amounts of alpha bearing waste, mostly liquid, having sludge phases with specific physical-chemical and radiological properties. Up to 1994, the approach for eliminating the consequences of the accident was based on safety priorities. The systematic approach, which includes also the rehabilitation of the affected environment, was implemented in the period 1994-2008. The process includes also establishing of the decommissioning infrastructure, legislative and funding system with the aim to implement the standard decommissioning procedures after 2008. However, the specific aspects, especially the level and radio-nuclide composition of contamination of systems and structures will remain. For final decommissioning 2008-2033, the approach was selected which foresees four licensed phases. This approach enables proper planning and performing of individual decommissioning phases. (authors)

  18. A model for severe accidents management of WWER 440 at Kozloduy NPP

    International Nuclear Information System (INIS)

    Genovski, I.; Bonev, B.; Velev, V.; Grigorov, A.; Filipov, L.

    2006-01-01

    In order to reduce the residual risk associated with hypothetical severe nuclear accidents, systems and components for filtered containment venting and H2 reduction were implemented in the Kozloduy NPP units 3 and 4. The system technologies developed have to fulfill the following main tasks: 1) Creating a new pressure barrier system to confine the activity inventory by maintaining a slight containment sub-atmospheric pressure thereby preventing any relevant unfiltered activity releases. 2) Retaining a great extend of the airborne activity in the liquid phase of the venturi scrubber unit and return these activity back into the containment. 3) Controlling the containment atmosphere H2 gas mixture to prevent fast deflagration that may jeopardize the containment integrity. To meet above mentioned requirement a system was developed, consisting of a venturi scrubber unit which comprises a high speed long venturi section, a metal fibre filter section and molecular sieve. The system is operated by a turbo blower unit supplied with electrical power from the unaffected unit. The system keeps a slight sub-atmospheric pressure (approx. 5 - 10 mbar) in the containment with the purpose to minimize the uncontrolled radioactive release from the containment to the environment. The final analysis showed that the containment performance in combination with above mentioned countermeasures could be increased significantly and the impact to the environment is minimized

  19. Vertical transfer of radionuclides in soils of different genesis after Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Bakarykava, Zh.; Shagalova, E.; Zhukova, O.

    2003-01-01

    In this paper a vertical transfer of radionuclides in soils of different genesis after Chernobyl NPP accident was studied. Analysis of obtained data revealed that the main content of cesium-137 is located in 0-5 cm layer of turf-podsolic, sandy-loam and loamy soil provided the lack of their humidification, and of light un-bogged (automorphous) soil as well. Cesium-137 penetration into light un-bogged soils with that sings of surplus humidification is approximately 10 cm deep. Strontium-90 as global birth so Chernobyl origin migrates more rapidly than cesium-137 because of less strong bond with soil absorbing complex. Cesium-137 migration coefficients amounted (0.03-0.46)·10 -7 cm 2 /s for a slow component, and for the fast one (0.39-0.67)·10 -7 cm 2 /s. Strontium-90 migration coefficients in the experimented sites, amounted (0.07-0.58)·10 -7 cm 2 /s for a slow component, and for the fast one (0.64-1.28)·10 -7 cm 2 /s. (authors)

  20. Modelling of melting and solidification transport phenomena during hypothetical NPP severe accidents

    Energy Technology Data Exchange (ETDEWEB)

    Sarler, B [Inst. Jozef Stefan, Ljubljana (Slovenia)

    1992-07-01

    A physical and mathematical framework to deal with the transport phenomena occuring during melting and solidification of the hypothetical NPP severe accidents is presented. It concentrates on the transient temperature, velocity, and species concentration distributions during such events. The framework is based on the Mixture Continuum Formulation of the components and phases, cast in the boundary-domain integral shape structured by the fundamental solution of the Laplace equation. The formulation could cope with various solid-liquid sub-systems through the inclusion of the specific closure relations. The deduced system of boundary-domain integral equations for conservation of mass, energy, momentum, and species could be solved by the boundary element discrete approximative method. (author) [Slovenian] Predstavljeno je fizikalno in matematicno ogrodje za obravnavo prenosnih pojavov taljenja in strjevanja med hipoteticnimi tezkimi nezgodami v jedrskih elektrarnah. Osredotoceno je na popis neustaljene porazdelitve temperatur, hitrosti in koncentracij sestavin med taksnimi dogodki. Ogrodje temelji na formulaciji kontinuuma mesanice komponent in faz, v obliki robno obmocnih integralskih enacb, ki so sestavljena na podlagi fundamentalne resitve Laplace-ove enacbe. Formulacija lahko popisuje stevilne trdno-tekoce pod-sisteme na podlagi specificnih sklopitvenih relacij. Izpeljan sistem robno-obmocnih integralskih enacb za popis ohranitve mase, energije, gibalne kolicine in sestavin lahko resimo na podlagi diskretne aproksimativne metode robnih elementov. (author)

  1. Measurement of long-lived radionuclides in surface soil around F1NPP accident site by Accelerator Mass Spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Miyake, Yasuto; Matsuzaki, Hiroyuki [Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo (Japan); Sasa, Kimikazu; Takahashi, Tsutomu [AMS Group, Tandem Accelerator Complex, Research Facility Center for Science and Technology, University of Tsukuba, Tsukuba, Ibaraki 305-8577 (Japan)

    2015-10-15

    In March 2011, vast amounts of radionuclides were released into the environment due to the Fukushima Daiichi Nuclear Power Plant (F1NPP) accident. However, very little work has been done concerning accident-derived long-lived nuclides such as {sup 129}I (T{sub 1/2} = 1.57 × 10{sup 7} year) and {sup 36}Cl (T{sub 1/2} = 3.01 × 10{sup 5} year). {sup 129}I and {sup 131}I are both produced by {sup 235}U fission in nuclear reactors. Being isotopes of iodine, these nuclides are expected to behave similarly in the environment. This makes {sup 129}I useful for retrospective reconstruction of {sup 131}I distribution during the initial stages of the accident. On the other hand, {sup 36}Cl is generated during reactor operation via neutron capture reaction of {sup 35}Cl, an impurity in the coolant or reactor component. Resulting {sup 36}Cl/Cl ratio within the reactor is thus much higher compared to that in environment. Similar to {sup 129}I, {sup 36}Cl is expected to have leaked out during the accident and it is important to evaluate its effects. In this study, {sup 129}I concentrations were determined in several surface soil samples collected around F1NPP. Average {sup 129}I/{sup 131}I ratio was estimated to be 26.1 ± 5.8 as of March 11, 2011, consistent with calculations using ORIGEN2 code and other published data. {sup 36}Cl/Cl ratios in some of the soil samples were likewise measured and ranged from 1.1 × 10{sup −12} to 2.6 × 10{sup −11}. These are higher compared to ratios measured around F1NPP before the accident. A positive correlation between {sup 36}Cl and {sup 129}I concentration was observed.

  2. Measurement of long-lived radionuclides in surface soil around F1NPP accident site by Accelerator Mass Spectrometry

    Science.gov (United States)

    Miyake, Yasuto; Matsuzaki, Hiroyuki; Sasa, Kimikazu; Takahashi, Tsutomu

    2015-10-01

    In March 2011, vast amounts of radionuclides were released into the environment due to the Fukushima Daiichi Nuclear Power Plant (F1NPP) accident. However, very little work has been done concerning accident-derived long-lived nuclides such as 129I (T1/2 = 1.57 × 107 year) and 36Cl (T1/2 = 3.01 × 105 year). 129I and 131I are both produced by 235U fission in nuclear reactors. Being isotopes of iodine, these nuclides are expected to behave similarly in the environment. This makes 129I useful for retrospective reconstruction of 131I distribution during the initial stages of the accident. On the other hand, 36Cl is generated during reactor operation via neutron capture reaction of 35Cl, an impurity in the coolant or reactor component. Resulting 36Cl/Cl ratio within the reactor is thus much higher compared to that in environment. Similar to 129I, 36Cl is expected to have leaked out during the accident and it is important to evaluate its effects. In this study, 129I concentrations were determined in several surface soil samples collected around F1NPP. Average 129I/131I ratio was estimated to be 26.1 ± 5.8 as of March 11, 2011, consistent with calculations using ORIGEN2 code and other published data. 36Cl/Cl ratios in some of the soil samples were likewise measured and ranged from 1.1 × 10-12 to 2.6 × 10-11. These are higher compared to ratios measured around F1NPP before the accident. A positive correlation between 36Cl and 129I concentration was observed.

  3. Transfer of fallout radionuclides by Fukushima NPP accident from tree crown to forest ecosystem

    Science.gov (United States)

    Onda, Y.; Kato, H.; Wakahara, T.; Kawamori, A.; Tsujimura, M.

    2011-12-01

    Radioactive contamination has been detected in Fukushima and the neighboring prefectures due to the nuclear accident at Fukushima Daiichi Nuclear Power Plant (NPP) following the earthquake and tsunami on 11 March 2011. The total deposition of radioactive materials in fallout samples for 137Cs ranged from 0.02to >10 M Bq/m2 for Cs-137. Experimental catchments have been established in Yamakiya district, Kawamata Town, Fukushima prefecture, located about 35 km from Fukushima power plant, and designated as the evacuated zone. Approximate Cs-137 fallout in this area is 200-600k Bq/m2. We established 3 forest sites: broad leaf tree forest and two Japanese cedar forest plantation (young and mature). In each site we installed towers of 8-12 meters. Using these towers, we sampled tree leaves, and measure Cs-137 and Cs-134 in the laboratory, and also we have measure Cs-137, Cs-134 content at various height in each forest using a portable High Purity Germanium (HPGe) detector (Ortech; Detective-EX). We also measured the throughfall, stem flow and litter fall inside of the forest. In each site, we establish the 20 m x 20 m plot to monitor the changes of fallout radionuclides through time with the portable HPGe detector. The monitoring is now ongoing but we found significant amount of Cs-134 and Cs-137 has been trapped by cedar forest plantations especially young trees, but not so much in broad leaf trees. The trapped Cs-137 and Cs-134 is then washed by rainfall and found into throughfall. Therefore, in forest ecosystems, the fallout has been still ongoing, and and effective remediation method in forested area (especially cedar plantation) can be removing the trees.

  4. Developing Off-site Emergency Preparedness and Response Model (OEPRM) for Severe Accident of NPP in a Densely Populated Country Using System Dynamics Approach

    Energy Technology Data Exchange (ETDEWEB)

    Hossena, Muhammed Mufazzal; Kang, Kyoung Ho; Song, Jin Ho [KAERI, Deajeon (Korea, Republic of)

    2016-05-15

    The main objectives of this study are to find the influencing factors of systems and sub-systems of OEPRM, to find the interdependency among the influencing factors, and to develop a conceptual qualitative OEPRM for densely populated NPP country in case of SA using system dynamics (SD). NPP accidents are classified as nuclear accidents and incidents depending on the severity. Severe accident (SA) is certain low probability accident that are beyond design basis accident which may arise due to multiple failures of safety systems leading to significant core degradation and jeopardize the integrity of many or all of the barriers to the release of radioactive material. The weakness to the off-site emergency response in the time of Fukushima accident was observed. So, it is crucial to develop an off-site emergency preparedness and responses model (OEPRM) for radiological emergency in densely populated country from the Fukushima emergency response lesson. In this study, an OEPRM is developed for densely populated NPP country to mitigate radiological effects in case of SA using SD approach. Besides, this study focuses the weakness of emergency response in Fukushima accident and proposed solution approach. The development of OEPRM in case of SA of NPP is very complex because of the involvement of various organization and it requires highly specialized agencies and technical experts. Moreover, if the country is agriculture based, it will make completely sophisticated.

  5. Developing Off-site Emergency Preparedness and Response Model (OEPRM) for Severe Accident of NPP in a Densely Populated Country Using System Dynamics Approach

    International Nuclear Information System (INIS)

    Hossena, Muhammed Mufazzal; Kang, Kyoung Ho; Song, Jin Ho

    2016-01-01

    The main objectives of this study are to find the influencing factors of systems and sub-systems of OEPRM, to find the interdependency among the influencing factors, and to develop a conceptual qualitative OEPRM for densely populated NPP country in case of SA using system dynamics (SD). NPP accidents are classified as nuclear accidents and incidents depending on the severity. Severe accident (SA) is certain low probability accident that are beyond design basis accident which may arise due to multiple failures of safety systems leading to significant core degradation and jeopardize the integrity of many or all of the barriers to the release of radioactive material. The weakness to the off-site emergency response in the time of Fukushima accident was observed. So, it is crucial to develop an off-site emergency preparedness and responses model (OEPRM) for radiological emergency in densely populated country from the Fukushima emergency response lesson. In this study, an OEPRM is developed for densely populated NPP country to mitigate radiological effects in case of SA using SD approach. Besides, this study focuses the weakness of emergency response in Fukushima accident and proposed solution approach. The development of OEPRM in case of SA of NPP is very complex because of the involvement of various organization and it requires highly specialized agencies and technical experts. Moreover, if the country is agriculture based, it will make completely sophisticated

  6. Conceptual Design of Portable Filtered Air Suction Systems For Prevention of Released Radioactive Gas under Severe Accidents of NPP

    Energy Technology Data Exchange (ETDEWEB)

    Gu, Beom W.; Choi, Su Y.; Yim, Man S.; Rim, Chun T. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2014-05-15

    It becomes evident that severe accidents may occur by unexpected disasters such as tsunami, heavy flood, or terror. Once radioactive material is released from NPP through severe accidents, there are no ways to prevent the released radioactive gas spreading in the air. As a remedy for this problem, the idea on the portable filtered air suction system (PoFASS) for the prevention of released radioactive gas under severe accidents was proposed. In this paper, the conceptual design of a PoFASS focusing on the number of robot fingers and robot arm rods are proposed. In order to design a flexible robot suction nozzle, mathematical models for the gaps which represent the lifted heights of extensible covers for given convex shapes of pipes and for the covered areas are developed. In addition, the system requirements for the design of the robot arms of PoFASS are proposed, which determine the accessible range of leakage points of released radioactive gas. In this paper, the conceptual designs of the flexible robot suction nozzle and robot arm have been conducted. As a result, the minimum number of robot fingers and robot arm rods are defined to be four and three, respectively. For further works, extensible cover designs on the flexible robot suction nozzle and the application of the PoFASS to the inside of NPP should be studied because the radioactive gas may be released from connection pipes between the containment building and auxiliary buildings.

  7. Study of lymphocyte sensitization to protein S-100 in the patients with cerebrovascular diseases, suffered due to Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Khomenko, V.Yi.

    2004-01-01

    Among the persons with cerebrovascular diseases, suffered due to Chernobyl NPP accident two groups of patients were revealed: with DNA coloration coefficients in response to protein S-100 stimulation below and above 1. Patients with DNA coloration coefficients <1 were older, they had statistically significant lower monocytes and T-activated lymphocytes absolute counts as well as increased content of cholesterol-2 and circulating immune complexes. Charges found there suggested possible existence of different pathways of immune response to antigenic stimulation by S-100 protein

  8. Psychosomatic and somatopsychic aspects of the development of mental disturbances in liquidators of the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Rumyantseva, G.M.

    2003-01-01

    For mathematic-statistical analysis of factors, probably influencing the formation of mental disorders in participants of the liquidation of Chernobyl NPP accident the database containing 165 variables was made. By factor and dispersion analysis variables, influencing mental disorders formation rate, and share of influence and correlation dependencies were discriminated and calculated. The mental disturbances, emerging after an ecological radiation catastrophe, form not only due to direct and indirect action of physical factors, but as a consequence of inclusion of somatopsychic and psychosomatic mechanisms, associated directly with catastrophe effect

  9. Accidents during shutdown conditions for NPP with WWER-1000/428

    International Nuclear Information System (INIS)

    Antropov, H.A.

    1996-01-01

    This paper considers the effect of such internal initiating events upon safety of the NPP with WWER-1000/428 as boron dilution and loss of residual heat removal at the reduced coolant inventory in the primary circuit. 2 refs

  10. Human reliability analysis for steam generator feed-and-bleed accident in Bushehr NPP-1

    Energy Technology Data Exchange (ETDEWEB)

    Jafarian, Reza [Valiasr University of Rafsanjan, Rafsanjan, 28 (Iran, Islamic Republic of); Sepanloo, Kamran [Atomic Energy Organization of Iran (AEOI), external link End of North Karegar Av., Tehran 14155-1339 (Iran, Islamic Republic of)

    2006-07-01

    According to the incident/accident reports, unsuccessful implementation of steam generator feed-and-bleed procedure is one of the most important events in nuclear power plants operation which greatly contributes to the level of risk of the plants. Generally, the loss of all feed water pumps flow (as one of the precursors) results in failure to maintain adequate cooling of the reactor core unless the operating crew initiate and follow the feed-and-bleed procedure correctly and timely. In this paper, firstly, a Human Reliability Analysis (HRA) event tree is presented delineating the major human activities and errors in the implementation of the steam generator (SG) feed-and-bleed procedure following the loss of (both normal and emergency) water feed to four SGs of Bushehr Nuclear Power Plant Unit 1 (BNPP-1). Secondly, the graphical method of task analysis as a part of HRA is used as a means of delineating correct and incorrect human actions. To be used in the probabilistic risk assessment (PRA), the outputs of the HRA event trees are fed into the system event trees, functional event trees or system fault trees. As a part of a probabilistic risk assessment of BNPP-1 and to assess the reliability of control room operators, a human reliability analysis model is applied based on the THERP (Technique for Human Error Rate Prediction) technique. The THERP method is used in the form of event trees named as the probability tree diagrams. In this research the Human Reliability Analysis event tree is constructed based on the background information and assumptions made and on a similar NPP task analysis. It is done so because the BNPP-1 is not an operational nuclear power plant. Thirdly, based on NUREG/CR-1278 Handbook, a computer program has been developed in Visual Basic language and used to illustrate the major human activities and determination of error rates of operators in the course of the implementation of the steam generator feed-and-bleed procedure. Finally, total

  11. Human reliability analysis for steam generator feed-and-bleed accident in Bushehr NPP-1

    International Nuclear Information System (INIS)

    Jafarian, Reza; Sepanloo, Kamran

    2006-01-01

    According to the incident/accident reports, unsuccessful implementation of steam generator feed-and-bleed procedure is one of the most important events in nuclear power plants operation which greatly contributes to the level of risk of the plants. Generally, the loss of all feed water pumps flow (as one of the precursors) results in failure to maintain adequate cooling of the reactor core unless the operating crew initiate and follow the feed-and-bleed procedure correctly and timely. In this paper, firstly, a Human Reliability Analysis (HRA) event tree is presented delineating the major human activities and errors in the implementation of the steam generator (SG) feed-and-bleed procedure following the loss of (both normal and emergency) water feed to four SGs of Bushehr Nuclear Power Plant Unit 1 (BNPP-1). Secondly, the graphical method of task analysis as a part of HRA is used as a means of delineating correct and incorrect human actions. To be used in the probabilistic risk assessment (PRA), the outputs of the HRA event trees are fed into the system event trees, functional event trees or system fault trees. As a part of a probabilistic risk assessment of BNPP-1 and to assess the reliability of control room operators, a human reliability analysis model is applied based on the THERP (Technique for Human Error Rate Prediction) technique. The THERP method is used in the form of event trees named as the probability tree diagrams. In this research the Human Reliability Analysis event tree is constructed based on the background information and assumptions made and on a similar NPP task analysis. It is done so because the BNPP-1 is not an operational nuclear power plant. Thirdly, based on NUREG/CR-1278 Handbook, a computer program has been developed in Visual Basic language and used to illustrate the major human activities and determination of error rates of operators in the course of the implementation of the steam generator feed-and-bleed procedure. Finally, total

  12. Human Reliability Analysis for steam generator feed-and-bleed accident in Bushehr NPP-1

    International Nuclear Information System (INIS)

    Jafarian, R.; Sepanloo, K.

    2005-01-01

    According to the incident/accident reports, unsuccessful implementation of steam generator feed-and-bleed procedure is one of the most important events in nuclear power plants operation which greatly contributes to the level of risk of the plants. Generally, the loss of all feed water pumps flow (as one of the precursors) results in failure to maintain adequate cooling of the reactor core unless the operating crew initiate and follow the feed-and-bleed procedure correctly and timely. In this paper, firstly, a Human Reliability Analysis (HRA) event tree is presented delineating the major human activities and errors in the implementation of the steam generator (SG) feed-and-bleed procedure following the loss of (both normal and emergency) water feed to four SGs of Bushehr Nuclear Power Plant unit1 (BNPP-1). Secondly, the graphical method of task analysis as a part of HRA is used as a means of delineating correct and incorrect human actions. To be used in the probabilistic risk assessment (PRA), the outputs of the HRA event trees are fed into the system event trees, functional event trees or system fault trees. As a part of a probabilistic risk assessment of BNPP-1 and to assess the reliability of control room operators, a human reliability analysis model is applied based on the THERP (Technique for Human Error Rate Prediction) technique. The THERP method is used in the form of event trees named as the probability tree diagrams. In this research the Human Reliability Analysis event tree is constructed based on the background information and assumptions made and on a similar NPP task analysis. It is done so because the BNPP-1 is not an operational nuclear power plant. Thirdly, based on NUREG/CR-1278 Handbook, a computer program has been developed in Visual Basic language and used to illustrate the major human activities and determination of error rates of operators in the course of the implementation of the steam generator feed-and-bleed procedure. Finally, total

  13. Application of the ALARA principle to minimize the collective dose in NPP accident management within the containment

    International Nuclear Information System (INIS)

    Bogorad, V.; Slepchenko, O.; Kyrylenko, Y.

    2016-01-01

    The paper focuses on application of the ALARA principle to minimize the collective doses (both for NPP personnel and the public) related to admission of personnel to the containment for accident management activities and depending on operation of ventilation systems. Results from assessment of radiation consequences are applied to a small - break LOCA with failure of LPIS at VVER - 1000 reactors. The public doses are evaluated using up - to - date RODOS, MACCS and HotSpot software for assessment of radiation consequences. The personnel doses are evaluated with MicroShield and InterRAS codes. The time function and optimal value of the collective dose are defined. The developed approach can be applied for minimization of the collective dose for optimization of accident management strategies at NPPs

  14. A program package connected with a communication network for accident statistics of NPP, TPP, HPP and the power lines

    International Nuclear Information System (INIS)

    Madjarova, A.

    1993-01-01

    The package is designed for registration and analysis of accidents according to users' needs. A possibility is also provided for easy data transfer and access to data on implemented decisions. Special programmes are developed for NPP, TPP, HPP, electricity supply branch, regional distribution management and the National Electric Company. The system is open for local network connection and file exchange between the workstations. The dialogue features are user-friendly. The emergency situations are classified according to the requirements of the enacted in Bulgaria 'Regulations for Investigation, Classification and Recording of Accidents in Electric and Thermal Stations and Networks, 1993'. The unified data input provides a possibility for insertion of additional texts (remarks), correcting and updating. Data security tools are also envisaged. (author)

  15. Status of antiviral immunity in patients with non-alcoholic liver fatty disease, who were Chornobyl NPP accident liquidators

    Directory of Open Access Journals (Sweden)

    A.A. Chumak

    2017-11-01

    Full Text Available 34 men were examined, who after participating in the liquidation of the Chornobyl NPP accident developed non-alcoholic fatty liver disease. The state of antiviral defense was evaluated by the levels of immunoglobulin (Ig G and IgM antibodies in the blood serum. In most patients with non-alcoholic steatohepatitis, who were Chornobyl NPP accident liquidators, antibodies of the IgG, but not IgM class to the persistent mixed infection with herpes simplex virus types 1 and 2, cytomegaly and Epstein-Barr were found. A positive correlation was established between the antibody titers to the herpes simplex virus types 1 and 2 (anti-HSV-1/2 IgG and cytomegalovirus (anti-CMV IgG (rs = 0.383, p = 0.040, as well as between the antibodies titers to the nuclear antigen of Epstein-Barr virus (anti-EBV NA IgG and antibodies to core antigen of Epstein-Barr (anti-EBV VCA IgG (rs = 0.584, p = 0.002 in patients with persistent mixed infection of these herpesviruses.

  16. A quantitative assessment method for the NPP operators' diagnosis of accidents

    International Nuclear Information System (INIS)

    Kim, M. C.; Seong, P. H.

    2003-01-01

    In this research, we developed a quantitative model for the operators' diagnosis of the accident situation when an accident occurs in a nuclear power plant. After identifying the occurrence probabilities of accidents, the unavailabilities of various information sources, and the causal relationship between accidents and information sources, Bayesian network is used for the analysis of the change in the occurrence probabilities of accidents as the operators receive the information related to the status of the plant. The developed method is applied to a simple example case and it turned out that the developed method is a systematic quantitative analysis method which can cope with complex relationship between the accidents and information sources and various variables such accident occurrence probabilities and unavailabilities of various information sources

  17. Real-time management (RTM) by cloud computing system dynamics (CCSD) for risk analysis of Fukushima nuclear power plant (NPP) accident

    International Nuclear Information System (INIS)

    Cho, Hyo Sung; Woo, Tae Ho; The Cyber Univ. of Korea, Seoul

    2017-01-01

    The earthquake and tsunami induced accident of nuclear power plant (NPP) in Fukushima disaster is investigated by the real-time management (RTM) method. This non-linear logic of the safety management is applied to enhance the methodological confidence in the NPP reliability. The case study of the earthquake is modeled for the fast reaction characteristics of the RTM. The system dynamics (SD) modeling simulations and cloud computing are applied for the RTM method where the real time simulation has the fast and effective communication for the accident remediation and prevention. Current tablet computing system can improve the safety standard of the NPP. Finally, the procedure of the cloud computing system dynamics (CCSD) modeling is constructed.

  18. Real-time management (RTM) by cloud computing system dynamics (CCSD) for risk analysis of Fukushima nuclear power plant (NPP) accident

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Hyo Sung [Yonsei Univ., Wonju Gangwon-do (Korea, Republic of). Dept. of Radiation Convergence Engineering; Woo, Tae Ho [Yonsei Univ., Wonju Gangwon-do (Korea, Republic of). Dept. of Radiation Convergence Engineering; The Cyber Univ. of Korea, Seoul (Korea, Republic of). Dept. of Mechanical and Control Engineering

    2017-03-15

    The earthquake and tsunami induced accident of nuclear power plant (NPP) in Fukushima disaster is investigated by the real-time management (RTM) method. This non-linear logic of the safety management is applied to enhance the methodological confidence in the NPP reliability. The case study of the earthquake is modeled for the fast reaction characteristics of the RTM. The system dynamics (SD) modeling simulations and cloud computing are applied for the RTM method where the real time simulation has the fast and effective communication for the accident remediation and prevention. Current tablet computing system can improve the safety standard of the NPP. Finally, the procedure of the cloud computing system dynamics (CCSD) modeling is constructed.

  19. Basic parameters of the Cs 137 contents in some components of trophic chains of Kanevskoe reservoir after accident on Chernobyl NPP

    International Nuclear Information System (INIS)

    Zarubin, O.L.; Pan'kov, I.V.; Volkova, E.N.; Belyaev, V.V.

    2002-01-01

    The analysis of parameters of radioactive pollution of water and biota of Kanevskoe reservoir has shown, what even in 15 years after accident on Chernobyl NPP, the distribution of Cs 137 on the basic components by this ecosystem has not achieved an equilibrium condition

  20. Accident beyond the design basis management with the coolant loss at the NPP with WWER

    International Nuclear Information System (INIS)

    Skalozubov, V.I.; Klyuchnikov, A.A.; Kolykhanov, V.N.

    2010-01-01

    The analysis of status and experience of development on modelling and accident beyond the design basis management, including the severe accidents, at the nuclear power plants is carried out. The methodical providing of manuals on the accident beyond the design basis management with the coolant loss on the basis of simulated critical system configurations providing the necessary safety function performance on reactor unit is proposed. The project of symptom-oriented manuals on accident beyond the design basis management with the coolant loss on the serial power unit with WWER-1000 on the basis of developed methodical providing and well known results of deepened safety analysis is presented.

  1. Accident at TEPCo’s Fukushima-Daiichi NPP - LL for Operator/Industry

    International Nuclear Information System (INIS)

    Omoto, Akira

    2011-01-01

    Lessons Learned - Emergency Management: • Loss of communication tool and plant information (SPDS) at NPP; • Dissemination of information: - Damage to social infrastructure by earthquake hampered dissemination of information to local government and residents: - Lack of Information sharing with local residents on dispersion of FP (SPEEDI) and risk of radiation with neighboring countries on release of slightly-contaminated water: - “Data but not information”; •Who is in charge?: - Ambiguity in delineation of responsibility; - Recognized role by Joint (Government and TEPCO) ERC and local resources center 20—30km away from NPP; • Offsite center: function was lost by loss of electricity and radiation; • Effective channeling of emergency supports: - Systematize domestic/foreign helping hands for logistics/experts

  2. Cytogenetic examination of persons working in the area of radiation accident at the Fukushima-1 NPP in Japan

    Directory of Open Access Journals (Sweden)

    Nugis V.Yu.

    2014-12-01

    Full Text Available Purpose: biological dose indication of employees of the Ministry of Emergency Situations of Russia who took part in the work in Japan in connection with the accident at Fukushima-1 NPP and several journalists covering this event. Material and methods. The analysis of chromosomal aberrations in peripheral blood lymphocyte cultures of 46 people was performed. Results. The frequency of chromosomal damages exceeded background levels in only 3 people, and aberration character testified irradiation in previous situations. Conclusion. The significant overexposure of these workers during they stayed in Japan is absent, however it is necessary to perform a preliminary analysis of chromosome aberrations if you intend to exercise of biological dose indication after returning of people from areas of potential exposure.

  3. The influence of biotic and abiotic factors on (137)Cs accumulation in higher fungi after the accident at Chernobyl NPP.

    Science.gov (United States)

    Zarubina, N

    2016-09-01

    Levels of soil contamination with (137)Cs, the belonging of fungi to a certain ecological group, the localization depth of the main part of mycelium in soil are the primary factors influencing the value of (137)Cs specific activity in higher fungi after the accident at Chernobyl NPP. It has been found that the value of (137)Cs specific activity in fungi of one species could vary by more than 10 times during a vegetation period. A correlation between the changes of (137)Cs content in fungi during the vegetation period and the amount of precipitates during various periods preceding the collection of samples has not been determined. An assumption has been proposed stating dependence between peculiarities of mycelium growth during the vegetation period and the changes of (137)Cs specific activity in fungi. Copyright © 2015 Elsevier Ltd. All rights reserved.

  4. Development of a dose assessment computer code for the NPP severe accident at intermediate level - Korean case

    International Nuclear Information System (INIS)

    Cheong, J.H.; Lee, K.J.; Cho, H.Y.; Lim, J.H.

    1993-01-01

    A real-time dose assessment computer code named RADCON (RADiological CONsequence analysis) has been developed. An approximation method describing the distribution of radionuclides in a puff was proposed and implemented in the code. This method is expected to reduce the time required to calculate the cloud shine (external dose from radioactive plumes). RADCON can simulate an NPP emergency situation by considering complex topography and continuous washout phenomena and provide a function of effective emergency planning. To verify the code results, RADCON has been compared with RASCAL, which was developed for the U.S. NRC by ORNL, for eight hypothetical accident scenarios. Sensitivity analysis was also performed for the important input parameters. (2 tabs., 3 figs.)

  5. Main stages of 137Cs accumulation by mushrooms in exclusion zone after ChNPP accident

    International Nuclear Information System (INIS)

    Shatrova, N.E.

    2001-01-01

    In Chernobyl exclusion zone area the 137 Cs accumulation by mushrooms (macromycetes) of different types is investigated. The main factor influencing radiocaesium content value in mushrooms-symbiotrophes, is the depth of location in ground of the main part of mycelium of each kind. For macromycetes, whole mycelium is located in the soil in 0 - 5 or 5 - 10 cm layers, 137 Cs accumulation occurs in two stages. The first stage is characterised by gradual increase (from year to year) of 137 Cs concentration in fruit bodies of mushrooms; the second stage - abrupt decrease of radionuclide contents. The maximum 137 Cs amount in macromycetes of different kinds are marked in 1996-1998 years. In the year of 2000 on 2 zone test sites the change of the ratio of 137 Cs contents in mushrooms-symbiotrophes with different depth of mycelium's localization for first time was marked

  6. Radiation conditions in the Oryol region territory impacted by radioactive contamination caused by the Chernobyl NPP accident

    Directory of Open Access Journals (Sweden)

    G. L. Zakharchenko

    2016-01-01

    Full Text Available Research objective is retrospective analysis of radiation conditions in the Oryol region during 1986- 2015 and assessment of efficacy of the carried out sanitary and preventive activities for population protection against radiation contamination caused by the Chernobyl NPP accident.Article materials were own memoirs of events participants, analysis of federal state statistic surveillance forms 3-DOZ across the Oryol region, f-35 “Data on patients with malignant neoplasms, f-12 “Report on MPI activities”. Risk assessment of oncological diseases occurrence is carried out on the basis of AAED for 1986- 2014 using the method of population exposure risk assessment due to long uniform man-made irradiation in small doses. Results of medical and sociological research of genetic, environmental, professional and lifestyle factors were obtained using the method of cancer patients’ anonymous survey. Data on "risk" factors were obtained from 467 patients hospitalized at the Budgetary Health Care Institution of the Oryol region “Oryol oncology clinic”; a specially developed questionnaire with 60 questions was filled out.The article employs the method of retrospective analysis of laboratory and tool research and calculation of dose loads on the Oryol region population, executed throughout the whole period after the accident.This article provides results of the carried out laboratory research of foodstuff, environment objects describing the radiation conditions in the Oryol region since the first days after the Chernobyl NPP accident in 1986 till 2015.We presented a number of activities aimed at liquidation of man-caused radiation accident consequences which were developed and executed by the experts of the Oryol region sanitary and epidemiology service in 1986-2015. On the basis of the above-stated one may draw the conclusions listed below. Due to interdepartmental interaction and active work of executive authorities in the Oryol region, the

  7. Dose limit for emergency workers. Application of Fukushima-Daiichi NPP accident and problems for the future

    International Nuclear Information System (INIS)

    Sugai, Kenji

    2012-01-01

    Described are details of management for workers' personal exposure dose, of problems raised and of their solutions taken under various complicated conditions of Fukushima Daiichi Nuclear Power Plant (NPP) Accident (Mar. 2011). As the entrance/exit (en/ex) for the NPP site with regular control were impossible due to the hydrogen explosion which expanded the control area to 20 km distance from the site, Japan Football Village (J-Village) localizing at the border and Important Anti-seismic Building in the site were defined to be the bases of en/ex and of their control, respectively. Flooded 5,000 alarm pocket dosimeters (APD) by tsunami were not usable and only 320 APD remained available. At the quite early stage of working at the site, one representative worker in a group had only one APD. Management of internal exposure was also difficult essentially because the power source of the whole body counter was unavailable. At an early emergent stage alone, workers with higher dose than the limit (100 mSv for emergency) were observed, but >90% of workers were exposed to <50 mSv (the limit for the radiation worker). Six male Tokyo Electric Power Company (TEPCO) personnel were exposed to 250 mSv (specially defined dose limit) or more with the maximum 678.80 mSv, in whom the internal exposure due to radioiodine largely attributed. They were examined for their health by the expert doctors in National Institute of Radiological Sciences, were found free of abnormality and were to be followed up thereafter. Out of 19 female TEPCO personnel, two had exceeded the dose limit 5 mSv/3 mo and other 2, the annual limit 1 mSv. They received the examination by the industrial doctor, were found free of abnormality, but were decided not to work at the site. Recently, about 5,000 APD have been purchased for personal usage and dose management is conducted by bar-coding of individual workers, and internal exposure is managed with 11 whole body counters by once a month measurement in J

  8. Experience of rehabilitation of territories contaminated during Chernobyl NPP accident in Ukraine

    International Nuclear Information System (INIS)

    Zeleznyak, M.

    2003-01-01

    Full text: Significant part of Ukraine territory, including agricultural lands, was subjected to radioactive contamination as a result of ChNPP emergency. In the initial period of emergency the main attention was given to averting of radioactivity propagation and irradiation of the population. Irradiation of the thyroid gland for a large contingent of human, especially children, became the hardest consequence of the emergency. The main problem of minimization of the emergency consequences consisted in a complete rehabilitation of contaminated areas. Resettlement of residents of contaminated territories was appeared effective only in cases, when expected effective dose of irradiation could exceed levels of interference. In the remote terms after emergency this measure was accompanied by an unjustifiable psychological stress for the population and considerable material expenses. The adopted organizational and technological countermeasures allowed to reduce significantly a dose of irradiation for thyroid gland, especially for population of Kiev urban agglomeration - about 4 mln. persons. The efficiency of countermeasures was insufficient due to hiding of the emergency firstly, and then because of the late announcement of a danger, after iodine attack already. The program of reconstruction of irradiation doses for different groups of population was realized, i.e. the liquidators of emergency, children, inhabitants of the contaminated zone. The sharp increase of thyroid gland cancer frequency and other types of pathologies was observed. The network of specialized medical entities for consulting and clinical examination of victims was created. Iodine radionuclides entered into human organism per os with foodstuffs predominantly. Prevention of milk contamination and its processing was the most effective measures of population protection. The big part of the territory of Ukraine was subjected to radioactive contamination with fallout predominantly the area of Ukrainian

  9. NPP post-accident monitoring system based on unmanned aircraft vehicle:concept, design principles

    International Nuclear Information System (INIS)

    Sachenko, A.A.; Kochan, V.V.; Kharchenko, V.S.; Yanovskij, M.Eh.; Yastrebenetskij, M.A.; Fesenko, G.V.

    2016-01-01

    The paper presents a concept of designing the post-accident system for monitoring the equipment and territory of nuclear power plant after a severe accident based on unmanned aircraft vehicle (UAVs). Wired power and communications networks are found out as the most vulnerable ones during the accident monitoring, and informativity, reliability and veracity are recognized as system basic parameters. It is proposed to equip measurement and control modules with backup wireless communication channels and deploy the repeaters network based on UAVs to ensure the informativity. Modules possess the backup power battery, and repeaters appear in the appropriate places after the accident to provide the survivability. Moreover, an optimization of UAVs' location is proposed according to the minimum energy consumption criterion. To ensure the veracity, it is expected to design the noise-immune protocol for message exchange and archiving and self-diagnostics of all system components

  10. Study on spraying water soluble resin to reduce pollution for Fukushima daiichi NPP accident

    International Nuclear Information System (INIS)

    Zhang Qiong; Guo Ruiping; Zhang Chunming; Han Fujuan; Hua Jie; Zhang Jiankui

    2012-01-01

    After Fukushima nuclear accident, Tokyo electric power company used the method of spraying water soluble resin synthesis at the scene of the accident, to restrain and control the spread of the radioactive dust, by forming consolidation layer in pollution area surface. This paper briefly introduced the accident, motivation of spraying water soluble resin, spraying range and implementation process. According to the relevant report on Fukushima nuclear accident, the effect of spraying water soluble resin for reducing pollution was analyzed. The mechanism of reducing pollution for water soluble resin and the application prospect were discussed. Spraying water soluble resin for fixing radioactive dust has reasonable reducing pollution effect. It is worth to use as reference and study in China. (authors)

  11. Study on the offsite emergency planning against an accident in NPP

    International Nuclear Information System (INIS)

    Khang, Byung Oui; Lee, Goan Yup; Wu, Jong Sup; Kim, Joo Hag; Lee, Jong Tai; Lee, Jae Eun; Ahn, Chul Hyun; Ahn, Jae Hyun; Park, Dae Woo

    2009-12-01

    - Proposing effective local nuclear emergency preparedness system against nuclear/radiological accidents. - Proposing improved preparation/operation scheme on emergency response facilities, installations and equipment. - Establishing protection scheme on the general public against nuclear/radiological accidents. - Proposing effective preparation/operation scheme on local radioactive monitoring system. - Establishing effective training/drill scheme on the nuclear emergency preparedness. - Proposing effective technical administrative system of the local government (Busan metropolitan city)

  12. Response of neutrophils in peripheral blood of participants in the liquidation of Chernobyl NPP accident consequences to an additional radiation exposure in vitro

    International Nuclear Information System (INIS)

    Timoshevskij, A.A.; Grebenyuk, A.N.; Kalinina, N.A.

    2001-01-01

    Specific effect of radiation exposure in vitro on morphobiochemical characteristics of leukocytes in peripheral blood of the participants in the liquidation of Chernobyl NPP consequences are investigated. Samples of peripheral blood taken from 49 participants in the liquidation of Chernobyl NPP consequences were irradiated in vitro in doses 0.25, 0.50 and 1.0 Gy. Cytochemical analysis of neutrophils was used for estimating the contents of lipids and cationic proteins, and also the activity of alkaline phosphatase and myeloperoxidase. The irradiation of samples of peripheral blood taken from the participants in the liquidation of Chernobyl NPP consequences has the same effects on functional and metabolic somatic status but with no history of exposure to the complex of radiation accident factors [ru

  13. The rehabilitation strategies in agriculture in the long term after the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Fesenko, S.V.

    2002-01-01

    The experience gained in the aftermath of the severe radiation accidents shows that in the case of large-scaled radionuclide contamination the limitation of internal radiation doses to people by means of restoration of agricultural lands is more realistic than reduction of levels of external irradiation. Therefore, the problems connected with the optimal restoration strategies of agricultural land subjected to radioactive contamination after the Chernobyl accident are of crucial importance. The justification of the approach for the estimation of the effectiveness of countermeasure strategies in the long term after the Chernobyl accident, based on the classification of farms by contamination density and risk of the exceeding of radiological standards, restricting the use of agricultural products, is presented. For each class of the farms the ranking of rehabilitation options and the time periods when their application would be of importance are given. Comparative analysis of the rehabilitation strategies, which are different in their effectiveness and cost, is provided. (author)

  14. Assessing the consequences in a nuclear accident scenario at Cernavoda NPP

    International Nuclear Information System (INIS)

    Margeanu, Sorin; Angelescu, Tatiana

    2004-01-01

    Having in view a possible nuclear incident, considerable planning is necessary to reduce at manageable levels the types of decisions leading to effective responses concerning the public protection. One of the most important parts of an emergency response plan is the computerized system which allows to predict the radiological impact of the accident and to provide information in a manageable and effective form for evaluating alternative countermeasure strategies in the various stages of the accident. In this paper the PC-COSYMA results for early containment failure of a CANDU reactor are presented. The deterministic health effects arising in nuclear accident situation are also presented. As source term we have used the core inventory obtained with ORIGEN computer code. The essential input parameters for PC-COSYMA computer code are also done. (authors)

  15. The NEA benchmark study of the accident at the Fukushima Daiichi NPP

    International Nuclear Information System (INIS)

    Koganeya, Toshiyuki

    2015-01-01

    In November 2012, the NEA, under the aegis of the Committee on the Safety of Nuclear Installations (CSNI), initiated a joint research project called the Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF). Objectives of this project include supporting Fukushima Daiichi decommissioning by analysing accident progression and the current status of the reactors, such as fuel debris distribution in the reactor pressure vessels and primary containment vessels in preparation for fuel debris removal. A second objective of the project is to improve SA (severe analysis) codes through comparisons with data from the Fukushima reactors. So as to enhance communication between analysts and those involved in decommissioning activities, participants in the project have been discussing the remaining uncertainties in relation to understanding the accident and the data needs from the viewpoint of the analysts. Since the accident sequences at the Fukushima Daiichi site include a wide range of phenomena, a phased approach is being applied in this benchmark exercise while awaiting more detailed information on debris examination and other factors. This article provides an overview of the project (scope, input data and boundary conditions, participants (from eight countries), analytical approach - common case and best estimate case) as well as an outline of the project's next phase (BASF phase 2) that begins in June 2015

  16. The information psychological periodization of the Chernoby'l NPP accident information in the mass media

    International Nuclear Information System (INIS)

    Bugrim, V.V.

    1992-01-01

    The activity of mass media reflecting the Chernobyl' accident in 1986-1991 has been surveilled. The information (radio, television, press conferences) given at this period was devided into seven classification periods. The analysis of the information and its assessment in each period was demonstrated. 6 refs

  17. Application of GIS in prediction and assessment system of off-site accident consequence for NPP

    International Nuclear Information System (INIS)

    Wang Xingyu; Shi Zhongqi

    2002-01-01

    The assessment and prediction software system of off-site accident consequence for Guangdong Nuclear Power Plant (GNARD2.0) is a GIS-based software system. The spatial analysis of radioactive materials and doses with geographic information is available in this system. The structure and functions of the GNARD system and the method of applying ArcView GIS are presented

  18. Audit calculations of accidents analysis for second unit of Ignalina NPP with ATHLET code

    International Nuclear Information System (INIS)

    Adomavicius, A.; Belousov, A.; Ognerubov, V.

    2004-01-01

    Background of thermo hydraulic processes audit calculations in the frame of RSR-2 project is presented. Assumptions for the design based accident - RBMK-1500 group distributor header break analysis and modeling are presented. Audit calculations by ATHLET code and evaluation of results were provided. (author)

  19. Chernobyl'-90. Reports of the 1. International conference on biological and radioecological aspects of the Chernobyl' NPP accident effects. V. 1, part 1. Radioecology of plants. Radioecology of terrestrial animals. Radioecology of hydrobionts

    International Nuclear Information System (INIS)

    Senin, E.V.

    1990-01-01

    The results of works done in 1988-1990 within the ecology part of the complex program dealing with elimination of the Chernobyl NPP accident effects in regions of Ukraine, Belarus and Rissua, as well as the data of foreign specialists on the Chernobyl radioactive fallout effects in many countries are analyzed. Comparative analysis of the methods, means and results of activities dealing with accident effect eliminations on South Urals and at the Chernobyl NPP is given

  20. Chernobyl'-90. Reports of the 1. International conference on biological and radioecological aspects of the Chernobyl' NPP accident effects. V. 1, part 2. Radioecology of plants. Radioecology of terrestrial animals. Radioecology of hydrobionts

    International Nuclear Information System (INIS)

    Senin, E.V.

    1990-01-01

    The results of works done in 1988-1990 within the ecology part of the complex program dealing with elimination of the Chernobyl' NPP accident effects in regions of Urkaine, Belarus and Russia, as well as the data of foreign specialists on the Chernobyl' radioactive fallout effects in many countries are analyzed. Comparative analysis of the methods, means and results of activities dealing with accident effect eliminations on South Urals and at the Chernobyl' NPP is given

  1. Chernobyl'-88. Reports of the 1. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 7. Part 1. Localization of accident consequences at the 4th power unit, operating site of the Chernobyl NPP and adjoining territories

    International Nuclear Information System (INIS)

    Ignatenko, E.I.

    1989-01-01

    The next data on the accident consequence elimination are presented: temperature monitoring results, gamma radiation exposure dose rates, neutron and gamma fields, aerosol disperse composition. The information system for scientific researches FINISH and automatic subsystems for radiation control and the Ukrytie object diagnostics are described. Decontamination of the Chernobyl' NPP territory, equipment and rooms is described too

  2. Chernobyl'-88. Reports of the 1. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 7. Part 2. Localization of accident consequences at the 4th power unit, operating site of the Chernobyl' NPP and adjoining territories

    International Nuclear Information System (INIS)

    Ignatenko, E.I.

    1989-01-01

    The next data on the accident consequence elimination are presented: temperature monitoring results, gamma radiation exposure dose rates, neutron and gamma fields, aerosol disperse composition. The information system for scientific researches FINISH and automatic subsystems for radiation control and the Ukrytie object diagnostics are described. Decontamination of the Chernobyl' NPP territory, equipment and rooms is described too

  3. Clinical and encephalographic study of the dynamics of asthenic syndrome in persons involved in the liquidation of Chernobyl NPP accident consequences

    International Nuclear Information System (INIS)

    Sukharskaya, Marta; Tsurkanu, Lukretsiya; Kirka, Luchiya; Boshnyaga, Emiliya; Godorozha, Mikhai; Toma, Viktoriya; Postovan, Alla; Andronik, Zinaida; Mornyala, Elena; Popovich, Lyudmila

    2011-01-01

    The article is devoted to the analysis of dynamics of asthenic syndrome and electro encephalography indicators during the 25 years after the Chernobyl NPP accident. Four stages of syndrome development were segregated. The clear correlation between the course of mental disorder and electro encephalography indicators was discovered. This made it possible to determine the intensity and weight of pathological processes and conduct the effective timely treatment. (authors)

  4. Use of MAAP code for identification of key plant vulnerabilities for the beyond design accidents and their mitigation at NPP Krsko

    International Nuclear Information System (INIS)

    Krajnc, B.

    1995-01-01

    NPP Krsko performed according to GL 88-20, Supplement 1-4 and RUJV requirement the Individual Plant Examination analyses. For the required deterministic analyses the MAAP 3.0B code was used. It was proven that such severe accident analysis can be used for evaluation of the overall level of safety improvement that can be gained with the different modifications and alternate design. In this paper one such important outcomes from these analyses will be presented. (author)

  5. Modeling of Spray System Operation under Hydrogen and Steam Emissions in NPP Containment during Severe Accident

    Directory of Open Access Journals (Sweden)

    Vadim E. Seleznev

    2011-01-01

    Full Text Available The paper describes one of the variants of mathematical models of a fluid dynamics process inside the containment, which occurs in the conditions of operation of spray systems in severe accidents at nuclear power plant. The source of emergency emissions in this case is the leak of the coolant or rupture at full cross-section of the main circulating pipeline in a reactor building. Leak or rupture characteristics define the localization and the temporal law of functioning of a source of emergency emission (or accrued operating of warmed up hydrogen and steam in the containment. Operation of this source at the course of analyzed accident models should be described by the assignment of the relevant Dirichlet boundary conditions. Functioning of the passive autocatalytic recombiners of hydrogen is described in the form of the complex Newton boundary conditions.

  6. NPP accident scenario. Which emergency measures are planned in Switzerland?; Szenario KKW-Unfall. Welche Notfallschutzmassnahmen sind in der Schweiz geplant?

    Energy Technology Data Exchange (ETDEWEB)

    Flury, Christoph [Bundesamt fuer Bevoelkerungsschutz (BABS), Bern (Switzerland). Eidgenoessisches Departement fuer Verteidigung Bevoelkerungsschutz und Sport (VBS)

    2016-07-01

    As a consequence of the reactor accident in Fukushima the Swiss government has ordered an extensive analysis of emergency planning in case of a NPP accident Switzerland. A special working group has analyzed the possible improvements of Swiss emergency planning based on the experiences in Japan. Under the special direction of the Bundesamt fuer Bevoelkerungsschutz (BABS) the agreed improvements were integrated into the emergency concept. The reference scenarios have been re-assessed and the zone concept adapted. The emergency measures include shelter-type rooms (basement or window-less rooms), the preventive distribution of iodine pills, measures concerning agriculture, aquatic systems, preventive evacuation, traffic regulations, and delayed evacuation.

  7. Japan Catastrophic Earthquake and Tsunami in Fukushima Daiichi NPP; Is it Beyond Design Basis Accident or a Design Deficiency and Operator Unawareness?

    International Nuclear Information System (INIS)

    Gaafar, M.A.; Refeat, R.M.; EL-Kady, A.A.

    2012-01-01

    On March 11, 2011 a catastrophic earthquake and tsunami struck the north east coast of Japan. This catastrophe damaged fully or partially the six units of the Fukushima Daiichi Nuclear Power Plant.Questions were raised following the aftermath, whether it is beyond design basis accident caused by severe natural event or a failure by the Japanese authorities to plan to deal with such accident. There are many indications that the Utility of Fukushima Daiichi NPP, Tokyo Electric Power Company (TEPCO), did not pay enough attention to numerous facts about the incompatibility of the site and several design defects in the plant units. In fact there are three other NPP sites nearby Fukushima Daiichi Plant (about 30 to 60 Km far from Fukushima Daiichi NPP), with different site characteristics, which survived the same catastrophic earthquake and tsunami, but they were automatically turned into a safe shutdown state. These plants sites are Fukushima Daini Plant (4 units), Onagawa Plant (3 units) and Tokai Daini (II) Plant (one unit). In this paper, the aftermath Fukushima Daiichi plant integrity is pointed out. Some facts about the site and design concerns which could have implications on the accident are discussed. The response of Japan Authority is outlined and some remarks about their actions are underlined. The impacts of this disaster on the Nuclear Power Program worldwide are also discussed.

  8. Overview of Mobile Equipment Used in Case of Beyond Design Basis Accident at NPP Krsko

    International Nuclear Information System (INIS)

    Lukacevic, H.; Kopinc, D.; Ivanjko, M.

    2016-01-01

    Terrorist attack in USA in the September 11, 2001 and accident at the Fukushima - Daiichi Nuclear Power Station in the March 11, 2011 highlight the importance of mitigating strategies in responding to Beyond Design Basis Accident (BDBA), while ensuring cooling of reactor core, containment and spent fuel pool. Nuclear Power Plant Krsko (NEK) has acquired additional mobile equipment and made necessary modifications on existing systems for the connection of this equipment (fast couplers). Usage of mobile equipment is not only limited to design basis accident (DBA), but, also to prevent and mitigate the consequences in case of BDBA, when other plant systems are not available. NEK also decided to take steps for upgrade of safety measures and prepared Safety Upgrade Program (SUP), which is consistent with the nuclear industry response to the Fukushima accident and is implementing main projects and modifications related to SUP. NEK mobile equipment is not required to operate under normal reactor plant operation except for periodic surveillance testing and is incorporated into the normal training process. Equipment is dislocated from the reactor building and most of the equipment is located in the new building, able to withstand extreme natural events, including earthquakes and tornadoes. The usage of all mobile equipment is prescribed as an additional option in NEK operating procedures in following cases and enables following options: filling various tanks, filling the steam generators, filling the containment, additional compressed air source, spent fuel pool refilling and spraying, alternative power supply. This document provides an overview of NEK mobile equipment, which consists of various mobile fire protection pumps, air compressors, protective equipment, fire trucks, diesel generators. Sufficient fuel supply for the equipment is provided on site for a minimum three days of operation. (author).

  9. On forecasting of rivers contamination as a result of Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Novitskij, M.A.

    2016-01-01

    Contamination of rivers on the territory effected by the Chernobyl accident is under consideration. On the base of analysis field and laboratory experiments data understanding about formation of long-lived radionuclides concentration in rain and snow melt runoff was elaborated. The correctness of mathematical model used for forecasting radiation situation on rivers was confirmed by the data of rivers contamination levels in spring 1987 [ru

  10. Time changes in radiocesium wash-off from various land uses after the Fukushima Daiichi NPP accident

    Science.gov (United States)

    Onda, Yuichi; Kato, Hiroaki; Yoshimura, Kazuya; Tsujimura, Maki; Wakiyama, Yoshifumi; Taniguchi, Keisuke; Sakaguchi, Aya; Yamamoto, Masayoshi

    2014-05-01

    A number of studies have been conducted to monitor and model the time series change of radiocesium transfer through aquatic systems after significant fallout, especially from the Chernobyl disaster. However, no data is available for the temporal changes of radiocesium concentration in environmental materials such as soil and water after the Fukushima Daiichi nuclear power plant accident. Our research team has been monitoring the environmental consequences of radioactive contamination just after the Fukushima Daiichi NPP accident in Yamakiya-district, Kawamata town, Fukushima prefecture. Research items are listed below. 1. Radiocesium wash-off from the runoff-erosion plot under different land use. 2. Measurement of radiocesium transfer in forest environment, in association with hydrological pathways such as throughfall and overlandflow on hillslope. 3. Monitoring on radiocesium concentration in soil water, ground water, and spring water. 4. Monitoring of dissolved and particulate radiocesium concentration in river water, and stream water from the forested catchment. 5.Measurement of radiocesium content in drain water and suspended sediment from paddy field. Our monitoring result demonstrated that the Cs-137 concentration in eroded sediment from the runoff-erosion plot has been almost constant for the past 3 years, however the Cs-137 concentration of suspended sediment from the forested catchment showed slight decrease through time. On the other hand, the suspended sediment from paddy field and those in river water from large catchments exhibited rapid decrease in Cs-137 concentration with time. The decreasing trend of Cs-137 concentration were fitted by the two-component exponential model, differences in decreasing rate of the model were compared and discussed among various land uses and catchment scales. Such analysis can provide important insights into the future prediction of the radiocesium wash-off from catchments with different land uses.

  11. Spatio-temporal variability of the deposited radioactive materials in forest environments after the Fukushima Daiichi NPP accident

    Science.gov (United States)

    Kato, H.; Onda, Y.; Komatsu, Y.; Yoda, H.

    2012-12-01

    Soil, vegetation and other ecological compartments are expected to be highly contaminated by the deposited radionuclides after the Fukushima Daiichi nuclear power plant (NPP) accident triggered by a magnitude 9.1 earthquake and the resulting tsunami on Marchi 11, 2011. Study site have been established in Yamakiya district, Kawamata Town, Fukushima prefecture, located about 35 km from Fukushima power plant, and designated as the evacuated zone. The total deposition of radioactive materials at the study site ranged from 0.02to >10 M Bq/m2 for Cs-137. The mature cedar, young cedar, and broad-leaf stands were selected as experimental site for the monitoring of spatio-temporal variability of the deposited radionuclides after the accidental release of radioactive materials. In order to measure the vertical distribution of radioactivity in forest, a tower with the same height of tree have been established at each experimental site. The measurement of radioactivity by using a portable Ge gamma-ray detector (Detective-DX-100, Ortec) and radionuclide analysis of leaf samples at different height revealed that a large proportion of radionuclides which deposited on forest were trapped by canopies of the cedar forests. In contrast, in the broad-leaf forest highest radioactivity was found at the forest floor. Furthermore, spatio-temporal variability of radioactivity at the forest floor indicated that huge amount of caesium still remains on the canopy of coniferous forest, and subsequently transfers to forest floor in association with throughfall, stemflow, and litter fall.

  12. The investigation of Passive Accident Mitigation Scheme for advanced PWR NPP

    International Nuclear Information System (INIS)

    Shi, Er-bing; Fang, Cheng-yue; Wang, Chang; Xia, Geng-lei; Zhao, Cui-na

    2015-01-01

    Highlights: • We put forward a new PAMS and analyze its operation characteristics under SBO. • We conduct comparative analysis between PAMS and Traditional Secondary Side PHRS. • The PAMS could cope with SBO accident and maintain the plant in safe conditions. • PAMS could decrease heat removal capacity of PHRS. • PAMS has advantage in reducing cooling rate and PCCT temperature rising amplitude. - Abstract: To enhance inherent safety features of nuclear power plant, the advanced pressurized water reactors implement a series of passive safety systems. This paper puts forward and designs a new Passive Accident Mitigation Scheme (PAMS) to remove residual heat, which consists of two parts: the first part is Passive Auxiliary Feedwater System (PAFS), and the other part is Passive Heat Removal System (PHRS). This paper takes the Westinghouse-designed Advanced Passive PWR (AP1000) as research object and analyzes the operation characteristics of PAMS to cope with the Station Blackout Accident (SBO) by using RELAP5 code. Moreover, the comparative analysis is also conducted between PAMS and Traditional Secondary Circuit PHRS to derive the advantages of PAMS. The results show that the designed scheme can remove core residual heat significantly and maintain the plant in safe conditions; the first part of PAMS would stop after 120 min and the second part has to come into use simultaneously; the low pressurizer (PZR) pressure signal would be generated 109 min later caused by coolant volume shrinkage, which would actuate the Passive Safety Injection System (PSIS) to recovery the water level of pressurizer; the flow instability phenomenon would occur and last 21 min after the PHRS start-up; according to the comparative analysis, the coolant average temperature gradient and the Passive Condensate Cooling Tank (PCCT) water temperature rising amplitude of PAMS are lower than those of Traditional Secondary Circuit PHRS

  13. Overview of IRSN R and D on NPP safety, with focus on severe accident

    International Nuclear Information System (INIS)

    Van Dorsselaere, Jean-Pierre

    2015-01-01

    IRSN contributes to the continuous improvement of safety level of Gen.II and III reactors, with the aim to approach for Gen.II the target safety level of Gen.III. This needs to build the necessary knowledge to appreciate margins for safety important systems, structures and components in the frame of plant operation life extension beyond 40 years. Research is a major IRSN mission that is tightly linked to expertise needs: it involves 40% of overall budget and, out of radiation protection and safety of waste disposal, around 280 scientists. IRSN has acquired a huge experience in the last 30 years on severe accidents, both on experimental and theoretical aspects, in particular through management of large international research programmes like the Phébus. FP integral experiments in the last 20 years and the coordination of the SARNET network of excellence that continues now in the frame of the NUGENIA European association. Besides, IRSN is developing, in collaboration with GRS (Germany), the integral system code ASTEC that is considered now as the European reference code due to the continuous capitalization of all the international knowledge. The presentation summarizes the ongoing IRSN research on the different phenomena involved in severe accidents, with more focus in the last years on mitigation devices or measures, i.e. for in-vessel and ex-vessel corium coolability, hydrogen explosion risk and source term. IRSN leads several international projects in Euratom frame (such as CESAM on ASTEC, PASSAM on source term mitigation, and IVMR on in-vessel corium retention) or OECD/NEA/CSNI (such as STEM). Moreover, several national projects on the above issues are ongoing with the French actors in this domain. Collaboration between IRSN and India is very active and efficient on ASTEC code with BARC and AERB, in particular through PHWR model development and assessment, and could be extended in the future to other issues either on severe accidents or on other Topics. (author)

  14. Influence of the Chernobyl NPP accident consequences to the animal kingdom. Chapter 4

    International Nuclear Information System (INIS)

    Pikulik, M.M.; Plenin, A.E.; Galkovskaya, G.A.; Zarubov, A.I.; Molotkov, D.V.; Khmeleva, N.N.; Golubev, A.P.; Moroz, M.D.; Petukhov, V.B.; Petrikov, A.M.; Kokhnenko, O.S.; Shevtsova, T.M.; Ermolaev, V.V.; Ermolaeva, I.A.; Maksimova, S.L.; Matveenko, A.A.; Blinov, V.V.; Shlyakhtenok, A.S.; Eliseeva, K.G.; Vojtovich, A.M.; Trusova, V.D.; Ogurtsova, S.Eh.; Drobenkov, S.M.; Nikiforov, M.E.; Tishechkin, A.K.; Samusenko, I.Eh.; Parejko, O.A.; Goncharova, R.I.; Ryabokon', N.I.; Rozhdestvenskaya, A.S.; Sidorovich, V.E.; Kozlo, P.G.; Dunin, V.F.; Kuchmel', S.V.; Deryabina, T.G.

    1995-01-01

    The total regularities of ionizing irradiation effect on the living systems, as well as molecular, cell and tissues radiation effects, radiation effects on organism, population and ecosystem are shown. The results of monitoring of zoo plankton systems, state of populations of mass species of benthos invertebrates and fishes in water reservoirs in the Chernobyl accident zone are given. Disorders in hemolymph and changes in complexes of soil invertebrates, as well as changes of population structures of amphibians and reptiles living in radioactive contaminated zone are described. The state of model groups and forming of population structure of insects, birds and mammals were investigated. 19 tabs., 16 figs

  15. Development of Highly Reliable Power and Communication System for Essential Instruments Under Severe Accidents in NPP

    Directory of Open Access Journals (Sweden)

    Bo Hwan Choi

    2016-10-01

    Full Text Available This article proposes a highly reliable power and communication system that guarantees the protection of essential instruments in a nuclear power plant under a severe accident. Both power and communication lines are established with not only conventional wired channels, but also the proposed wireless channels for emergency reserve. An inductive power transfer system is selected due to its robust power transfer characteristics under high temperature, high pressure, and highly humid environments with a large amount of scattered debris after a severe accident. A thermal insulation box and a glass-fiber reinforced plastic box are proposed to protect the essential instruments, including vulnerable electronic circuits, from extremely high temperatures of up to 627°C and pressure of up to 5 bar. The proposed wireless power and communication system is experimentally verified by an inductive power transfer system prototype having a dipole coil structure and prototype Zigbee modules over a 7-m distance, where both the thermal insulation box and the glass-fiber reinforced plastic box are fabricated and tested using a high-temperature chamber. Moreover, an experiment on the effects of a high radiation environment on various electronic devices is conducted based on the radiation test having a maximum accumulated dose of 27 Mrad.

  16. Development of highly reliable power and communication system for essential instruments under severe accidents in NPP

    International Nuclear Information System (INIS)

    Choi, Bo Hwan; Jang, Gi Chan; Shin, Sung Min; Kang, Hyun Gook; Rim, Chun Taek; Lee, Soo Ill

    2016-01-01

    This article proposes a highly reliable power and communication system that guarantees the protection of essential instruments in a nuclear power plant under a severe accident. Both power and communication lines are established with not only conventional wired channels, but also the proposed wireless channels for emergency reserve. An inductive power transfer system is selected due to its robust power transfer characteristics under high temperature, high pressure, and highly humid environments with a large amount of scattered debris after a severe accident. A thermal insulation box and a glass-fiber reinforced plastic box are proposed to protect the essential instruments, including vulnerable electronic circuits, from extremely high temperatures of up to 627 .deg. C and pressure of up to 5 bar. The proposed wireless power and communication system is experimentally verified by an inductive power transfer system prototype having a dipole coil structure and prototype Zigbee modules over a 7-m distance, where both the thermal insulation box and the glass-fiber reinforced plastic box are fabricated and tested using a high-temperature chamber. Moreover, an experiment on the effects of a high radiation environment on various electronic devices is conducted based on the radiation test having a maximum accumulated dose of 27 Mrad

  17. Estimation of health in Chernobyl NPP accident consequences cleaning-up participants

    International Nuclear Information System (INIS)

    Bebeshko, V.G.; Kovalenko, A.N.; Chomazjuk, I.N.

    1997-01-01

    Over 11 years period of health observation of Chernobyl Accident's victims permits to make some conclusions. Quantitative changes of peripheral blood and bone marrow cells, changes in ultrastructural organization of hemopoietic cells, disturbance of proliferative activity of hemopoietic and stromal progenitor cells in clean-up workers testify to alterations of functional properties of hemopoiesis. There are high level of T- helpers, early appearance regenerated T-cells, which simultaneously express surface antigens of helpers and supressors, synchronization of proliferative cycle of immunocompetentive cells in these patients. Oppressing of antioxidant protection, stable changes of hormonal maintenance of adaptation and reproduction processes, disturbance of feedback mechanism between effector glands and hypophysis, significant rise of polyamines were determined. Cardiovascular diseases are the principal cause of health disruptions at victims. Neural and psychological diseases, suicidal cases, trauma, death in automobile accidents are rank second and third in structure of morbidity. In structure of chronic nonspecific pulmonary diseases dominated chronic obstructive bronchitis. The adrenergic tonus of vegetative nervous system was seen. The peculiarity of rehabilitation measures is complexness and continuity in-patients, out-patients service and providing facilities in health resorts. (author)

  18. Development of highly reliable power and communication system for essential instruments under severe accidents in NPP

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Bo Hwan; Jang, Gi Chan; Shin, Sung Min; Kang, Hyun Gook; Rim, Chun Taek [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Lee, Soo Ill [I and C Group, Korea Hydro and Nuclear Power Co., Ltd, Central Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    This article proposes a highly reliable power and communication system that guarantees the protection of essential instruments in a nuclear power plant under a severe accident. Both power and communication lines are established with not only conventional wired channels, but also the proposed wireless channels for emergency reserve. An inductive power transfer system is selected due to its robust power transfer characteristics under high temperature, high pressure, and highly humid environments with a large amount of scattered debris after a severe accident. A thermal insulation box and a glass-fiber reinforced plastic box are proposed to protect the essential instruments, including vulnerable electronic circuits, from extremely high temperatures of up to 627 .deg. C and pressure of up to 5 bar. The proposed wireless power and communication system is experimentally verified by an inductive power transfer system prototype having a dipole coil structure and prototype Zigbee modules over a 7-m distance, where both the thermal insulation box and the glass-fiber reinforced plastic box are fabricated and tested using a high-temperature chamber. Moreover, an experiment on the effects of a high radiation environment on various electronic devices is conducted based on the radiation test having a maximum accumulated dose of 27 Mrad.

  19. ACCIDENT AT «FUKUSHIMA-»I NPP: FIRST RESULTS OF EMERGENCY RESPONSE REPORT 2: ACTIVITIES OF THE ROSPOTREBNADZOR AUTHORITIES FOR THE RADIATION PROTECTION OF THE RUSSIAN FEDERATION POPULATION ON THE EARLY STAGE OF ACCIDENT

    Directory of Open Access Journals (Sweden)

    G. G. Onischenko

    2011-01-01

    Full Text Available Basic measures of the Rospotrebnadzor emergency response during the early stage of the «Fukushima-I» NPP radiation accident are being analyzed in the article. Radiation monitoring of the environmental objects of the territories of the Russian Federation Far East Federal District, radiation control of arriving from Japan vehicles, freights and passengers as well as imported from Japan food products were promptly organized. This allowed to get reliable evaluations of the levels of radioactive contamination at the Russian Federation territory and population exposure doses due to the «Fukushima-I» NPP accident, timely exclude the possibility of import to the Russian territory for the freights, vehicles, food products having contamination exceeding established in the Russian Federation standards.

  20. Dynamics of natural rehabilitation of Cs 137 soil contamination at the late stage due to the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Germenchuk, M.G.; Zhukova, O.M.; Tretyakevich, S.S.; Koreniak, A.P.

    2006-01-01

    As a result of Chernobyl NPP accident, the greatest quantity of radionuclides has fallen on the territory of Belarus, therefore 23% of the territory have been contaminated with Cs 137 with a level exceeding 37 kBq/m 2 on the total area of 46.45 thousand km 2 that has led to the exclusion from an agricultural rotation 2,64 thousand km 2 of farmland. Now, external gamma-radiation on the territory of Belarus is formed due to 'Chernobyl' and 'global' (caused by tests of the nuclear weapon) radioactive losses. A contribution is also done by natural radioactivity. To-date, due to natural radionuclides decay a radiation conditions in zones of Chernobyl contamination has been stabilized and main dose formation radionuclide is Cs 137. In conformity with clause 4 of the Law 'On legal regime of territories, exposed to radioactive contamination after the Chernobyl nuclear power plant accident' the territory of the Republic of Belarus is divided into zones depending on radioactive contamination of soil by radionuclides and sizes of a mean-annual effective dose. The estimation of a dose of external irradiation demands establishment of interrelation between the level of soil contamination with radionuclides and created by them exposure dose power (EDP). As a quantitative size of this link, a normalized on density of contamination of soil Cs 137 EDP at 1 m height is most used which is formed by all radionuclides and is called the transition coefficient 'density of contamination of soil Cs 137 - EDP'. In the given work, empirical values of factor of transition on items of supervision of a network of the radiation monitoring, registered in National System of Environment Monitoring (NSEM) Republic of Belarus have been determined. The carried out data analysis for 1993-2003 showed, that: Value of transition factor within 10 years have changed from 0,054 μR/h/kBq·m 2 to 0,041 μR/h/kBq·m 2 (with 2,0 μR/h/Ci·km 2 to 1,5 μR/h/Ci·km 2 ). Decrease of EDP from 'Chernobyl' radioactive

  1. Peculiarities of hypothalamic-pituitary thyroid function in children born from the Chornobyl NPP accident survivors

    International Nuclear Information System (INIS)

    Kopylova, O.V.; Stepanenko, O.A.

    2015-01-01

    The 168 children born to parents exposed after the Chernobyl accident were examined to study the hypothalamic-pituitary-thyroid system function in descendants of the Chernobyl survivors. Clinical, hormonal, ultrasound examinations and challenge test with tyroliberynum were conducted. Some abnormalities that might explain the functional strain of the hypothalamic-pituitary system were identified being of a great role in origination and progress of thyroid disease. The prolonged strain leads to decreased production of thyroid hormone, which causes an increased secretion of thyroid stimulating hormone. Under the influence of TSH the thyroid gland in the first stage becomes increased in its mass, which leads to the formation of endemic goiter. Stable and permanent thyroid gland enlargement often leads to formation of the nodular goiter and other proliferative processes, namely to carcinogenesis

  2. Hydrogen-management in beyond design accident conditions in NPP Neckar 2

    International Nuclear Information System (INIS)

    Zaiss, W.

    1999-01-01

    Neckar 2 is a 1340 MWE 4-loop pressurized water reactor (PWR) of Siemens KONVOI type, located in the south of Germany. It was first connected to the grid in January 1989. Commercial operation started in April 1989. Task assignment: In Germany it was recommended by the Reactor Safety Commission (RSK) on December 17, 1997, to reequip passive autocatalytic recombiners for the controlling of the hydrogen problem. The removal of the hydrogen is an essential part which guarantees the integrity of the containment. The implementation of the recombiners is a further step for the decrease of the nuclear rest risk. The RSK confirmed, that the implementation of the passive autocatalytic recombiners is a safety measure for the controlled removal of the hydrogen in beyond design accident conditions. Assumption : Failure of the whole residual heat removal system (RHRS) and non sufficient effect of the systems which have been installed for beyond design accident conditions. Effect on the reactor coolant system (RCS): The reactor core will be damaged by non sufficient cooling with the output of hydrogen because all the specified emergency actions have failed. The overheating of the core is responsible for the production of hydrogen by the reaction of zirconium of the fuel-rod cladding with the water vapour. In case of nuclear superheating it would be possible that the reactor vessel would start smelting. The interacting between the core and the concrete, together with the armouring of the biological shield would also produce hydrogen. The hydrogen would escape together with the water vapour out of the leak and would spread out into the whole containment. Results : the number and the position of the different sized recombiners were determined on engineering judgement. the following 4 scenarios are representatively. The 4 scenarios were analyzed for in beyond design accident conditions with the MELCOR-Code: No. 1: Loss of main feedwater supply with primary feed and bleed. No. 2

  3. An experience of information support of the Russian federal programs of the overcoming of consequences of the accident at the Chernobyl NPP

    International Nuclear Information System (INIS)

    Linge, I.I.; Ossipiants, I.A.; Ilushkin, I.I.; Melihova, E.I.; Blinov, B.K.; Marchenko, T.A.

    2002-01-01

    Since 1992, by a number of paragraphs of the federal programs on overcoming consequences of accident on Chernobyl NPP, the measures on informational-analytic support of the federal programs were provided. Within the framework of this activity for the solution of various aspects of Chernobyl's problem central bank of generalized data and numerous information systems were created. In the report the brief description of some of them is presented. In particular the databank on radioactive situation includes the information on 12 thousand settlements of Russia which have been exposed to radioactive contamination as a result of the accident.The medico-demographic section of a databank includes information on death rate for the reasons for all subjects of Russian Federation since 1982 till the present time. The developed information systems are available to all participants of work on overcoming of consequences of the accident. There are given the examples of integral estimates in short- and long-term forecasts of development of a situation in territories suffered by the accident at the Chernobyl NPP. (author)

  4. Aerial spraying to capture released radioactivity from NPP in a severe accident

    Energy Technology Data Exchange (ETDEWEB)

    Younus, Irfan; Yim, Man Sung [KAIST, Daejeon (Korea, Republic of); Medard, Thiphaine [Ecole des Mines de Saint-Etienne, Daejeon (Korea, Republic of)

    2016-05-15

    The proposed strategy in this paper is the use of aqueous spray (water/foam) mixed with suitable chemical additives to capture, dissolve and stabilize the radioactive gases and aerosol particles released from leaked reactor containment and auxiliary building. The spray system can be approached to the leaked reactor building through the use of a truck with high rising cranes, unmanned aerial vehicles (UAVs, such as helicopters), aerostats, or by installing fixed piping structure around the containment building depending on the accident situation. Laboratory-scale experimental system was setup to examine the performance of such systems. The alkaline water (aqueous NaOH.Na{sub 2}S{sub 2}O{sub 3}) and foam-based spray material (sodium lauryl sulphate) were used to examine capture efficiency of gaseous iodine and aerosol particles. The gaseous iodine and aerosol removal efficiency of foam-based spray is higher when compared with alkaline water-based spray. 2. The nozzle producing full cone spray provides the better removal efficiency than nozzle producing hollow cone spray patterns.

  5. Aerial spraying to capture released radioactivity from NPP in a severe accident

    International Nuclear Information System (INIS)

    Younus, Irfan; Yim, Man Sung; Medard, Thiphaine

    2016-01-01

    The proposed strategy in this paper is the use of aqueous spray (water/foam) mixed with suitable chemical additives to capture, dissolve and stabilize the radioactive gases and aerosol particles released from leaked reactor containment and auxiliary building. The spray system can be approached to the leaked reactor building through the use of a truck with high rising cranes, unmanned aerial vehicles (UAVs, such as helicopters), aerostats, or by installing fixed piping structure around the containment building depending on the accident situation. Laboratory-scale experimental system was setup to examine the performance of such systems. The alkaline water (aqueous NaOH.Na_2S_2O_3) and foam-based spray material (sodium lauryl sulphate) were used to examine capture efficiency of gaseous iodine and aerosol particles. The gaseous iodine and aerosol removal efficiency of foam-based spray is higher when compared with alkaline water-based spray. 2. The nozzle producing full cone spray provides the better removal efficiency than nozzle producing hollow cone spray patterns.

  6. Post-accident environmental radiomonitoring in the vicinity of the Chernobyl NPP

    International Nuclear Information System (INIS)

    Hashari, M.; Assadi, M.; Reese, S.

    1997-01-01

    After the Chernobyl accident, the vicinity around the fourth reactor unit, destroyed after explosion, has become the largest outdoor laboratory, where the mankind's knowledge concerning the, radionuclides behaviour in the environment can be essentially tested and improved. An international group of scientists from the Ukraine, USA and the IAEA fellows from Brasil, Kenya, Syria and Iran as participants of Summer School on environmental monitoring, took participation in field exercises to investigate radioecological situation inside 30-km Exclusion Zone at three different sites: two fields and one forest with inherent levels of contamination. The present radioecological situation inside the 30-km Exclusion Zone is mainly determined by the 137 Cs + 134 Cs, 90 Sr and transuranic elements as well. The international group divided into teams and performed gamma and beta surveys, in-situ gamma-spectrometry and vegetation and soil sampling in contaminated field and forest locations. The aim of this work was to investigate the peculiarities of measurement at different sites and to develop recommendations on group-made environmental monitoring

  7. Radiological impact assessment for a severe accident scenario for a CANDU 6 type NPP

    International Nuclear Information System (INIS)

    Penescu, Maria; Mehedinteanu, Stefan; Cruceanu, Amalia; Ispas, Georgeta

    2004-01-01

    . The consequences of a given accidental release will depend on the values of a number of parameters, in particular, type and nature of the accident, the total amount of radioactive material and different radionuclides involved, the energy with which they are disposed in the environment, the nature of the surrounding environment and the mechanisms of radioactive dispersion and transfer. This paper presents some assessments on the LOCA type accident influence, without the intact loop cooling and ECCS in case of a hypothetical site. The developed assessments resulted in the necessity to evacuate the population up to a distance of about 10 km away from the sectors located in the wind blowing direction. Note that for a real situation of a site, smaller values of the doses are expected, considering other phenomena which may lead to the decrease of the dose values for individuals (the consideration of the meteorologic parameter hourly values, of precipitation, of the actual distribution of population, of the protection measure application, etc)

  8. Time changes in radiocesium concentration in aquatic systems affected by the Fukushima Daiichi NPP accident

    Science.gov (United States)

    Onda, Yuichi; Taniguchi, Keisuke; Kato, Hiroaki; Yoshimura, Kazuya; Wakiyama, Yoshifumi; Iwagami, Sho; Tsujimura, Maki; Sakaguchi, Aya; Yamamoto, Masatoshi

    2015-04-01

    Due to Fukushima Daiichi Nuclear Power Plant accident, radioactive materials including Cs-134 and Cs-137 were widely distributed in surrounded area. The radiocesiums have been transported in river networks. The monitoring started at 6 sites from June 2011. Subsequently, additional 24 monitoring sites were installed between October 2012 and January 2013. Flow and turbidity (for calculation of suspended sediment concentration) were measured at each site, while suspended sediments and river water were collected every one or half month to measure Cs-134 and Cs-137 activity concentrations by gamma spectrometry. Also detailed field monitoring has been condcuted in Yamakiya-district, Kawamata town, Fukushima prefecture. These monitoring includes, 1) Radiocesium wash-off from the runoff-erosion plot under different land use, 2) 2. Measurement of radiocesium transfer in forest environment, in association with hydrological pathways such as throughfall and overlandflow on hillslope, 3) Monitoring on radiocesium concentration in soil water, ground water, and spring water, 4)Monitoring of dissolved and particulate radiocesium concentration in river water, and stream water from the forested catchment, and 5)Measurement of radiocesium content in drain water and suspended sediment from paddy field. Our monitoring result demonstrated that the Cs-137 concentration in eroded sediment from the runoff-erosion plot has been almost constant for the past 3 years, however the Cs-137 concentration of suspended sediment from the forested catchment showed slight decrease through time. On the other hand, the suspended sediment from paddy field and those in river water from large catchments exhibited rapid decrease in Cs-137 concentration with time. The decreasing trend of Cs-137 concentration were fitted by the two-component exponential model, differences in decreasing rate of the model were compared and discussed among various land uses and catchment scales. Such analysis can provide

  9. Distribution and migration of ⁹⁰Sr in components of the Dnieper River basin and the Black Sea ecosystems after the Chernobyl NPP accident.

    Science.gov (United States)

    Mirzoyeva, N Yu; Egorov, V N; Polikarpov, G G

    2013-11-01

    The change in (90)Sr concentrations in hydrobionts, water and bottom sediments of the Chernobyl NPP pond-cooler, the Kievskoe and Kakhovskoe reservoirs, the Northern-Crimean canal and the Black Sea after the Chernobyl NPP accident was studied. The environmental half-times for the decrease of (90)Sr concentrations were determined: in water - 4.1-24.3 years; algae and flowering water plants - 3.6-7.7 years, in molluscs - 2.4-6.7 years, and in fish - 7.8-12.9 years. The time for (90)Sr concentrations to decrease to pre-accident levels were estimated: in freshwater reservoirs and the northwest part of the Black Sea this was 32-44 years, and in freshwater hydrobionts this was 25-73 years. The contribution of dose from (90)Sr to the hydrobionts, sampled from the Kakhovskoe reservoir, the Northern-Crimean canal and the Black Sea, has not reached values which could impact them during the entire post-accident period. This complex of comparative studies was carried out for the first time. Copyright © 2013 Elsevier Ltd. All rights reserved.

  10. 90Sr content in the Black Sea bottom sediments after the Chernobyl NPP accident and its use as a radiotracer for an assessment of bottom settlement rate

    International Nuclear Information System (INIS)

    Mirzoyeva, N. Y.; Egorov, V. N.; Polikarpov, G. G.

    2006-01-01

    The increase of 9 0Sr concentrations in the Black Sea bottom sediments along to western coast of the Black Sea and south part of Crimea was observed in 1987-1988 years. To our opinion, it was connected with hydrological processes (for example, currents), occurring in the given sea parts. The most polluted by post-Chernobyl 9 0Sr areas were bottom sediments of Dnieper, Dniester and Danube River deltas, territory of an arrangement of a main channel of the North-Crimea Channel - region of a peninsula Tarkhankut, southeast part of Crimea (Feodosiya area). The similar situation in confined of the greatest contents 9 0Sr to the specified areas not only is kept with time (till 2000), but the process of increase of 9 0Sr concentration in bottom sediments of the investigated regions is observed. So average concentration of 9 0Sr in Dnieper River delta bottom sediments in 1987 was 28,5 Bq kg - 1 , in 2000 - 148,2 28,5 Bq kg - 1 of Dry Weight. Such character of 9 0Sr redistribution shows, that both in first years after Chernobyl NPP accident, and in the following time, the entry of 9 0Sr in the Black Sea basin occurs, basically, with water flow of the large rivers in a northwest part of the Black Sea, discharge waters of the North-Crimean Channel. These sources of 9 0Sr input to the Black Sea ecosystem considerably prevailed above direct atmospheric pollution by given radionuclide in April-May 1986 at once after the Chernobyl NPP accident. On the base of monitoring researches results the maps of 9 0Sr dynamics redistribution in the Black Sea bottom sediments (0-5 cm) since 1986 (Chernobyl NPP accident) up to 2000 were sketched out. The distribution of 9 0Sr radionuclide in the bottom sediments columns, which were selected from the Corukh river mouth region and from the Dnieper-Bug estuary area, is investigated. The peaks of 9 0Sr increased contents were founded in the profile of its vertical distribution in the bottom sediments. These peaks correspond to the periods of 9 0Sr

  11. Chernobyl'-88. Reports of the 1. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 4. Organization of accident effect elimination and prospects of the 30-km zone use

    International Nuclear Information System (INIS)

    Ignatenko, E.I.

    1989-01-01

    Some results of liquidation of the Chernobyl' NPP accident effects and main principles of the zone development are discussed. The problems of management for the zone territory and natural objects and the ways for wood industry development are considered. The state estimation and forecasting for conifers in the zone, wood ecosystem radioactive contamination effects, analysis of conifer genetic effects are made. The results of physical-mathematical simulation of formation of the Chernobyl' NPP near zone territory contamination with long-living radionuclides are given. The protection ability of the aeration zone soil-grounds within the boundaries of radiogeochemical effects of radioactive effluents from internal surfaces of air conduit and ventilation duct during ventilation system operation is estimated

  12. The Thirty Years’ Results of Radiation Hygienic Monitoring of Tula Region territories contaminated due to the Chernobyl NPP accident

    Directory of Open Access Journals (Sweden)

    V. V. Boldyreva

    2016-01-01

    Full Text Available Over 50% of Tula Region areas were contaminated after the Chernobyl NPP accident. The article provides the thirty years’ results of radiation hygienic monitoring of the Chernobyl accidental fallout - affected areas in Tula Region. The radiation situation is assessed at the initial accidental period and at the current stage. The initial levels of gamma - radiation dose intensity (up to 35 mcSv/hr are identified for the period of the “iodine” hazard along with the tabular data on the dose intensity relative stabilization by the beginning of August 1986 due to iodine-131 decay. The information is presented regarding iodine-131 tentative maximum permissible level exceedance in the dairy products of the two most contaminated regional areas - Plavskoye and Arsenievskoye. The article also provides the laboratory data on the total beta - activity in the foodstuffs in 1986-1987 and cesium-137 maximum permissible level exceedence in 1986. The radionuclide maximum permissible level exceedances in foodstuffs were registered only in 1986 due to the plants surface contamination whereas in the forest mushrooms those exceedances were repeatedly found until 2004. The black earths and grey forest soils had a benign impact upon the intensity of the radionuclide transfer into plants which resulted in the formation of internal radiation doses.At the current stage, the content of cesium-137 and strontium- 90 in the foodstuffs can only be quantified by a radiochemical method. The table covers all the districts within the boundaries of radiation contaminated zones. The radiochemical studies indicate the main dose - forming products. The article contains the table of internal and external radiation doses of the population in Plavsk town over 1986-1990 and displays the factors impacting population’s internal and external exposure. The Chernobyl - affected exposure dose of the population is mostly attributed to the external radiation and, for over twenty years, it

  13. The Project on the distribution of fallout radionuclide and their transfer through environment by Fukushima Daiichi NPP accident

    Science.gov (United States)

    Onda, Yuichi; Kato, Hiroaki; Yoshimura, Kazuya; Fukushima, Takehiko; Patin, Jeremy

    2013-04-01

    Radioactive contamination has been detected in Fukushima due to the nuclear accident at Fukushima Daiichi Nuclear Power Plant (NPP) following the earthquake and tsunami on 11 March 2011. Following comprehensive investigation (FMWSE project funded by MEXT, Japan; http://fmwse.suiri.tsukuba.ac.jp/) was conducted to confirm migration of radionuclides through natural environment including soils and rivers. Experimental catchments have been established in Yamakiya district, Kawamata Town, Fukushima prefecture, located about 35 km from Fukushima power plant, and designated as the evacuated zone. Approximate Cs-137 fallout in this area is 200 - 600 kBq/m2. (1) Migration study of radionuclides in natural environment including forests and rivers: 1) Depth distribution of radiocaesium in soils within forests, fields, and grassland, 2) Confirmation of radionuclide distribution and investigation on migration in forests, 3) Study on radionuclide migration due to soil erosion under different land use, 4) Measurement of radionuclides entrained from natural environment including forests and soils. (2) Migration study of radionuclides through hydrological cycle such as soil water, rivers, lakes and ponds, ground water: 1) Investigation on radionuclide migration through soil water, ground water, stream water, spring water under different land use, 2) Study on paddy-to-river transfer of radionuclides through suspended sediments, 3) Study on river-to-ocean transfer of radionuclides via suspended sediments, 4) Confirmation of radionuclide deposition in ponds and reservoirs. The main finding is as follows: 1) Migration of radionuclides to soil water, stream water and ground water was confirmed low at present. On the other hand, concentration of radiocaesium was found approximately 50 kBq/kg in the suspended sediments flowing down the river. 2) Amount of sediments deposited in the tank placed at the end of downstream within the USLE plot was confirmed together with the concentrations of

  14. National report on 'stress tests', NPP Dukovany and NPP Temelin, Czech Republic. Evaluation of safety and safety margins in the light of the accident of the NPP Fukushima. Rev. 1

    International Nuclear Information System (INIS)

    2012-03-01

    The stress tests were performed based on European Commission requirement as a response to the Fukushima-Daiichi accident. The stress tests encompassed the Dukovany and Temelin nuclear power plants and concentrated on the potential impacts of earthquakes, flooding, extreme weather conditions, loss of electrical power and loss of ultimate heat sink, and severe accident management. (P.A.)

  15. The peculiarities of accumulation of Cs 137 by mushrooms after accident of the Chernobyl NPP in 1986

    International Nuclear Information System (INIS)

    Zarubina, N.E.; Trishin, V.V.; Malyuk, I.A.; Golovach, L.A.

    2005-01-01

    The researches which have been carried out in the territory by the Kiev region, including 30-km the zone of the Chernobyl NPP showed that major factors influencing levels of the Cs 137 accumulation by mushrooms, are: density of pollution soils by these radionuclides; belonging of mushrooms to the certain ecological group; depth of localization in soil mycelium of each kind. (authors)

  16. Abstracts of papers of international scientific conference 'Fundamental and applied aspects of radiobiology: Biological effects of low doses and radioactive contamination of environment (Radioecological and medical biological consequences of the Chernobyl NPP accident)'

    International Nuclear Information System (INIS)

    Konoplya, E.F.; Astakhov, A.I.; Bogdevich, I.M.; Borisevich, N.Ya.; Zubovich, V.K.; Knat'ko, V.A.; Lobanok, L.M.; Matsko, V.P.; Mrochek, A.G.

    1998-05-01

    The results of research works executed in Belarus, as well as in Ukraine and Russia, on various aspects of the Chernobyl problematic are given: radiation medicine and risks, radiobiological effects and their forecasting, radioecology and agricultural radiology, decontamination and radioactive wastes management, socio economic and psychological problems caused by the Chernobyl NPP accident

  17. Graphic console for analysis of severe accidents visualization of OEs, NAEs and calculation of the source term for the NPP-LV (CoGrAAS)

    International Nuclear Information System (INIS)

    Sandoval V, S.; Mendoza E, P. R.; Gonzalez C, J. M.; Cecenas F, M.; Tijerina S, F.

    2016-09-01

    In response to the Fukushima Daiichi nuclear power plant accident, the NRC conducted an analysis and issued recommendations to improve the safety of the nuclear reactors. These include strengthening and integrating emergency response capabilities and emphasizing periodic staff training, the performance of simulation exercises. As a tool to observe these recommendations, the Graphic Console was developed for Analysis of Severe Accidents, Visualization of OEs, NAEs and calculation of the source term for nuclear power plant of Laguna Verde (NPP-LV ; CoGrAAS). The CoGrAAS is a computer system that displays in an integrated, graphic and dynamic way the information of a catalog of previously simulated accident scenarios. Has core mimics, vessel, primary containment and safety systems, trend graph of thermodynamic and radiological variables and the emergency procedures (OEs), chronological list of events, windows with detailed information for the dry-well, among others. The use of CoGrAAS allows that staff to understand and become familiar with the thermo-hydraulic progression of actual scenarios that exceed the design basis including those with core damage as severe accidents. The system enables personnel to develop an integral vision of the scenarios during the exercises and drills by observing and analyzing the evolution of the main reactor, core and primary containment variables, the response of emergency systems and the influence of that progression on OEs and the emergency action levels (NAEs). The CoGrAAS allows o observe the radiological variables and obtain the source term, to make the projection of doses, at any time within the scenario evolution. Thus, not only can the phenomenology of severe accidents be analyzed and understood, it is also possible to exercise, verify and evaluate the performance of critical tasks in the application of procedures, guidelines and emergency management plans. (Author)

  18. Intelligent system for accident identification in NPP; Sistema inteligente para la identificacion de accidentes en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez, J L [Centro Nacional de Seguridad Nuclear, La Habana (Cuba)

    1999-12-31

    Accidental situations in NPP are great concern for operators, the facility, regulatory bodies and the environmental. This work proposes a design of intelligent system aimed to assist the operator in the process of decision making initiator events with higher relative contribution to the reactor core damage occur. The intelligent System uses the results of the pre-operational Probabilistic safety Assessment and the Thermal hydraulic Safety Analysis of the NPP Juragua as source for building its knowledge base. The nucleus of the system is presented as a design of an intelligent hybrid from the combination of the artificial intelligence techniques fuzzy logic and artificial neural networks. The system works with variables from the process of the first circuit, second circuit and the containment and it is presented as a model for the integration of safety analyses in the process of decision making by the operator when tackling with accidental situations

  19. Peculiarities of viruses Herpesviridae family persistence in patients with non-alcoholic fatty liver disease who had been exposed to the factors of Chornobyl NPP accident

    International Nuclear Information System (INIS)

    Chumak, A.A.; Nosach, O.V.; Ovsyannyikova, L.M.; And Others

    2014-01-01

    According to the presence of class IgG antiviral antibodies, NAFLD patients regardless of radiation influence in anamnesis have high prevalence of Herpesviridae family viral infection: herpes simplex 1/2 types, cytomegalovirus and Epstein-Barr virus. In the group of patients who had been exposed to the factors of Chornobyl NPP accident greater part of seropositive results and higher mean values of the probed antibodies titres were registered than in the groups of comparison. The mix infection by the viruses of herpes simplex 1/2 types and cytomegaly was registered in most patients with existence of direct correlation between the levels of anti-HSV-1/2 IgG and anti-CMV IgG

  20. On the results of nuclear fuel temperature dynamics restoration at the Chornobyl NPP unit 4 during active phase of the accident

    Directory of Open Access Journals (Sweden)

    O. V. Mikhailov

    2016-02-01

    Full Text Available Fuel temperature dynamics was reconstructed for active phase of the accident at the Chernobyl NPP Unit 4. Method of effective temperature calculation for uranium oxide is based on implementation of the CORSOR type mathematical codes and the model of lava-like fuel containing materials (LFCM formation from fragments of the former core (FFC in the room 305/2. Calculations were carried out according to release rate of 131I and 137Cs radionuclides during the period from April 26 until May 6, 1986. The rate of temperature drop during the FCM stage cooling bath silicate melt was estimated. It is shown that the main streams of LFCM could be formed at more moderate values of temperatures than it was performed previously. The results of the work are used to verify the “blast furnace” version of LFCM formation and formation of FCM with high uranium concentration.

  1. A recommended epidemiological study design for examining the adverse health effects among emergency workers who experienced the TEPCO fukushima daiichi NPP accident in 2011.

    Science.gov (United States)

    Yasui, Shojiro

    2016-01-01

    Results from medical examinations conducted in 2012 of workers who were engaged in radiation work in 2012 as a result of the 2011 Fukushima Daiichi Nuclear Power Plant (NPP) accident showed that the prevalence of abnormal findings was 4.21%, 3.23 points higher than the 0.98% that was found prior to the accident in the jurisdiction area of the labor inspection office which holds jurisdiction over the NPP. The Ministry of Health, Labour and Welfare (MHLW) concluded that the 2010 and 2012 data cannot be easily compared because 70% of the enterprises within the jurisdiction of the office that reported the 2012 results were different from those that did so in 2010. In addition, although the radiation workers' estimated average dose weighted by number of workers was 3.66 times higher than decontamination workers' dose, the prevalence among radiation workers was only 1.14 times higher than that among decontamination workers. Based on the results of the medical examinations, however, the MHLW decided to implement an epidemiological study on the health effects of radiation exposure on all emergency workers. This article explains key issues of the basic design of the study recommended by the expert meeting established in the MHLW and also identifies challenges that could not be resolved and thus required further consideration by the study researchers. The major issues included: (a) study methods and target group; (b) evaluation of cumulative doses; (c) health effects (end points); (d) control of confounding factors; and (e) study implementation framework. Identified key challenges that required further deliberation were: (a) preventing arbitrary partisan analysis; (b) ensuring a high participation rate; (c) inquiry about the medical radiation doses; and (d) the preparedness of new analytical technology. The study team formulated and implemented the pilot study in 2014 and started the full-scale study in April 2015 with funding from a research grant from the MHLW.

  2. A brief overview of Ignalina NPP safety issues

    International Nuclear Information System (INIS)

    Almenas, K.; Ushpuras, E.

    1998-01-01

    A description of the safety of Ignalina NPP in a very popular form is presented. Answers to the most frequently recurring questions concerning the Ignalina NPP are provided based on recently completed international studies. Questions are like these: can a similar accident to the one that occurred in Chernobyl take place at Ignalina NPP, does the Ignalina NPP have a containment, what are the probabilities and potential consequences of accidents, etc. The brochure contains a short description of Ignalina NPP safety improvement programs

  3. Social aspects in evaluation of health status of subjects who participated in liquidation of radiation accident consequences

    International Nuclear Information System (INIS)

    Tukov, A.R.; Kleev, N.A.; Shafranskij, I.L.

    2000-01-01

    The morbidity rate of the Russian atomic industry workers, the liquidators of ChNPP accident consequences and their future life span shorting with an account of their social status are evaluated. Tentative and standard morbidity values were calculated with an account of various social groups of the liquidators. Intensive values of the man-year losses were used in the methodology for evaluating the vital potential losses. The study results indicated considerable morbidity difference in certain diseases by the persons of various social groups, who took part in liquidation of the ChNPP accident consequences [ru

  4. Dynamics of health status of residents in the Lugyny district after the accident at the ChNPS

    International Nuclear Information System (INIS)

    Godlevsky, I.; Nasvit, O.

    1998-01-01

    The Lugyny district lies in the northern part of the Zhytomyr region of Ukraine within 110-150 km from the Chernobyl nuclear power station (ChNPS). Its territory is crossed by the southern and south-western tracks that were formed by the Chernobyl accident in April 1986. The total territory of the district constitutes approximately 900 km 2 , the territory of agricultural land - more than 300 km 2 , and about 190 km 2 of them arable land. Practically all agricultural land in the district have the 137 Cs contamination density higher than 1 Ci/km 2 . Prior to the Chernobyl accident about 30 thousand residents were living in the Lugyny district. By the present moment the population of the district has dropped to approximately 22 thousand people due to resettlement from the most contaminated territories and the decrease in the birth-rate. (J.P.N.)

  5. MDEP AP1000WG Design-Specific Common Position CP-AP1000WG-02. Common position addressing Fukushima Daiichi NPP accident-related issues

    International Nuclear Information System (INIS)

    2016-09-01

    A severe accident involving several units took place in Japan at Fukushima Daiichi nuclear power plant (NPP) in March 2011. The immediate cause of the accident was an earthquake followed by a tsunami coupled with inadequate provisions against the consequences of such events in the design. Opportunities to improve protection against a realistic design basis tsunami had not been taken. As a consequence of the tsunami, safety equipment and the related safety functions were lost at the plant, leading to core damage in three units and subsequently to large radioactive release. Several studies have already been performed to better understand the accident progression and detailed technical studies are still in progress in Japan and elsewhere. In the meantime, on-going studies on the behaviour of nuclear power plants in very severe situations, similar to Fukushima Daiichi, seek to identify potential vulnerabilities in plant design and operation; to suggest reasonably practicable upgrades; or to recommend enhanced regulatory requirements and guidance to address such situations. Likewise, agencies around the world that are responsible for regulating the design, construction and operation of AP1000 R plants are engaged in similar activities. The MDEP AP1000 R Working Group (AP1000 WG) members consist of members from Canada, China, the United Kingdom and the United States. Since the regulatory review of their AP1000 R applications have not been completed by all of these Countries yet, this paper identifies common preliminary approaches to address potential safety improvements for AP1000 R plants as related to lessons learned from the Fukushima Daiichi accident or Fukushima Daiichi-related issues. In seeking common position, regulators will provide input to this paper to reflect their safety conclusions regarding the AP1000 R design and how the design could be enhanced to address Fukushima Daiichi issues. The common preliminary approaches are organized into five sections

  6. The main results of fulfilment in 1996 of the scientific part of the State programme of the Republic of Belarus for minimization and overcoming of the Chernobyl NPP accident consequences (1996-2000)

    International Nuclear Information System (INIS)

    Konoplya, E.F.

    1997-01-01

    In the publication are summarized the basic results of the researches executed in 1996 in the framework of the 'Scientific maintenance of the decision of problems of the Chernobyl NPP accident consequences' of the State program of Republic of Belarus for minimization and overcoming of the Chernobyl NPP accident consequences on 1996-2000 on the following directions: dose monitoring of the population, estimation and forecast of both collective irradiation dozes and risks of radiation induced diseases; development and optimization of a complex of measures for effective land use and decrease of radioactive contamination of agricultural production in order to reduce irradiation dozes of the population; development of complex technologies and means of decontamination, processing and burial of radioactive wastes; development of the measures for increase of radiation protection of the population of Belarus during of the reducing period after the Chernobyl accident; development of complex system of an estimation and decision-making on problems of radiation protection of the population living on contaminated territories; study of influence of radiological consequences of the Chernobyl accident on health of people, development of methods and means of diagnostics, treatment and preventive maintenance of diseases for various categories of the victims; development of effective methods of preventive maintenance and treatment of diseases of both mother and child in conditions of influence of the Chernobyl NPP accident consequences; study of genetic consequences caused by the Chernobyl accident and development of effectual measures of their prevention; creation of the effective both prophylactic means and food additives for treatment and rehabilitation of the persons having suffered after the Chernobyl accident; study of the radioisotopes behaviour dynamics in environment (air, water, ground), ecosystems and populated areas; optimization of the system of radiation ecological

  7. Population-genetic consequences of the accident at the Chernobyl NPP for cattle self-reproducing in the alienated zone

    International Nuclear Information System (INIS)

    Glazko, T.T.; Glazko, V.I.

    2001-01-01

    We have performed the analysis of a genetic structure for generations of cattle-self-reproducing under conditions of enhanced radioactive contamination in the alienated zone near the Chernobyl NPP. Only in the second generation was revealed one animal mutated by the transferrin locus. The violation of the equiprobable transfer of allelic variants by certain loci from parents to off springs is observed. It is shown that heterozygosity does not decrease in generations in spite of inbreeding. The possible mechanisms of the phenomena observed are considered

  8. Demographic situation in the Kaluga region for 1976-1992. Possible consequences of the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Omel'chenko, V.N.; Kurochkina, O.I.; Kostina, M.A.; Sidenko, L.G.

    1993-01-01

    The paper studies the demographic situation in different areas of the Kaluga region contaminated as a result of the Chernobyl accident, during 1976-1992. The following indices received the particular attention: the composition of population, size of population, birth rate, mortality, child mortality. It is shown that during the investigated period no variations of the size of population, of the mortality and of the increment of population resulted from the Chernobyl accident were detected

  9. Brief review of 1995 events at Ukraine's NPPs. Report on the ChNPP unit 1 of November 27.1995 ''strict regime area premises contamination after reactor refuelling''

    International Nuclear Information System (INIS)

    Lomakin, V.

    1996-01-01

    In 1995 number of events at NPP had considerably decreased as compared with that for previous 1992-94, amounted in 87. In particular, as compared with 1994, events number had decreased by 36%. It characterizes a total improvement of current NPPs safety level during 1995. The most events number as recalculated per single unit was at the South Ukraine NPP - 8. The least - at the ChNPP - 4 in total, and 1,3 per unit. Decreasing of a total events number for 1995 did also accordingly reduce other quantitative system indices which reflect state of NPPs safety level. Among event root causes, as it was before, ''administrative management deficiencies'' and ''staff training deficiencies'' are still dominanting. ''Human factor'' issues are still pending for NPPs safety, despite of considerable efforts applied to improved efficiency of correcting measures aimed at their solution. Of sufficient importance for events system development in 1995 was the work implemented at the SSTC NRS/NRA as regards preparation of modern edition of the ''Regulation on order of NPP events investigation and account''. The IAEA/Nuclear Safety Division rendered a sufficient assistance for this work to be done through arrangement of advisory help to Ukrainian specialists from international experts. 2 figs, 8 diagrams

  10. Experience in accident liquidation at the Chernobyl' NPP and problems of organization of the emergency-engineering service

    International Nuclear Information System (INIS)

    Andreev, Yu.B.; Samojlenko, Yu.N.

    1989-01-01

    The efficiency of measures realized in order to eliminate the Chernobyl' accident effects is estimated. The principles of organization of the emergency-engineering service for accident elimination in nuclear power engineering are described. The automated information safety system should from the technical basis for this service. The information system structure is determined. The list of main directions of research and design works realized in the emergency-engineering service interests is given. It is noted that all parts of the emergency-engineering service must prepare the plants of works together with the USSR civil defense service, and they should interact in the process of accident elimination basing on coordinated organizational and technical solutions

  11. Some aspects of the population relocation from Bryansk region areas contaminated due to the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Kislov, M.V.; Karlin, N.E.; Liberman, A.N.; Bronshtejn, I.Eh.; Nuralov, V.N.; Karlina, L.V.

    1993-01-01

    The paper presents the results of the investigations carried out in 1992 linked with the resettlement of people from the Bryansk region areas affected by the Chernobyl accident with analysis of some use-harm indices. Resettlement is shown to be the most radical way of protection and to prevent completely the effect of irradiation, but to be accomplished with the essential money expenses ad inadequately determined social-and-psychological and medical-and-biological consequences for people health. Decision about people resettlement, especially at the accident latest stage, should be obligatory based on the use-harm analysis

  12. STEAM GENERATOR TUBE INTEGRITY ANALYSIS OF A TOTAL LOSS OF ALL HEAT SINKS ACCIDENT FOR WOLSONG NPP UNIT 1

    Directory of Open Access Journals (Sweden)

    HEOK-SOON LIM

    2014-02-01

    Full Text Available A total loss of all heat sinks is considered a severe accident with a low probability of occurrence. Following a total loss of all heat sinks, the degasser/condenser relief valves (DCRV become the sole means available for the depressurization of the primary heat transport system. If a nuclear power plant has a total loss of heat sinks accident, high-temperature steam and differential pressure between the primary heat transport system (PHTS and the steam generator (SG secondary side can cause a SG tube creep rupture. To protect the PHTS during a total loss of all heat sinks accident, a sufficient depressurization capability of the degasser/condenser relief valve and the SG tube integrity is very important. Therefore, an accurate estimation of the discharge through these valves is necessary to assess the impact of the PHTS overprotection and the SG tube integrity of the primary circuit. This paper describes the analysis of DCRV discharge capacity and the SG tube integrity under a total loss of all heat sink using the CATHENA code. It was found that the DCRV's discharge capacity is enough to protect the overpressure in the PHTS, and the SG tube integrity is maintained in a total loss of all heat accident.

  13. Steam Generator Tube Integrity Analysis of A Total Loss of all Heat Sinks Accident for Wolsong NPP Unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Heoksoon; Song, Taeyoung; Chi, Moongoo [Korea Htydro and Nuclear Power Co., Ltd., Daejeon (Korea, Republic of); Kim, Seoungrae [Nuclear Engineering Service and Solution, Daejeon (Korea, Republic of)

    2014-02-15

    A total loss of all heat sinks is considered a severe accident with a low probability of occurrence. Following a total loss of all heat sinks, the degasser/condenser relief valves (DCRV) become the sole means available for the depressurization of the primary heat transport system. If a nuclear power plant has a total loss of heat sinks accident, high-temperature steam and differential pressure between the primary heat transport system (PHTS) and the steam generator (SG) secondary side can cause a SG tube creep rupture. To protect the PHTS during a total loss of all heat sinks accident, a sufficient depressurization capability of the degasser/condenser relief valve and the SG tube integrity is very important. Therefore, an accurate estimation of the discharge through these valves is necessary to assess the impact of the PHTS overprotection and the SG tube integrity of the primary circuit. This paper describes the analysis of DCRV discharge capacity and the SG tube integrity under a total loss of all heat sink using the CATHENA code. It was found that the DCRV's discharge capacity is enough to protect the overpressure in the PHTS, and the SG tube integrity is maintained in a total loss of all heat accident.

  14. Steam Generator Tube Integrity Analysis of A Total Loss of all Heat Sinks Accident for Wolsong NPP Unit 1

    International Nuclear Information System (INIS)

    Lim, Heoksoon; Song, Taeyoung; Chi, Moongoo; Kim, Seoungrae

    2014-01-01

    A total loss of all heat sinks is considered a severe accident with a low probability of occurrence. Following a total loss of all heat sinks, the degasser/condenser relief valves (DCRV) become the sole means available for the depressurization of the primary heat transport system. If a nuclear power plant has a total loss of heat sinks accident, high-temperature steam and differential pressure between the primary heat transport system (PHTS) and the steam generator (SG) secondary side can cause a SG tube creep rupture. To protect the PHTS during a total loss of all heat sinks accident, a sufficient depressurization capability of the degasser/condenser relief valve and the SG tube integrity is very important. Therefore, an accurate estimation of the discharge through these valves is necessary to assess the impact of the PHTS overprotection and the SG tube integrity of the primary circuit. This paper describes the analysis of DCRV discharge capacity and the SG tube integrity under a total loss of all heat sink using the CATHENA code. It was found that the DCRV's discharge capacity is enough to protect the overpressure in the PHTS, and the SG tube integrity is maintained in a total loss of all heat accident

  15. Customization of RODOS 5.0 system for the assesment of a CANDU Cernavoda NPP nuclear accident scenario

    International Nuclear Information System (INIS)

    Mateescu, Gh.; Galeriu, D.; Slavnicu, D.; Vamanu, D.; Craciunescu, T.; Turcanu, C.; Melintescu, C.A.; Gheorghiu, D.; Gheorghiu, A.

    2003-01-01

    The RODOS expert system is designed to be run in real time and on-line for multiuser operation in local, regional and national nuclear emergency centers responsible for off-site nuclear emergency management. RODOS provides continuously updated, consistent, comprehensive and timely information as an input for making decisions at local, national and European scale, in early or late phase of an accident, for all types of actions and countermeasures in an emergency situation. For testing the customization of RODOS in prototype version 5.0 to Romanian conditions an accident scenario for CANDU reactor was considered. This accident scenario is the early reactor core disruption with hydrogen burning. For customization a more detailed geographic database was created and was updated according to the radioecological database for our country. The goal of testing is to assess the accident consequences in early phase and also the banning, processing and disposal of agricultural products. One figure presents the evacuation zone and a second one shows the iodine tablet intake (for children). Another application was the estimation of HTO concentration and OBT (organic bound tritium) in cow's milk and also the tritium ingestion dose, having in view that CANDU reactor is an important source of tritium in the case of an accidental release. Other important estimations regard the assessment of concentration of important radionuclides as Cs-137, I-131 and Sr-90 which has an important impact on organs like muscles, thyroid and bones. In case of countermeasures for long term it is very important to estimate the number of persons to be relocated as well as the relocation lapse. The system provides economic estimations corresponding to different countermeasure strategies regarding the costs of food consumption and decontamination activities of radioactively contaminated regions. RODOS is adapted to evaluate accident or incident consequences for all nuclear risk zones in Romania (Cernavoda

  16. Scenarios catalog for the graphical console for analysis of severe accidents visualization of OEs, NAEs and calculation of source term of the NPP-LV

    International Nuclear Information System (INIS)

    Sandoval V, S.; Mendoza R, M. E.; Tijerina S, F.; Garcia C, T.

    2016-09-01

    A nuclear power plant is operated at all times within the design criteria of structures, systems and components, and according to the operation technical specifications. For different areas of work of a nuclear power plant is necessary to carry out practices in which is useful to have the prediction of the thermo-hydraulic and radiological progression of scenarios that imply exceeding that design bases, even reaching the damage of the fuel in different degree. During the exercises and drills of the External Plan of Emergency Response, the projection of doses is done to exercise the different tasks of the plan. To make the projection of doses is required to have the radiological source term of the scenario on which is practiced. Because of this, was identified the convenience of having a catalog of scenarios for which the radiological source term was calculated. In 2004, a first version of the catalog was produced for a power of 2027 MW, and in 2011 the catalog was updated for extended power conditions, 2317 MW. Both versions were made using the severe accident simulator MAAP-3B. That catalog consists of a form and an optical storage device. The form contains tables and figures in which the characteristics of the scenario to be practiced are searched and the electronic files of the corresponding radiological source term are located in the storage device. Due to the recent development of the graphical console for analysis of severe accidents, visualization of OEs, NAEs and calculation of the source term for the nuclear power plant of Laguna Verde (NPP-LV) CoGrAAS, the catalog printed was replaced by an electronic catalog for the CoGrAAS. The new catalog retains the philosophy of the previous catalog, constituted by a wide collection of scenarios that involve different circumstances and phenomena, that can be used to practice different tasks during training exercises or simulacrums, and combined with the following advantages: the scenario selection is made from an

  17. Bioindication of total toxicity and teratogenicity of bottom deposits and soils from regions with different degree of the influence of the Chernobyl NPP accident using the developing embryos of grey sea urchins

    International Nuclear Information System (INIS)

    Grishchenko, O.M.; Chumak, V.K.; Grishchenko, S.O.; Rachins'kij, V.N.; Grishchenko, N.O.

    1992-01-01

    The changes (for 1983-90) in total toxicity and teratogenicity of bottom deposits in the Dnieper cascade and soil from some regions of the Ukraine with unequal degree of the influence of the Chernobyl NPP accident have been comparatively studied using developing embryos and larvae of grey sea urchins which are very sensitive to the unfavourable effect of radionuclides, many chemical technogenic factors. (author)

  18. Chernobyl'-92. Reports of the 3. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 1. Radiation monitoring. Migration of radionuclides in environment. Part 2

    International Nuclear Information System (INIS)

    Senin, E.V.

    1992-01-01

    Section Radiation monitoring comprises: atlas of area radioactive contamination as a result of the Chernobyl' NPP accident, state of automated radiation monitoring control system, hydrological monitoring, radiation situation in different areas, problems of radiation monitoring and protection of water objects, methods for determining radionuclidescontents, radiochemical mechanisms of radionuclide migration mobility in the Chernobyl' effluents, the results of investigations into migration of radionuclides in soils, landscapes, bottom depositions, in the soil-plant chain

  19. Modeling of spreading of the melted corium jet inside the pool of emergency heat removal during severe accidents at NPP

    Directory of Open Access Journals (Sweden)

    I. V. Kazachkov

    2012-03-01

    Full Text Available Important nuclear power safety problem in touch with modeling of melted corium jet spreading inside the coolant pool is considered in the paper. It appears by development of the passive protection systems against se-vere accidents. The non-linear mathematical developed model is presented for the jet under reactor vessel pool for one of the perspective passive protection systems and the results of its analysis and studies are given. The performed analysis and the results of the numerical simulation done on the base of the model have allowed estab-lishing the interesting behaviors of the system, which may be useful for the scientists, as well as the engineers-constructors of the passive protection systems against severe accidents.

  20. MORBIDITY RATE OF RETARDEDNESS AND CNS ORGANIC DISEASES AMONG THE POPULATION OF THE BRYANSK REGION BORN AFTER CHERNOBYL NPP ACCIDENT

    Directory of Open Access Journals (Sweden)

    G. M. Rumyantseva

    2010-01-01

    Full Text Available The article analyses dynamics of morbidity rate of oligophrenia and CNS organic diseases for the population born in the Bryansk region after the Chernobyl accident. Two regions were taken for the detailed analysis: contaminated - Novozybkov and not contaminated - Zhukov. 518 patient medical records were analyzed in the contaminated region and 359 ones in not contaminated. It is revealed that morbidity indicators for the radioactive contaminated territories are significantly higher than for the not contaminated territories.

  1. Structure of comorbid diseases inpatients with non-alcoholic fatty liver disease, exposed to ionizing radiation as a result of the Chornobyl NPP accident

    International Nuclear Information System (INIS)

    Gasanova, O.V.; Sarkyisova, E.O.; Ovsyannyikova, L.M.; And Others

    2014-01-01

    A significant amount of co-morbid pathology was found in all studied groups but III CG: at the average from 4.1 ± 0.4 diseases in II CG to 5.2 ± 0.2 in the main group of patients (p < 0.05), among which in 6.6-7.1 % of cases more than 10 diseases were established. The most common disorders were cardiovascular and cerebrovascular and endocrine diseases. Structure of comorbid pathology in NAFLD in the main study group differed from this in II CG by a significantly greater frequency of detection of cerebrovascular diseases (73.5 and 56 %, p < 0.05). As for features of the metabolic syndrome in Chornobyl accident sufferers essential hypertension (71.3 % ), discirculatory encephalopathy (48.5 %) and thyroid diseases (47.1 %) were more frequent than in II GC: correspondingly 58 % (p < 0.001), 28 %, (p < 0.01), and 30 %, (p < 0.05). Essential hypertension in only 35.7 % patients without NAFLD (I CG) was detected (71.3 % in the study group, p < 0.01), and chronic cerebrovascular insufficiency in 71.4 % (39.7 % in the study group, p < 0.01). Structure of comorbid pathology in NAFLD patients sufferers of the Chornobyl NPP accident was different both in a large number of identified diseases and nosological structure. The most common disorders were cardiovascular, cerebrovascular, and endocrine diseases. Significantly higher incidence of essential hypertension, vascular encephalopathy, and thyroid disease was determined

  2. Experience with a contact point (CP) for psychological and medical care after an NPP accident or another R/N disaster situation in Switzerland

    International Nuclear Information System (INIS)

    Baggenstos, M.A.; Frey, P.E.; Schmid, A.

    2006-01-01

    Mission The Swiss Federal Concept for Emergency Protection in the Vicinity of Nuclear Power Plants requires the preparation of a 'Contact Point' (C.P.) for psychological and medical care of the affected public in case of an accident in a nuclear power plant. Purpose The central questions, which during a release of radioactivity could cause anxiety within the population, are: - Have I come into contact with radioactive substances? - If so, what are the short-term and long-term radiological consequences? - How dangerous is the dose I have received? These questions are answered with the following procedures: - Examination of all persons arriving at the contact point with respect to radioactive contamination and, if necessary decontamination (showers). - Screening of the thyroid for the purpose of checking for incorporation of radioactive iodine and dose measurement in case screening is positive. - Answering of personal questions related to radioactivity and radiological consequences. - Information and advisory service concerning impact of radiation and possibilities of protective measures. Experience The Paper will discusses the experience from an exercise taken place 18./19. november 2005. In this exercise 100 players will be involved. The background of the exercise is a scenario taken from a federal exercise with a NPP. In addition to the direct support at the contact point a telephone hot line will be exercised. We expect lessons learned in man y areas of the management of psychological and medical care. (authors)

  3. The influence of biotic and abiotic factors on "1"3"7Cs accumulation in higher fungi after the accident at Chernobyl NPP

    International Nuclear Information System (INIS)

    Zarubina, N.

    2016-01-01

    Levels of soil contamination with "1"3"7Cs, the belonging of fungi to a certain ecological group, the localization depth of the main part of mycelium in soil are the primary factors influencing the value of "1"3"7Cs specific activity in higher fungi after the accident at Chernobyl NPP. It has been found that the value of "1"3"7Cs specific activity in fungi of one species could vary by more than 10 times during a vegetation period. A correlation between the changes of "1"3"7Cs content in fungi during the vegetation period and the amount of precipitates during various periods preceding the collection of samples has not been determined. An assumption has been proposed stating dependence between peculiarities of mycelium growth during the vegetation period and the changes of "1"3"7Cs specific activity in fungi. - Highlights: • Factors influencing on the "1"3"7Cs accumulation by higher fungi have been studied. • "1"3"7Cs specific activity levels in one species fungi could change to up to 10 times during a vegetation season. • A reliable linear dependence of "1"3"7Cs content in fungi on precipitate quantity has not been determined.

  4. Knowledge Management Learned from Decommissioning and Environmental Remediation after an Unexpected Radiological Contamination Occurred at Fukushima Dai-ichi NPP Accident

    International Nuclear Information System (INIS)

    Inoue, T.

    2016-01-01

    Full text: The Fukushima Dai-ichi Nuclear Power Plant (NPP) Accident resulted in severe damage of cores in units 1 to 3, and subsequently entailed not only contamination of facility but also widely-spread radiological contamination in environment due to the release of radioactive nuclides. Decommissioning activities will require at least 30–40 years with various stages of operation, such as contaminated water treatment, decontamination of reactor buildings, retrieval of spent fuel (SF) from SF pools, inspection of primary containment vessel (PCV) and reactor pressure vessel (RPV), and retrieval and further management of damaged fuel and melted debris. Especially, a water injection for core cooling is a pressing issue to stabilize the melted debris, which leads to produce a large amount of contaminated water. Environmental remediation is a crucial issue to return a normal life for local residents. On-site cleaning and off-site remediation produce various kinds and enormous amount of contaminated material with low to high radioactivity. Knowledge management of on-site and off-site issues over generation are critical to achieve the cleaning and remediation requiring a couple of decades. In addition, knowledge obtained through a long term-operation should be shared globally. (author

  5. Evaluation of containment peak pressure and structural response for a large-break loss-of-coolant accident in a VVER-440/213 NPP

    Energy Technology Data Exchange (ETDEWEB)

    Spencer, B.W.; Sienicki, J.J.; Kulak, R.F.; Pfeiffer, P.A. [Argonne National Lab., IL (United States); Voeroess, L.; Techy, Z. [VEIKI Inst. for Electric Power Research, Budapest (Hungary); Katona, T. [Paks Nuclear Power Plant (Hungary)

    1998-07-01

    A collaborative effort between US and Hungarian specialists was undertaken to investigate the response of a VVER-440/213-type NPP to a maximum design-basis accident, defined as a guillotine rupture with double-ended flow from the largest pipe (500 mm) in the reactor coolant system. Analyses were performed to evaluate the magnitude of the peak containment pressure and temperature for this event; additional analyses were performed to evaluate the ultimate strength capability of the containment. Separate cases were evaluated assuming 100% effectiveness of the bubbler-condenser pressure suppression system as well as zero effectiveness. The pipe break energy release conditions were evaluated from three sources: (1) FSAR release rate based on Soviet safety calculations, (2) RETRAN-03 analysis and (3) ATHLET analysis. The findings indicated that for 100% bubbler-condenser effectiveness the peak containment pressures were less than the containment design pressure of 0.25 MPa. For the BDBA case of zero effectiveness of the bubbler-condenser system, the peak pressures were less than the calculated containment failure pressure of 0.40 MPa absolute.

  6. Optimization of chronic obstructive pulmonary disease treatment in clean-up workers of the Chornobyl NPP accident in the remote period after irradiation

    International Nuclear Information System (INIS)

    Sushko, V.O.; Shvajko, L.Yi.; Bazika, K.D.; Ryazhs'ka, A.S.

    2015-01-01

    Studied 60 chronic obstructive pulmonary disease (COPD) patients before treatment and 1 year after from the beginning, who were randomly assigned to two groups: the first group of patients (32 persons) additionally was appointed long reception (6 months) combination Ambroxol (30 mg x 3 times per day) and Essenciale (600 mg x 3 times per day), in the second group (28 people) patients received only basic therapy. The doses of radiation exposure were 25-500 mSv. Were studied clinical, functional characteristics, the number of exacerbations. Low response to the basic COPD therapy were shown by clean-up workers of the Chornobyl NPP accident, which is defined by the absence of significant changes in lung function tests. Additional appointments to the basic treatment of COPD combination of Ambroxol (30 mg x 3 times per day) and Essenciale (600 mg x 3 times per day) within 6 months of the liquidators of the Chernobyl made it possible to reduce the frequency of exacerbations in 46.9% patients without significant improvement in lung function tests

  7. On closure strategy for 1-D thermohydraulics models and closure relationships of two-phase flows in simple and subchannel geometry for NPP accident conditions

    International Nuclear Information System (INIS)

    Kornienko, Y.; Kornienko, E.; Ninokata, H.

    2001-01-01

    One-dimensional mathematical models are extensively used in thermohydraulics assessment of Nuclear Power Plant (NPP) transients and accidents, because specifically 1-D system of the conservation laws allows to reduce computing time and required memory, especially in ''best estimate'' code calculations. This work is generalization of the well-known Zuber-Findley and Hancox-Nicoll methods for two-phase flow distribution parameters Cs taking into account the non-monotonous void fraction distribution in the transverse direction in terms of two superimposed monotonous profiles. The method is very useful in evaluating the saddle-shape void fraction profile effects. In this work two-phase flow distribution parameters Cs were developed for simple circular and rectangular pipes, and subchannel geometry in a rod bundle. Basic assumptions were power-mode approximations for describing the profiles of local volume flux density, phase velocity and temperature. The general analytical (quadrature) relationships for Cs were obtained and their 3-D illustrations are proposed. Also, we propose generalized formulation and simple approach to construct friction factor, heat and mass transfer coefficients within the gradient hypothesis and boundary layer assumptions. The contribution of momentum, heat and mass transfer as well as their sources and sinks in the channel cross-section are taken into account. In the same way, the friction factor, heat and mass transfer coefficients with the transversal and azimuthal variations being taken into account are proposed for subchannel geometry as well. (author)

  8. Personal dosimetry at the radiation accidents

    International Nuclear Information System (INIS)

    Perevoznikov, O.N.; Klyuchnikov, A.A.; Kanchenko, V.A.

    2007-01-01

    The radiation accidents of different types and the methods of the dosimetry used at the consequences liquidation are considered. The long-term experience of the population personal instrumental dosimetric control carrying out at the ChNPP accident consequences liquidation is widely covered in details. The concepts are stated out and the results are presented on the functioning of the created system for personal dose monitoring of the population of Ukraine irradiation. The use of the person radiation counters at the internal irradiation population and personal dose assessment is considered in details

  9. Instrumentation and equipment for monitoring and controlling NPP post-accident situations. Working material. Proceedings of a specialists' meeting held in Dimitrovgrad, Russian Federation, 12-15 September 1995

    International Nuclear Information System (INIS)

    1995-01-01

    The objectives of the Specialist's Meeting were: To provide an international forum for presentation and discussion on experience with instrumentation and equipment for monitoring and controlling NPP post-accident situations; to share experience on the design and improvements in the subject area; to identify and describe advanced features for safety and post-accident management improvements. In order to facilitate a structure discussion and not to omit important problem areas, papers on the following subjects were considered to be within the scope of the Specialist's Meeting: Analysis of existing post-accident instrumentation (in terms of range, qualification and redundancy) to support post-accident management. Requirements for post accident instrumentation and equipment - operating experience, regulations, standards; experience in upgrading of the existing instrumentation; instrumentation and equipment for emergency management systems (emergency rooms and national centers); post-accident computerized aids to assist operators; post-accident operating procedures; R and D in post-accident instrumentation, future trends. The present volume contains: (1) the papers presented by national delegates; (2) programme of the meeting; (3) description of the RIAR research facilities; and (4) list of participants. Refs, figs and tabs

  10. Retinal vascular pathology risk development in the irradiated at different ages as a result if Chornobyl NPP accident

    International Nuclear Information System (INIS)

    Fedyirko, P.A.; Babenko, T.F.; Doryichevs'ka, R.Yu.; Gar'kava, N.A.

    2015-01-01

    The object of the study was the state of the retinal vessels in 2,531 persons (1,948 evacuated from the city of Pripyat under the age of 20 and 583 exposed to radiation in utero as a result of the Chornobyl NPP disaster. The results of standardized ophthalmic examination conducted from 1993 to 2000 within the framework of Clinical and epidemiological registry are used for the analysis. The evacuees were subdivided into different age groups of the exposed to radiation. The cohort of control group formed corresponding age groups of the unirradiated control. Statistical analysis of the survey results was carried out using the free trial version of ''Open Epi 2.2.1'' software package. The results obtained revealed a significant prevalence of retinal vessels pathology in all groups. The difference in angiopathy prevalence in exposed in utero persons was significant compared to age control. The prevalence of retinal vascular pathology was also significantly higher in all groups of evacuees. Angiopathy prevalence was higher in the group exposed in utero and at the age of 8-12 years, and in the group of people who were exposed at the age of 4-7 years, the risk of angiopathy was lower. It is proved that the occurrence of distant radiation effects mainly depends on the age at which a person has undergone irradiation. It should be noted that all the other conditions were approximately the same. If working conditions of the persons who were exposed in utero or were aged 8 to 20 years when the Chornobyl disaster happened are connected with occupational radiation exposure it is necessary to take additional preventive measures

  11. RETINAL VASCULAR PATHOLOGY RISK DEVELOPMENT IN THE IRRADIATED AT DIFFERENT AGES AS A RESULT OF CHERNOBYL NPP ACCIDENT.

    Science.gov (United States)

    Fedirko, P A; Babenko, T F; Dorichevska, R Yu; Garkava, N A

    2015-12-01

    To assess the relationship between the age at which a person undergoes radiation exposure and risk of developing eye lesions (case study of the retinal angiopathy prevalence). The object of the study was the state of the retinal vessels in 2,531 persons (1,948 evacuated from the city of Pripyat under the age of 20 and 583 exposed to radiation in utero as a result of the Chernobyl NPP disaster. The results of standardized ophthalmic examination conducted from 1993 to 2000 within the framework of Clinical and epidemiological registry are used for the analysis. The evacuees were subdivided into different age groups of the exposed to radiation. The cohort of control group formed corresponding age groups of the unirradiated control. Statistical analysis of the survey results was carried out using the free trial version of «Open Epi 2.2.1» software package. The results obtained revealed a significant prevalence of retinal vessels pathology in all groups. The difference in angiopathy prevalence in exposed in utero persons was significant compared to age-control. The prevalence of retinal vascular pathology was also significantly higher in all groups of evacuees. Angiopathy prevalence was higher in the group exposed in utero and at the age of 8-12 years, and in the group of people who were exposed at the age of 4-7 years, the risk of angiopathy was lower. It is proved that the occurrence of distant radiation effects mainly depends on the age at which a person has undergone irradiation. It should be noted that all the other conditions were approximately the same. If working conditions of the persons who were exposed in utero or were aged 8 to 20 years when the Chernobyl disaster happened are connected with occupational radiation exposure it is necessary to take additional preventive measures. P. А. Fedirko, T. F. Babenko, R. Yu. Dorichevska, N. А. Garkava.

  12. The EC TACIS project 'Social impact of closing Chornobyl NPP' objectives, tasks and intended outcomes

    International Nuclear Information System (INIS)

    Schoen, A.

    2001-01-01

    Being part of the common activities of Slavutich and ChNPP, our EC TACIS project representatives already actively participated in the elaboration of the state programme aimed to ensure the social security of the ChNPP personnel and the population of Slavutich in the result of the final shut down of ChNPP

  13. Whole-body counter survey results 4 months after the Fukushima Dai-ichi NPP accident in Minamisoma City, Fukushima

    International Nuclear Information System (INIS)

    Hayano, Ryugo S; Watanabe, Yuni N; Nomura, Shuhei; Nemoto, Tsuyoshi; Tsubokura, Masaharu; Hanai, Tatsuo; Kumemoto, Yuki; Kowata, Satoshi; Oikawa, Tomoyoshi; Kanazawa, Yukio

    2014-01-01

    Using the first WBC unit installed in Fukushima Prefecture after the accident, the radiocesium body burdens of 566 high-risk residents of Minamisoma city were measured in July 2011 at the Minamisoma Municipal General Hospital. The analysis of the data was challenging because this chair-type, WBC unit, did not have sufficient shielding against background gamma rays and methods had to be developed to reliably compensate for the body-attenuated background radiation. Fortunately, data for repeated tests of hospital staff members using both the chair-type and well-shielded FASTSCAN WBC units, installed in September 2011, were available and could be used to check the validity of the analysis. The CEDs of all subjects, estimated under the assumption of acute inhalation in March 2011, were found to be less than 1 mSv. (paper)

  14. Peculiarities of non-malignant endocrine disease in the Chornobyl NPP accident survivors, and hormonal interaction role

    International Nuclear Information System (INIS)

    Kamyins'kij, O.V.

    2014-01-01

    Some hormonal interactions were identified in study subjects indicating the thyroid disease onset under radiation impact through insulin resistance at the background of adipose tissue excess followed by body mass index increase, elevation of serum C-peptide and leptin levels, and onset of lipid metabolic disorders. Significant increase of the incidence of thyroid disease (1.5-3-fold), diabetes mellitus (3-7-fold), pre-obesity and obesity (in 25.67 %), and metabolic syndrome (5-fold) vs. entire population of Ukraine was found in remote terms upon the accident. Intricate pathogenetic inter systemic hormonal interactions were identified pre- disposing to thyroid disease due to insulin resistance, accompanying hyperinsulinemia, increased body mass index and some other hormonal and biochemical factors

  15. Chernobyl'-88. Reports of the 1. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 3. Part 2. Predictions of the variation in environmental radioactivity and radiation doses at the accidental zone

    International Nuclear Information System (INIS)

    Ignatenko, E.I.

    1989-01-01

    Experimental and radiation-sanitary data on radiation situation in the 30-km accident zone at the Chernobyl' NPP are discussed. Doses of soil, vegetation and animals contamination in this region are estimated. Long-term predictions of radiation situation in the accident zone are made

  16. The weakening of cell protection as a result of the Chernobyl NPP accident recovery factors affect on liquidator's organism

    International Nuclear Information System (INIS)

    Zybina, N.; Dryguina, L.; Katashkova, G.

    1997-01-01

    The markers of oxidative stress as well as intracellular antioxidants (enzymatic and non- enzymatic) were studied in 100 Chernobyl accident recovery workers(liquidators). Hormone screening tests were carried out in 250 liquidators. All persons (mean age - 35 years) have got external irradiation dose from 2 to 30 cGr. Control group was selected from persons of same age having not participated in accident liquidation. The significant antioxidant imbalance was found. ROS inactivating enzymes deficiency was revealed in neutrofils, lymphocytes and alveolar macrophages (AM). For instance, superoxide dismutase(SOD) activity in liquidator's AM was 2,8±0,3 U/mg protein (4,1-±1,8 U/mg protein in controls, P<0,05). Catalase activity was also lower than in control group (P<0,05). The significant disorder of the thiol-disulfide turnover was revealed: depression of reduced glutathione by 1,71-±0,46 μmol/l (control: 3,15±-0,34 μtmol/l, P<0,05). The oxidative stress destructive action realized in the conditions of excessive production of ROS, while the antioxidant potential was diminished(P<0,05). The oxidative destruction of lipids and proteins was found to be induced by free radical action. TBARS level in alveolar macrophages of liquidators was more than three times higher compared to controls. Enhanced levels of protein carbonyl groups were found as well. The decrease of TT3 in liquidators was detected most frequently. In 19% liquidators examined, TT3 was below the reference value (0,8 ng/ml). The TT3 level was registered at the low limit of the reference range (0,8 ng/ml) in 18% of liquidators. ''Low T3'' syndrome may be considered as a cell protection weakening. All the cellular protective mechanisms take part in processes of DNA synthesis and repair, transcription and translation, cell respiration and metabolism. Significant impairment of the cellular protective systems in liquidators could be regarded as a base of persistent ''chromosomal pathology'' and imbalance of

  17. Gas phase chemistry and removal of CH3I during a severe accident

    International Nuclear Information System (INIS)

    Karhu, A.

    2001-01-01

    The purpose of this literature review was to gather valuable information on the behavior of methyl iodide on the gas phase during a severe accident. The potential of transition metals, especially silver and copper, to remove organic iodides from the gas streams was also studied. Transition metals are one of the most interesting groups in the context of iodine mitigation. For example silver is known to react intensively with iodine compounds. Silver is also relatively inert material and it is thermally stable. Copper is known to react with some radioiodine species. However, it is not reactive toward methyl iodide. In addition, it is oxidized to copper oxide under atmospheric conditions. This may limit the industrial use of copper.(au)

  18. Gas phase chemistry and removal of CH{sub 3}I during a severe accident

    Energy Technology Data Exchange (ETDEWEB)

    Karhu, A. [VTT. Energy, Esbo (Finland)

    2001-01-01

    The purpose of this literature review was to gather valuable information on the behavior of methyl iodide on the gas phase during a severe accident. The potential of transition metals, especially silver and copper, to remove organic iodides from the gas streams was also studied. Transition metals are one of the most interesting groups in the context of iodine mitigation. For example silver is known to react intensively with iodine compounds. Silver is also relatively inert material and it is thermally stable. Copper is known to react with some radioiodine species. However, it is not reactive toward methyl iodide. In addition, it is oxidized to copper oxide under atmospheric conditions. This may limit the industrial use of copper.(au)

  19. Psychology of NPP operation safety

    International Nuclear Information System (INIS)

    Tret'yakov, V.P.

    1993-01-01

    The book is devoted to psychologic investigations into different aspects of NPP operative personnel activities. The whole set of conditions on which successful and accident-free personnel operation depends, is analysed. Based on original engineering and socio-psychologic investigations complex psychologic support for NPP personnel and a system of training and upkeep of operative personnel skills are developed. The methods proposed have undergone a practical examination and proved their efficiency. 154 refs., 12 figs., 9 tabs

  20. Whole-body counter surveys of Miharu-town school children for four consecutive years after the Fukushima NPP accident

    International Nuclear Information System (INIS)

    Hayano, Ryugo S.; Tsubokura, Masaharu; Miyazaki, Makoto; Satou, Hideo; Sato, Katsumi; Masaki, Shin; Sakuma, Yu

    2015-01-01

    Comprehensive whole-body counter surveys of Miharu-town school children have been conducted for four consecutive years, in 2011-2014. This represents the only long-term sampling-bias-free study of its type conducted after the Fukushima Dai-ichi accident. For the first time in 2014, a new device called the Babyscan, which has a low "1"3"4"/"1"3"7Cs MDA of <50 Bq/body, was used to screen the children shorter than 130 cm. No child in this group was found to have detectable level of radiocesium. Using the MDAs, upper limits of daily intake of radiocesium were estimated for each child. For those screened with the Babyscan, the upper intake limits were found to be ≲1 Bq/day for "1"3"7Cs. Analysis of a questionnaire filled out by the children's parents regarding their food and water consumption shows that the majority of Miharu children regularly consume local and/or home-grown rice and vegetables. This however does not increase the body burden. (author)

  1. Whole-body counter surveys of Miharu-town school children for four consecutive years after the Fukushima NPP accident

    Science.gov (United States)

    Hayano, Ryugo S.; Tsubokura, Masaharu; Miyazaki, Makoto; Satou, Hideo; Sato, Katsumi; Masaki, Shin; Sakuma, Yu

    Comprehensive whole-body counter surveys of Miharu town school children have been conducted for four consecutive years, in 2011-2014. This represents the only long-term sampling-bias-free study of its type conducted after the Fukushima Dai-ichi accident. For the first time in 2014, a new device called the Babyscan, which has a low $^{134/137}$Cs MDA of $< 50$ Bq/body, was used to screen the children shorter than 130 cm. No child in this group was found to have detectable level of radiocesium. Using the MDAs, upper limits of daily intake of radiocesium were estimated for each child. For those screened with the Babyscan, the upper intake limits were found to be <1 Bq/day for $^{137}$Cs. Analysis of a questionnaire filled out by the children's parents regarding their food and water consumption shows that the majority of Miharu children regularly consume local and/or home-grown rice and vegetables. This however does not increase the body burden.

  2. Dynamic reliability and risk assessment of the accident localization system of the Ignalina NPP RBMK-1500 reactor

    International Nuclear Information System (INIS)

    Kopustinskas, V.; Augutis, J.; Rimkevicius, S.

    2005-01-01

    The paper presents reliability and risk analysis of the RBMK-1500 reactor accident localization system (ALS) (confinement), which prevents radioactive releases to the environment. Reliability of the system was estimated and compared by two methods: the conventional fault tree method and an innovative dynamic reliability model, based on stochastic differential equations. Frequency of radioactive release through ALS was also estimated. The results of the study indicate that conventional fault tree modeling techniques in this case apply high degree of conservatism in the system reliability estimates. One of the purposes of the ALS reliability study was to demonstrate advantages of the dynamic reliability analysis against the conventional fault/event tree methods. The Markovian framework to deal with dynamic aspects of system behavior is presented. Although not analyzed in detail, the framework is also capable of accounting for non-constant component failure rates. Computational methods are proposed to solve stochastic differential equations, including analytical solution, which is possible only for relatively small and simple systems. Other numerical methods, like Monte Carlo and numerical schemes of differential equations are analyzed and compared. The study is finalized with concluding remarks regarding both the studied system reliability and computational methods used

  3. Transfer of fallout radionuclides derived from Fukushima NPP accident: 1 year study on transfer of radionuclides through hydrological processes

    Science.gov (United States)

    Onda, Yuichi; Kato, Hiroaki; Patin, Jeremy; Yoshimura, Kazuya; Tsujimura, Maki; Wakahara, Taeko; Fukushima, Takehiko

    2013-04-01

    Previous experiences such as Chernobyl Nuclear Power Plant accident have confirmed that fallout radionuclides on the ground surface migrate through natural environment including soils and rivers. Therefore, in order to estimate future changes in radionuclide deposition, migration process of radionuclides in forests, soils, ground water, rivers should be monitored. However, such comprehensive studies on migration through forests, soils, ground water and rivers have not been conducted so far. Here, we present the following comprehensive investigation was conducted to confirm migration of radionuclides through natural environment including soils and rivers. 1)Study on depth distribution of radiocaesium in soils within forests, fields, and grassland 2)Confirmation of radionuclide distribution and investigation on migration in forests 3)Study on radionuclide migration due to soil erosion under different land use 4)Measurement of radionuclides entrained from natural environment including forests and soils 5)Investigation on radionuclide migration through soil water, ground water, stream water, spring water under different land use 6)Study on paddy-to-river transfer of radionuclides through suspended sediments 7)Study on river-to-ocean transfer of radionuclides via suspended sediments 8)Confirmation of radionuclide deposition in ponds and reservoirs

  4. 90Sr and 137Cs in the Black Sea after the Chernobyl NPP accident: inventories, balance and tracer applications

    International Nuclear Information System (INIS)

    Egorov, V.N.; Povinec, P.P.; Polikarpov, G.G.; Stokozov, N.A.; Gulin, S.B.; Kulebakina, L.G.; Osvath, I.

    1999-01-01

    The paper summarizes studies of the distributions of 90 Sr and 137 Cs in the water and sediments of the Black Sea carried out during a 10-year period following the 1986 accident at the Chernobyl Nuclear Power Plant. Its goal is to assess the temporal evolution of radionuclide inventories and balances and to evaluate the mixing of water masses and the sedimentation processes using man-made radionuclides as tracers. Using mathematical models and field data, mixing time-scales of 5, 16 and 24 years have been estimated, respectively, for the water layers of depths 0-50, 0-100 and 0-200 m. For the Central Basin the ventilation time of the lower pycnocline is estimated at 15-25 years. 137 Cs has been used to date shelf and deep-basin sediments, providing the history of chemical and radioactive pollution and of eutrophication during the past 50 years. (Copyright (c) 1999 Elsevier Science B.V., Amsterdam. All rights reserved.)

  5. Smart Sensing of the Aux. Feed-water Pump Performance in NPP Severe Accidents Using Advanced GMDH Method

    Energy Technology Data Exchange (ETDEWEB)

    No, Young Gyu; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    In order to develop and verify the models, a number of data obtained by simulating station black out (SBO) scenario for the optimized power reactor 1000 (OPR1000) using MARS code were used. Most of monitoring systems for component have been suggested by using the directly measured data. However, it is very difficult to acquire data related to safety-critical component' status. Therefore, it is necessary to develop the new method that combines the data-based equipped with learning system and data miming technique. Many data-based modeling methods have been applied successfully to nuclear engineering area, such as signal validation, plant diagnostics and event identification. Also, the data miming is the process of analyzing data from different perspectives and summarizing it into useful information. In this study, the smart sensing technique was developed using advanced group method of data handing (GMDH) model. The original GMDH is an inductive self organizing algebraic model. The advanced GMDH model is equipped with a fuzzy concept. The proposed advanced GMDH model enhances the original GMDH model by reducing the effect of outliers and noise. The advanced GMDH uses different weightings according to their importance which is specified by the fuzzy membership grade. The developed model was verified using SBO accident simulation data for the OPR1000 nuclear power plant acquired with MARS code. Also, the advanced GMDH model was trained using the simulated development data and verified with simulated test data. The development and test data sets were independent. The simulation results show that the performance of the developed advanced GMDH model was very satisfactory, as shown in Table 1. Therefore, if the developed model can be optimized using diverse and specific data, it will be possible to predict the performance of Aux. feed water pump accurately.

  6. Plutonium in the wood of natural trees in the near zone of the Chernobyl NPP.; Plutonij v drevesine zhivykh derev`ev blizhnej zony ChAEhS.

    Energy Technology Data Exchange (ETDEWEB)

    Kopejkin, V A [VNIIGEOLNERUD, Kazan` (Russian Federation)

    1994-12-31

    It was for the first time that the fact of radionuclides migration, particularly migration of plutonium in the wood of natural trees, was fixed in the near zone of the Chernobyl NPP. The data obtained show considerably quicker process of radioactive fall-out penetration than it was considered before.

  7. Radioactive wastes management of NPP

    International Nuclear Information System (INIS)

    Klyuchnikov, A.A.; Pazukhin, Eh.M.; Shigera, Yu. M.; Shigera, V.Yu.

    2005-01-01

    Modern knowledge in the field of radiation waste management on example of the most serious man-made accident at Chernobyl NPP are illuminated. This nuclear power plant that after accident in 1986 became in definite aspect an experimental scientific ground, includes all variety of problems which have to be solved by NPP personnel and specialists from scientific organizations. This book is aimed for large sphere of readers. It will be useful for students, engineers, specialists and those working in the field of nuclear power, ionizing source and radiation technology use for acquiring modern experience in nuclear material management

  8. Ignalina NPP Safety Analysis: Models and Results

    International Nuclear Information System (INIS)

    Uspuras, E.

    1999-01-01

    Research directions, linked to safety assessment of the Ignalina NPP, of the scientific safety analysis group are presented: Thermal-hydraulic analysis of accidents and operational transients; Thermal-hydraulic assessment of Ignalina NPP Accident Localization System and other compartments; Structural analysis of plant components, piping and other parts of Main Circulation Circuit; Assessment of RBMK-1500 reactor core and other. Models and main works carried out last year are described. (author)

  9. Distribution of 137Cs, 90Sr, 239+240Pu, 241Am and 230,232Th on the fractions of natural organic species soils of ChNPP alienation zone

    International Nuclear Information System (INIS)

    Odintsov, A.A.; Sazhenyuk, A.D.

    2003-01-01

    The experimental data determination of distribution 137 Cs, 90 Sr, 239+240 Pu, 241 Am 'Chernobyl' releases and 230 , 232 Th on the fraction of humic and fulvic acids sandy- podsolic, meadow and peaty soils taken in the exclusive zone ChNPP are presents. Soils organic matter was isolated by conventional alkali extraction (Turin's method). It was shown that, with depending of soils types 15-45 % 241 Am associate with fulvic acids. In all investigated types of soils 30 - 40 % 239+240 Pu connects with humic acids, as strong complexes. The distribution of environmental 230 , 232 Th and artificial 239+240 Pu on the fraction natural organic species is the same

  10. The fate of long - lived radionuclides 137Cs and 90Sr in the Black Sea after Chernobyl NPP accident: results of twenty - year observations

    International Nuclear Information System (INIS)

    Stokozov, N. A.; Egorov, V. N.; Polikarpov, G. G.; Mirzoeva, N. Y.; Gulin, S. B.

    2006-01-01

    The presentation summarizes studies of 1 37Cs and 9 0Sr pollution of the Black Sea Basin carried out by Institute of Biology of the Southern Seas during 1986-2005 following the Chernobyl NPP accident. Its goal was to assess inflows of 1 37Cs and 9 0Sr from the Dnieper and the Danube Rivers, outflow through the Bosphorus Strait, inventories in bottom sediments and temporary evolution of 1 37Cs and 9 0Sr inventories in the Black Sea water column. Besides, the temporary evolution of 1 37Cs and 9 0Sr profiles in the Black Sea deep-water basin was used to estimations of a large-scale vertical water mixing. It has been estimated that the atmospheric fall outs during the first days of May 1986 have deposited 1.7-2.4 PBq of 1 37Cs on the Black Sea surface (nearly 2% of total 1 37Cs release in the environment). Therefore, 1 37Cs inventory in the 0-50 m layer have increased by a factor of 6-10 and the total 1 37Cs inventory in the whole basin have increased at least by a factor of 2 in comparison with the pre-Chernobyl value - 1.4+/-0.3 PBq. 1 37Cs input from the Danube and the Dnieper Rivers was insignificant in comparison with short-term atmospheric fall outs. The results of observations and mathematical modelling are testified that in the surface layers 0-50 and 0-200 m of the Black Sea deep-water basin in 1986-2000 an exponential decreases of the 1 37Cs inventories with an effective half-lifes of 5-6 years and 9-13 years, respectively, have been observed. The process of vertical water mixing has been observed mainly in the 0-200 m layer. The contribution of Chernobyl-origin 9 0Sr from atmospheric fallout was estimated around in 0.1-0.3 PBq. Pre-accident 9 0Sr level nearly 20 Bq m - 3 was reached by 1988. At the same time, an active input of 9 0Sr from the Dnieper and Danube Rivers has been observed. The total amount of 9 0Sr delivered by the two rivers into the Black Sea was estimated to be nearly 0.1 PBq in the 1986-1995. Under conditions of insignificant river input

  11. Selection of NPP for Kazakhstan

    International Nuclear Information System (INIS)

    Zhotabaev, Zh.R.

    2003-01-01

    Commercial NPP for Kazakhstan should to meet to several main requirements: 1). Safety operation (accident probability not more than 10 -6 1/p. year). 2). High efficiency > 40 %. 3). Possibility of use for high-temperature chemistry and hydrogen production. 4). Possibility for manufacturing of considerable part of equipment in Kazakhstan. 5). Possibility for fuel production and reprocessing in Kazakhstan. 6). Independence from existence of large water-supply sources. Comparative analysis of several NPP with different reactors (WWR-1000, Candu, BREST, VG-400; graphite molten salt reactor) shows that NPP with the graphite molten salt reactor meets to all above requirements, but hydrogen production it is possible by more complete 4-stage technology, since coolant temperature is 800 Deg. C. The principle advantage is possibility of manufacturing of main equipment and fuel in Kazakhstan that reduce the cost of NPP construction and operation

  12. Training center of Rovenskaya NPP. The experience of creation

    International Nuclear Information System (INIS)

    Fedorov, O.M.; Aristov, B.N.

    1991-01-01

    Experience in creation of a teaching-training centre at the Rovno NPP, which uses means available at unified NPPs, at most is discussed. The centre hardware complex functions include the event filing and providing for user-friendly interface with NPP technical personnel under training. The system of personnel training at the Rovno NPP teaching-training centre gives an opportunity to analyze accidents and emergency conditions more completely and carefully. The taching analysis of failures and accidents by a NPP operators using the complex of the teaching-training centre hardware sufficiently improves knowledge of particular accidents

  13. ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

    International Nuclear Information System (INIS)

    Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

    2009-01-01

    Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

  14. ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

    International Nuclear Information System (INIS)

    Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

    2008-01-01

    Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

  15. Radiation state of environment in the 30-km zone of Chernobyl NPP, water objects

    International Nuclear Information System (INIS)

    Sukhoruchkin, A.K.

    1994-01-01

    The level of radioactivity in the zone of Chernobyl NPP before the accident is shown. The extremely high level of radioactive contamination produced by the release from the ChNPP at the accident declined as short-lived nuclides decayed. The aerial γ surveys of the 5 km zone of the ChNPP in October, 1986 and September, 1987 are shown. The radiation hygienic parameters of long-lived nuclides at the moment of release are presented. The main contribution to the dose in inhalation is expected from transuranium nuclides, and in ingestion, 90 Sr. The radiation situation in the 30 km zone is at present determined by 137 Cs, 90 Sr and transuranium nuclides, and such nuclide mixture is very unfavorable from the radiobiological point of view. The dosimetric monitoring of them is discussed. The soil contamination density in the 5 km zone is shown. The circumstances of the rich water resources in the region are explained, and the state of contamination is shown. The observation of radioactive contamination of the surface water of Pripyat River is described, and the results are shown. Much concern in the 30 km zone was aroused by the radiation state of groundwater at the places of the forced temporary burial of solid radioactive waste. The state of the cooling water pond in relation to Pripyat River is reported. (K.I.)

  16. Modelization of the initiator success of the accident of Fukushima Daiichi in the NPP of ZION by the code MAAP-5

    International Nuclear Information System (INIS)

    Kevin Fernandez, M.; Jimenez, G.; Batteira, P.

    2013-01-01

    The main objective of the project is the modeling of the accident with a code new in the industry, MAAP5, and in a different nuclear plant, as well as various parameters sensitivity analysis to assess their influence on the evolution of the accident. The paper presents the analysis of the evolution of the simulated accident, as well as the evaluation of different sensitivity analyses performed on different parameters influence on the evolution: pre-accident conditions, actions of operator, etc. Operator actions, not referred to in the emergency procedures, which could influence the behavior of the reactor vessel during severe accident progression were analyzed.

  17. Emergency preparedness at Ignalina NPP

    International Nuclear Information System (INIS)

    Kairys, A.

    1998-01-01

    Brief review of Ignalina NPP safety upgrading and personnel preparedness to act in cases of accidents is presented. Though great activities are performed in enhancing the plant operation safety, the Ignalina NPP management pays a lot of attention to preparedness for emergency elimination and take measures to stop emergency spreading. A new Ignalina NPP emergency preparedness plan was drawn up and became operational. It is the main document to carry out organizational, technical, medical, evacuation and other activities to protect plant personnel, population, the plant and the environment from accident consequences. Great assistance was rendered by Swedish experts in drawing this new emergency preparedness plan. The plan consists of 3 parts: general part, operative part and appendixes. The plan is applied to the Ignalina NPP personnel, Special and Fire Brigade and also to other contractor organizations personnel carrying out works at Ignalina NPP. There are set the following emergency classes: incident, emergency situation, alert, local emergency, general emergency. Separate intervention level corresponds to each emergency class. Overview of personnel training to act in case of an emergency is also presented

  18. Dukovany NPP operation

    International Nuclear Information System (INIS)

    Vlcek, Jaroslav

    2010-01-01

    The topics discussed include: Dukovany NPP among CEZ Group power plants; International missions at the plant; Plant operation results; and Strategic goals and challenges. Historical data are presented in the graphical form, such as the unit capacity factor, unplanned capability loss factor, unplanned automatic scrams, fuel reliability, industrial safety accident rate, collective radiation exposure, WANO index, power generation data, and maximum achievable power by the end of year. Also discussed were the company culture and human resources, maintenance, power uprate, and related phenomena. (P.A.)

  19. Expedition surveys of the sea water and atmospheric air radioactive contamination in the Russian Far Eastern coastal areas and in the North- Western Pacific in connection with accident at the 'Fukushima-1' NPP

    Energy Technology Data Exchange (ETDEWEB)

    Nikitin, Aleksandr; Shershakov, Viacheslav; Artemev, Georgii [Research and Production Association ' Typhoon' (RPA ' Typhoon' ), Obninsk, Kaluga Region (Russian Federation); Ramzaev, Valery [Ramzaev Saint-Petersburg Research Institute of Radiation Hygiene, Saint-Petersburg (Russian Federation); Osokin, Vladimir [V.G.Khlopin Radium institute, Saint-Petersburg (Russian Federation); Sevastianov, Aleksandr [Far Eastern Regional Hydrometeorological Research Institute, Vladivostok (Russian Federation)

    2014-07-01

    In accordance with decision of the Russian Federation Federal Service on Hydro-meteorology and Environmental Monitoring (Roshydromet) on assessment of the sea water and atmospheric air radioactive contamination in the Russian coastal areas of the Far East in connection with accident at the 'Fukushima-1' NPP in Japan, two radioecological expedition surveys were conducted onboard of research vessels of the Far Eastern Regional Hydro-meteorological Research Institute (FERHRI) of Roshydromet in the Sea of Japan and in the North-Western Pacific (in the area adjacent to Kurile Islands and in the Kuroshio current selected area (coordinates 36 deg. 00'- 39 deg. 33' n., 146 deg. 33'- 150 deg. 00' e.): first survey in April-May 2011, onboard R/V 'Pavel Gordienko', second survey in August-September 2012, onboard R/V 'Akademik Shokalsky'. Both surveys were conducted under the Russian Geographical Society patronage. The leading Russian institutions dealing with ensuring of population radiation safety and protection of environment from radioactive contamination were enlisted to investigations. The following main observations were performed during the surveys: constant measurement of gamma-radiation dose rate above the sea surface; twenty-four hour sampling of atmospheric aerosols, sea water sampling from the surface and deep water horizons with preliminary concentrating of radionuclides for onboard gamma-spectrometry and for subsequent transportation to the shore laboratories for further analysis. During the expeditions, a real-time data were received onboard of research vessels which characterize impact of input of radioactive products of the 'Fukushima-1' NPP accident on radioactive contamination of environment existed on that period (these are onboard estimates of {sup 137}Cs and {sup 134}Cs concentrations in the sea water samples and {sup 131}I, {sup 137}Cs, {sup 134}Cs content in atmospheric aerosol samples, data

  20. Chernobyl'-88. Reports of the 1. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 1. Radiation environment

    International Nuclear Information System (INIS)

    Ignatenko, E.I.

    1989-01-01

    Information on the contamination levels within the 30 km area and in the adjacent area after the Chernobyl'-4 reactor accident is presented. There are some data on reper isotope ratio which add some knowledge about the processes taking place in the reactor core after the reactor accident. The time-dependent background radiation variations for the first two years after the accident are demonstrated

  1. Belene NPP

    International Nuclear Information System (INIS)

    Tsvetanov, P.

    1990-01-01

    The book presents the main results of the studies of the Bulgarian Academy of Sciences (BAS) on the construction of a new nuclear power plant at Belene on the Danube river. The programme of the studies comprises five areas: the socio-economic and energy development and the necessity of the commissioning; a technical project and design level of the equipment (safety, radioactivity control, waste disposal and economic efficiency of the power plant); the seismic properties of the construction site; the corresponding risk and design features of the plant; the ecological impacts of the NPP and public opinion. The studies in the different areas have been carried out by independent teams, fully responsible for the formulated topical conclusions. The general opinion of the BAS voiced in the book is that the construction of Belene NPP is not sufficiently substantiated and is considered unacceptable. 94 refs., 53 fig., 56 tabs. (R.Ts.)

  2. Radionuclide localization at the Chernobyl' NPP territory

    International Nuclear Information System (INIS)

    Mamaev, L.A.; Galkin, G.A.; Khrabrov, S.L.; Polyakov, A.S.; Mikhejkin, S.V.

    1989-01-01

    Experience is generalized of using different dust suppression (DS) compounds during Chernobyl' accident consequence elimination. Polymer DS compounds were used at the NPP operating site; the compounds kept dust-like radioactive contaminations during 1-2 months. DS at the country was realized by means of the compound on base of latex. The conclusion is made that the DS measures improved radiation situation in the NPP zone. 7 refs

  3. Estimation and justification of permissible levels of Sr 90 in firewood and timber produced on the territories contaminated after the Chernobyl NPP accident

    International Nuclear Information System (INIS)

    Zabrodskij, V.N.; Bondar', Yu.I.; Sadchikov, V.I.; Kalinin, V.N.

    2014-01-01

    The permissible levels of Sr 90 in firewood and timber produced on the radioactively contaminated territory are calculated and justified. They are proposed to be used on the territories contaminated after the Chernobyl accident. (authors)

  4. Features of clinical signs of nervous and psychosomatic disorders in the Chernobyl' NPP personnel and human populations of affected regions at different stages of accident and its response

    International Nuclear Information System (INIS)

    Aleksandrovskij, Yu.A.; Tabachnikov, S.I.; Bebeshko, V.G.; Shchukin, B.P.; Rumyantseva, G.M.; Roslyakov, V.S.; Mel'nik, V.V.; Cherenkov, V.N.; Bero, M.P.; Mukhamadieva, R.A.

    1989-01-01

    Clinical signs of nervous and psychosomatic disorders in the Chernobyl' NPP personnel and persons taking part in the emergency response were analysed. Main stress factors for the personnel side by side with radiation hazard were the following ones: house loss, family separation, future uncertainties, etc. Singularity of labour under conditions of remaining threat for life and health, absence of information on the environmental radioactivity, unsatisfactory life conditions were in the first place for arrived persons. Analysis of determined psychopathological signs testifies to the prevalence of wide range of nervous disorders peculiar to natural calamities and disasters

  5. Conference: Nuclear Safety at the Ignalina NPP - Achievements and Challenges

    International Nuclear Information System (INIS)

    1999-01-01

    Brief description of conference which took place in Vilnius on 8-9 April 1999 is presented. The aim of the international conference is to review the work carried out, to evaluate its influence on the nuclear safety, to get acquainted with the safety system of the Ignalina NPP. On December 31, the Ignalina NPP celebrated its 15 year anniversary. During that period the Ignalina NPP has produced more than 182 billion kWh of electricity. Nuclear power is not only immense economic benefit but also a syndrome of fear of an atomic bomb and the Chernobyl accident that has formed over the years. Numerous comprehensive international studies have been performed at the Ignalina NPP. After the Chernobyl accident many steps have been taken to improve the safety of the Ignalina NPP. The introduced changes guaranteed that the void coefficient remained negative in all possible circumstances. The Ignalina NPP is intensively preparing for licensing of unit 1

  6. Enhanced safety features of CHASHMA NPP UNIT-2 to encounter selected severe accidents, various challenges involved to prove the adequacy of severe accidents prevention/mitigation measures and to write management guidelines with one possible solution to these challenges

    International Nuclear Information System (INIS)

    Iqbal, Z.; Minhaj, A.

    2007-01-01

    This paper describes enhanced safety features of Chashma Nuclear Power Plant Unit-2 (C-2), a 325 MWe PWR to encounter selected severe accidents and discusses various challenges involved to prove the adequacy of severe accidents encountering measures and to write severe accident management guidelines (SAMGs) in compliance with the recently introduced national regulations based on the new IAEA nuclear safety standards. C-2 is being built by China National Nuclear Corporation (CNNC) for Pakistan Atomic Energy Commission (PAEC). Its twin, Unit-1 (C-1) also a 325 MWe PWR, was commissioned in 2000. Nuclear power safety with reference to severe accidents should be treated as a global issue and therefore the developed countries should include the people of developing countries in nuclear power industry's various severe accidents based research and development programs. The implementation of this idea may also deliver few other useful and mutually beneficial byproducts. (author)

  7. Immune status of perpons taking part in accident effect elimination and personnel of the Chernobyl' NPP 30-km zone according to the data of 5-year monitoring

    International Nuclear Information System (INIS)

    Oradovskaya, I.V.

    1992-01-01

    Clinical-immunological surveillance of persons taking part in accident effect elimination realized 5 years later has shown that the most characteristic clinical symptocomplex for the persons examined remains the syndrome of increased fatiguability. Supression of the immune status cell link expressed in lowering the mean values of T-lymphocytes is revealed for the persons examined 5 years later. It may be supposed that the fifth year is the critical period in which T-cell immune deficits develop for more than one third of persons subjected to the effects of the complex of severe radiation accident factors. 5 refs.; 6 figs.; 4 tabs

  8. NPP Krsko small break LOCA analysis

    International Nuclear Information System (INIS)

    Mavko, B.; Petelin, S.; Peterlin, G.

    1987-01-01

    Parametric analysis of small break loss of coolant accident for the Krsko NPP was calculated by using RELAP5/MOD1 computer code. The model that was used in our calculations has been improved over several years and was previously tested in simulation (s) of start-up tests and known NPP Krsko transients. In our calculations we modelled automatic actions initiated by control, safety and protection systems. We also modelled the required operator actions as specified in emergency operating instructions. In small-break LOCA calculations, we varied break sizes in the cold leg. The influence of steam generator tube plugging on small break LOCA accidents was also analysed. (author)

  9. Role of insulin resistance and hypothyroidism in pathogenesis of obesity in adolescents born of parents exposed to ionizing radiation after the ChNPP accident

    International Nuclear Information System (INIS)

    Kopilova, O.V.; Stepanenko, O.A.; Myishchenko, L.P.; Tal'ko, V.V.

    2017-01-01

    The survey findings have shown that examination of 186 children aged from 12 to 17 who were born of parents evacuated out of 30km exclusion zone, citizens of the administered area, makes it possible to reveal increased risk of benign endocrine pathology (thyroid, impaired carbohydrates metabolism, obesity, hypothalamic syndrome) in adolescence with the signs of latent hormone dysfunction. In every other adolescent there is an interaction between impaired function of the thyroid gland (hypothyroidism) and present insulinemia and insulin resistance resulting in disturbance of fat metabolism. Progressing of overweight in adolescence is accompanied by significant metabolic disorders which can be a trigger in development of MSX. Resistance to insulin as well as peripheral resistance to thyroid hormones lead to metabolic disorders, one of which is obesity. Hormone disfunction, which result in impaired of carbohydrate and fat metabolism, can be a predictive criterion of development of diabetes mellitus of type II in future.

  10. Clinical characterization of [sexual function disorders obseved for men suffering of vegeto-vascular dystonia who participated in liquidating the consequences of ChNPP accident

    International Nuclear Information System (INIS)

    Gorbov, V.G.

    1992-01-01

    152 men (age ranging from 25 to 55) suffering of vegeto-vascular dystonia have been examined from the point of view of structure and clinical features of the sexual pathology as well as the role of autonomic nervous system in pathologenesis of sexual abnormalities. For all the patients sexual disorders manifested to diferent degrees have been disclosed. Risc factors of occurring sexual disorders; inflammation of epididymis sexual glands and gonads have been estimated. The influence of shift method of work and conjugal dysharmony on the risc factors has been studied. Chromic prostatitis is the most frequently occurring risc factor (45%). No direct correlation dependence of the sexual disorder gravity on the total radiation dose to which the patients were exposed has been observed. 11 refs.; 1 tab

  11. Peculiarities of gastrointestinal disease concomitant to heart connective tissue dysplasia in children born from persons exposed to ionizing radiation in childhood after the ChNPP accident

    International Nuclear Information System (INIS)

    Kondrashova, V.G.; Kolpakov, Yi.Je.; Vdovenko, V.Yu.; And Others

    2014-01-01

    UGITD namely chronic gastroduodenitis with typically concomitant involvement of several parts of digestive tract are most prevalent within all digestive system diseases in remote period upon the Chornobyl disaster in children born from persons exposed to ionizing radiation in a childhood. Presentation of UGITD occurs earlier in children suffering HCTDS with evident systemic pattern of organ and system injury along with an age. Refluxes of various nature and localization are the leading factors for UGITD onset in children suffering HCTDS. Thus a range of multidirectional tools of reflux disease prophylaxis is required for inclusion to the disease management

  12. Status and prospects of radioecological data base for State register of individuals exposed to radiation as a result of ChNPP accident

    International Nuclear Information System (INIS)

    Tsyb, A.F.; Pitkevich, V.A.; Duba, V.V.; Ivanov, V.K.

    1992-01-01

    Radiation ecology register for radioecological data base is being elaborated. The basic components of register are as follows: the basis of the initial documents according to districts and inhabitated localities; software for the data analysis and processing; software for implementation of physical models of radionuclide behaviour in the environment and absorbed dose formation; radioecological certificates (passports) for inhabitated localities and regions; software for evaluating the individual radiation loads induced by various radiation factors according to the requirements made by the Russian State medico-dosimetric register; data base. 2 refs.; 3 figs

  13. Method for retrospective estimation of absorbed dose in subsurface tissues when conducting works connected with the Chernobyl' NPP accident effect elimination (using experimental and calculated data)

    International Nuclear Information System (INIS)

    Panova, V.I.; Shaks, A.I.

    1992-01-01

    The method for retrospective estimation of doses in subsurface tissues at early time periods from the accident begin in the case, when gamma radiation dose rate values (radiation field cartogram) and a person irradiation conditions on contaminated territory (professional route) are known, is discussed

  14. Sensitivity analysis for assesed concentration of radioactivity eleased at accident of NPP; Analiza osetljivosti procene koncentracije radioaktivnosti oslobodjene u akcidentu NE

    Energy Technology Data Exchange (ETDEWEB)

    Lalovic, M [Fakultet tehbickih nauka, Novi Sad (Yugoslavia); Ninkovic, M M [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

    1988-07-01

    Sensitivity analysis for atmospheric model of UFOMOD accident consequence code is presented. Partial correlation coefficients are used as sensitivity measure to quantify and rank variation in consequences due to change in input parameter values. regression method is used, R{sup 2} is proportional to variation in consequences which can be explained by regression. Main contributors to assessed concentration variation are determined. (author)

  15. IPEEE Review of other external events of the NPP Asco

    International Nuclear Information System (INIS)

    Canadell, F.; Aleman, A.; Beltran, F.; Pifarre, D.; Hernandez, H.; Gasca, C.

    2011-01-01

    Within the process of maintaining and updating the risk analysis of the NPP Asco, results from the review of the vulnerability study of the plant against severe accidents caused by external success (Individual Plant Examination of External Events, IPEEE).

  16. Accident management on french PWRS

    International Nuclear Information System (INIS)

    Queniart, D.

    1990-06-01

    After a brief recall of French safety rationale, the reactor operation and severe accident management is given. The research and development aimed at developing accident management procedures and emergency organization in France for the case of a NPP accident are also given

  17. Safety analysis of accident localization system

    International Nuclear Information System (INIS)

    1999-01-01

    A complex safety analysis of accident localization system of Ignalina NPP was performed. Calculation results obtained, results of non-destruct ing testing and experimental data of reinforced concrete testing of buildings does not revealed deficiencies of buildings of accident localization system at unit 1 of Ignalina NPP. Calculations were performed using codes NEPTUNE, ALGOR, CONTAIN

  18. Site characterization techniques used in restoration of agricultural areas on the territory of the Russian Federation contaminated after the accident at the Chernobyl NPP

    International Nuclear Information System (INIS)

    Fesenko, S.V.; Alexakhin, R.M.; Sanzharova, N.I.

    2000-01-01

    The experience gained in the aftermath after the heavy radiation accidents shows the need for improvement in site characterisation techniques and methodology in order to provide a link between site characterisation and the selection of restoration strategies. This paper gives an overview of the site characterisation techniques used in restoration of contaminated agricultural lands on the territory of the Russian Federation. The approach used for site characterisation and selection of restoration strategies is described. The main site specific factors influencing the choice of restoration options are identified. Data on the efficiency of major restoration measures used for the remediation of agricultural lands after the Chernobyl Nuclear Power Plant and the Kyshtym accidents are given. A description of the decision support system FORCON, designed to simplify the selection of restoration options, is presented. (author)

  19. Seasonal variability of iodine and selenium in surface and groundwater as a factor that may contribute to iodine isotope balance in the thyroid gland and its irradiation in case of radioiodine contamination during accidents at the NPP

    Science.gov (United States)

    Korobova, Elena; Kolmykova, Lyudmila; Ryzhenko, Boris; Berezkin, Viktor; Saraeva, Anastasia

    2016-04-01

    Radioiodine release to the environment during the accident at the Chernobyl NPP led to the increased risk of the thyroid cancer cases within the contaminated areas, the effect being aggravated in conditions of stable iodine and selenium deficiency in local food chains. Although the drinking water iodine is usually believed to contribute not more than 10% to local diet, our estimations accounting of water content in other products and several regional studies (e.g. India and Australia) proved its portion to be at least twice as much. As radioiodine isotopes are short-lived, their absorption depends greatly on stable iodine and selenium sufficiency in thyroid gland in the first few days of contamination and seasonal variation of stable iodine and selenium in local sources of drinking water may be significant as modifying the resulting thyroid irradiation in different seasons of the year. The main goal of the study was to evaluate seasonal variation of levels of iodine and selenium in natural waters of the Bryansk region as a possible factor affecting the radioiodine intake by thyroid gland of animals and humans in case of radioiodine contamination during the accident. Seasonal I and Se concentration was measured in the years of 2014 and 2015 at 14 test points characterizing surface (river and lake) and drinking groundwater. Obtained data proved considerable seasonal variation of I and Se concentration in natural waters (3,7-8,1 μg/l and 0,04-0,4 μg/l respectively) related to physico-chemical water parameters, such as pH, Eh and fluctuations in concentration of dissolved organic matter. The widest I and Se seasonal variability was observed in surface and well waters, maximum I level being found in autumn at the end of vegetation period characterized by active I leaching from the decomposed organic residues by long lasting precipitations. The content of selenium in the surface waters during summer-autumn (0,06-0,3 μg/l) was higher than in spring (0,04-0,05

  20. AGNES - safety reassessment of Paks NPP

    International Nuclear Information System (INIS)

    Gado, J.

    1995-01-01

    The main goal of the AGNES (Advanced General and New Evaluation of Safety) project for the reassessment of the safety of Paks Nuclear Power Plant, Hungary, was to improve the safety culture of the technology at Paks. A report was prepared on the reassessment of the Paks NPP safety. The analysis was divided into four groups: systems analysis, analysis of design basis accidents, severe accident analysis, and level 1 probabilistic safety analysis. Proposed safety enhancement measures are discussed. (N.T.)

  1. Design safety improvements of Kozloduy NPP

    International Nuclear Information System (INIS)

    Hinovski, I.

    1999-01-01

    Design safety improvements of Kozloduy NPP, discussed in detail, are concerned with: primary circuit integrity; reactor pressure vessel integrity; primary coolant piping integrity; primary coolant overpressure protection; leak before break status; design basis accidents and transients; severe accident analysis; improvements of safety and support systems; containment/confinement leak tightness and strength; seismic safety improvements; WWER-1000 control rod insertion; upgrading and modernization of Units 5 and 6; Year 2000 problem

  2. Qinshan NPP large break LOCA safety analysis

    International Nuclear Information System (INIS)

    Shi Guobao; Tang Jiahuan; Zhou Quanfu; Wang Yangding

    1997-01-01

    Qinshan NPP is the first nuclear power plant in the mainland of China, a 300 MW(e) two-loop PWR. Large break LOCA is the design-basis accident of Qinshan NPP. Based on available computer codes, the own analysis method which complies with Appendix k of 10 CFR 50 has been established. The RELAP4/MOD7 code is employed for the calculations of blowdown, refill and reflood phase of the RCS respectively. The CONTEMPT-LT/028 code is used for the containment pressure and temperature analysis. The temperature transient in the hot rod is calculated using the FRAP-6T code. Conservative initial and functional assumptions were adopted during Qinshan NPP large break LOCA analysis. The results of the analysis show the applicable acceptance criteria for the loss-of-coolant accident are met

  3. Influence of radiolysis and gas-liquid partition of I-131 in accumulated water on late phase source terms at Fukushima NPP accident

    International Nuclear Information System (INIS)

    Hidaka, Akihide

    2014-01-01

    In the process of core cooling at Fukushima Daiichi nuclear power plants accident, large amount of contaminated water was accumulated in the basements of the reactor buildings at Units 1 to 4. The present study estimated the quantities of I-131 and Cs-137 in the water as of late March based on the press-opened data. The estimated ratios of I-131 and Cs-137 quantities to the core inventories are 0.51%, 0.85% at Unit 1, 74%, 38% at Unit 2 and 26%, 18% at Unit 3, respectively. According to the Henry's law, certain fraction of iodine in water could be released to atmosphere due to gas-liquid partition and contribute to increase in the release to environment. A lot of evaluations for I-131 release have been performed so far by severe accident codes such as MELCOR or the reverse estimation with atmospheric dispersion code such as SPEEDI using the monitoring data. The SPEEDI reverse predicted significant release until March 26 while no prediction in MELCOR after March 17. The present study showed that iodine release from accumulated water due to radiolytic conversion from I - to I 2 and gas-liquid partition of I 2 may explain the release between March 17 and 26. This strongly suggests a need for improvement of current MELCOR approach which treats the release only from containment breaks for several days after the core melt. The study also indicates that the release of radioactive iodine from accumulated water in the basements of reactor buildings could become a great concern for the consequence of Fukushima accident. (author)

  4. Simulations of the transport and deposition of 137Cs over Europe after the Chernobyl NPP accident: influence of varying emission-altitude and model horizontal and vertical resolution

    Science.gov (United States)

    Evangeliou, N.; Balkanski, Y.; Cozic, A.; Møller, A. P.

    2013-03-01

    The coupled model LMDzORINCA has been used to simulate the transport, wet and dry deposition of the radioactive tracer 137Cs after accidental releases. For that reason, two horizontal resolutions were deployed and used in the model, a regular grid of 2.5°×1.25°, and the same grid stretched over Europe to reach a resolution of 0.45°×0.51°. The vertical dimension is represented with two different resolutions, 19 and 39 levels, respectively, extending up to mesopause. Four different simulations are presented in this work; the first uses the regular grid over 19 vertical levels assuming that the emissions took place at the surface (RG19L(S)), the second also uses the regular grid over 19 vertical levels but realistic source injection heights (RG19L); in the third resolution the grid is regular and the vertical resolution 39 vertical levels (RG39L) and finally, it is extended to the stretched grid with 19 vertical levels (Z19L). The best choice for the model validation was the Chernobyl accident which occurred in Ukraine (ex-USSR) on 26 May 1986. This accident has been widely studied since 1986, and a large database has been created containing measurements of atmospheric activity concentration and total cumulative deposition for 137Cs from most of the European countries. According to the results, the performance of the model to predict the transport and deposition of the radioactive tracer was efficient and accurate presenting low biases in activity concentrations and deposition inventories, despite the large uncertainties on the intensity of the source released. However, the best agreement with observations was obtained using the highest horizontal resolution of the model (Z19L run). The model managed to predict the radioactive contamination in most of the European regions (similar to Atlas), and also the arrival times of the radioactive fallout. As regards to the vertical resolution, the largest biases were obtained for the 39 layers run due to the increase of

  5. NPP Krsko Containment Response Following Main Steam Line Break

    International Nuclear Information System (INIS)

    Spalj, S.; Grgic, D.; Cavlina, N.

    2000-01-01

    This paper presents the calculation of thermohydraulic environmental parameters (pressure and temperature) inside containment of Krsko NPP after postulated Main Steam Line Break (MSLB) accident. This analysis was done as a part of the ambient parameters specification in the frame of the NPP Krsko Equipment Qualification (EQ) project. The RELAP5/mod2 computer code was used for the determination of MSLB mass and energy release and computer code GOTHIC was used to calculate pressure and temperature profiles inside NPP Krsko containment. The analysis was performed for spectrum of break sizes to account for possible steam superheating during accidents with smaller break sizes. (author)

  6. Radioactive source management in Daya Bay NPP

    International Nuclear Information System (INIS)

    Mao Chun Yang

    2000-01-01

    'Small sources causes big accidents' had occurred worldwide many times. Radioactive source management in Nuclear Power Plant in very important for its safety record. This paper introduces the way and experience of radioactive source management in Daya Bay NPP from aspects of clarifying the responsibilities, centralizing the management of high radioactivity sources, work process management and experience feedback etc. (author)

  7. Decommissioning of NPP A-1

    International Nuclear Information System (INIS)

    Anon

    2009-01-01

    In this presentation the Operation history of A1 NPP, Project 'Decommissioning of A1 NPP' - I stage, Project 'Decommissioning of A1 NPP ' - II stage and Next stages of Project 'Decommissioning of A1 NPP ' are discussed.

  8. Improvement of radiological consequence estimation methodologies for NPP accidents in the ARGOS and RODOS decision support systems through consideration of contaminant physico-chemical forms

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, K.G.; Roos, P. [Technical University of Denmark - DTU (Denmark); Lind, O.C.; Salbu, B. [Norwegian University of Life Sciences/CERAD - NMBU (Norway); Bujan, A.; Duranova, T. [VUJE, Inc. (Slovakia); Ikonomopoulos, A.; Andronopoulos, S. [National Centre for Scientific Research ' Demokritos' (Greece)

    2014-07-01

    The European standard computerized decision support systems RODOS and ARGOS, which are integrated in the operational nuclear emergency preparedness in practically all European countries, as well as in a range of non-European countries, are highly valuable tools for radiological consequence estimation, e.g., in connection with planning and exercising as well as in justification and optimization of intervention strategies. Differences between the Chernobyl and Fukushima accident atmospheric release source terms have demonstrated that differences in release conditions and processes may lead to very different degrees of volatilization of some radionuclides. Also the physico-chemical properties of radionuclides released can depend strongly on the release process. An example from the Chernobyl accident of the significance of this is that strontium particles released in the fire were oxidized and thus generally physico-chemically different from those released during the preceding explosion. This is reflected in the very different environmental mobility of the two groups of particles. The initial elemental matrix characteristics of the contaminants, as well as environmental parameters like pH, determine for instance the particle dissolution time functions, and thus the environmental mobility and potential for uptake in living organisms. As ICRP recommends optimization of intervention according to residual dose, it is crucial to estimate long term dose contributions adequately. In the EURATOM FP7 project PREPARE, an effort is made to integrate physico-chemical forms of contaminants in scenario-specific source term determination, thereby enabling consideration of influences on atmospheric dispersion/deposition, post-deposition migration, and effectiveness of countermeasure implementation. The first step in this context was to investigate, based on available experience, the important physico-chemical properties of radio-contaminants that might potentially be released to the

  9. Remediation activities wrestling with environmental pollution and radwaste generated by the Fukushima Daiichi NPP accident due to the Tohoku district-off the pacific ocean

    International Nuclear Information System (INIS)

    Kawanishi, Motoi; Fujitsuka, Tetsuro; Yoshihara, Koichi; Katsumi, Takeshi; Tochiyama, Osamu

    2013-01-01

    Based on the lectures and panel discussions 'Radioactive waste countermeasures and the role of civil engineering technology' on the occasion of 3rd year of the Great East Japan Earthquake, March 11, 2011, hosted by the Japan Society of Civil Engineers, the paper summarizes remediation activities reported during the seminar. Radioactive materials contaminated area due to the Fukushima Daiichi Nuclear Power Plant accident from the Department of Environment, endeavors for setting-up of temporary storage facilities for the decontaminated soils and solid wastes, present status of roadmap toward the decommissioning of the Fukushima Daiichi Plants from the Japanese Government and Tokyo Electric Power Co. were presented followed by expectations of civil engineers cooperation. (S. Ohno)

  10. Use of computer aids including expert systems to enhance diagnosis of NPP safety status and operator response. VDU displays in accidents - Interact

    International Nuclear Information System (INIS)

    Humble, P.; Welbourne, D.

    1998-01-01

    This report describes NNC development of a demonstration concept called Interact of Visual Display Unit (VDU) displays, integrating on-screen control of plant actions. Most plant vendors now propose on-screen control and it is being included on some plants. The integration of Station Operating Instructions (SOI) into VDU presentation of plants is being developed rapidly. With on-screen control, SOIs can be displayed with control targets able to initiate plant control, directly as called for in the SOIs. Interact displays information and control options, using a cursor to simulate on-screen display and plant control. The displays show a method which integrates soft control and SOI information into a single unified presentation. They simulate the SOI for an accident, on-screen, with simulated inserted plant values

  11. Mochovce NPP simulator

    International Nuclear Information System (INIS)

    Ziakova, M.

    1998-01-01

    Mochovce NPP simulator basic features and detailed description of its characteristics are presented with its performance, certification and application for training of NPP operators as well as the training scenario

  12. Current status of Chernobyl NPP decommissioning

    International Nuclear Information System (INIS)

    2009-01-01

    Strategy of Chernobyl NPP decommissioning with the decommissioning license 2002-2064 is presented. The main activities at the stage of ChNPP units shutdown (2002 - 2012) are: units maintenance in safe state; decommissioning infrastructure construction; unloading of SNF – main activity determining the stage duration; systems and elements final shutdown; decommissioning life-support systems reconstruction; Comprehensive engineering and radiation survey (CERS); dismantling of the reactor facilities external equipment; removal of RAW from units; decommissioning documentation development. The decommissioning activities main results are presented

  13. Chernobyl'-88. Reports of the 1. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 3. Part 1. Predictions of the variation in environmental radioactivity and radiation doses at the accidental zone

    International Nuclear Information System (INIS)

    Ignatenko, E.I.

    1989-01-01

    Information on the prediction of environmental radioactivity in case of general accident at NPP, at reactor site and external zone was presented. Attention was also paid to the prediction of subterranean and ground water contamination, to the modelling and prediction of environmental radioactivity in the Pripyat river water reservoirs, to the population cytogenetic examination, to the prediction of forest state. Data on the realization of radiation monitoring were presented. Features of the modern forms of realization of prevention and correction of neurotic and psychosomatic disorders, rapid methods for the diagnosis of personnel psychophysical state, problems of the prediction of radiation doses to personnel of main Chernobyl' NPP shops and to population in case of its rerelocation in 30-km zone

  14. Cs-137 Concentration in Seawater from the Gulf of Thailand and the Andaman Sea and Radiation Doses in Marine Biota After the Fukushima Dai-ichi NPP Accident

    International Nuclear Information System (INIS)

    Tumnoi, Y.; Nakkaew, N.; Khrautongkieo, C.; Udomsomporn, S.

    2014-01-01

    radiological threat caused by the FDNPP accident.

  15. CONTENT OF CS-137 IN HOMEMADE PRESERVES OF MUSHROOMS PICKED IN 2014 BY LOCAL RESIDENTS IN AREAS AFFECTED BY RADIOACTIVE CONTAMINATION AFTER CHERNOBYL NPP ACCIDENT

    Directory of Open Access Journals (Sweden)

    K. V. Varfolomeeva

    2015-01-01

    Full Text Available The article presents results of the study made in 2014 on evaluation of the content of Cs-137 in different homemade dried and pickled mushrooms picked by residents of most contaminated areas of the Bryansk region. The aim of the study was to evaluate actual content levels of Cs-137 in homemade preserves of dried and pickled mushrooms picked in the Bryansk region areas with high level of radioactive contamination after Chernobyl accident. Sampling was conducted in residential settlements in proximity to most visited forest areas located at different distances to residential settlements in the range from 0.3 to 5 kilometers, with different forest types, with different soil surface contamination density by Cs-137 in the range from 33 to 944 kBq/m2 (Tentative levels of surface contamination of forest soil are evaluated based on the results of gammaspectrometry measurements in soil samples. The sampling was done at voluntary consent of local residents. In the frameworks of the research in ten settlements with 6112 residents altogether 25 samples were selected (8 samples of dried and 17 of pickled mushrooms.The analyses of study results resulted in the following conclusions: specific activity in samples of different kinds of dry and pickled mushrooms picked by residents of south-west areas of the Bryansk region vary in broad range from 32 to 34000 Bq/kg. The most part of homemade preserves of dried and pickled mushrooms of the local residents exceeds normative levels of permissible mushroom contamination. Cs-137 content in pickled mushrooms is not explicitly dependent on the level of soil surface contamination whereas specific activity of dry mushrooms increases along with the level of surface contamination increase. In the process of mushroom pickling, the additional reduction of Cs-137 content is observed: from 17% to 67% which averages to 37%. Due to the gradual reduction of transfer coefficients for Cs-137 into forest mushrooms and significant

  16. Safety reassessment of the Paks NPP (the AGNES project)

    Energy Technology Data Exchange (ETDEWEB)

    Gado, J [Hungarian Academy of Sciences, Budapest (Hungary). Central Research Inst. for Physics; Bajsz, J; Cserhati, A; Elter, J [Paksi Atomeroemue Vallalat, Paks (Hungary); Hollo, E [Energiagazdalkodasi Intezet, Budapest (Hungary); Kovacs, K [EROTERV Engineering and Contractor Co (Hungary); Maroti, L [Hungarian Academy of Sciences, Budapest (Hungary). Central Research Inst. for Physics; Miko, S [Paksi Atomeroemue Vallalat, Paks (Hungary); Techy, Z [Energiagazdalkodasi Intezet, Budapest (Hungary); Vidovszky, I [Hungarian Academy of Sciences, Budapest (Hungary). Central Research Inst. for Physics

    1996-12-31

    The reassessment of the Paks NPP safety according to internationally recognized criteria of the Advanced General and New Evaluation of Safety (AGNES) project is outlined. The Paks NPP consists of four WWER-440/V-213 units. The following groups of analysis have been performed: system analysis and description; analysis of design basis accidents; severe accidents analysis; level 1 probabilistic safety analysis. Postulated accidents (PA) and Anticipated Operational Occurrences (AOO) are estimated in detail for the following initiating events: increase/decrease in secondary heat removal; decrease in primary coolant inventory; increase/decrease of reactor coolant inventory; reactivity and power distribution anomalies; analysis of transients with the failure of reactor scram (ATWS); pressurized thermal shock analyses. Severe accident analysis was made for the accidents on in-vessel phase and containment phase, for radioactive release and for accident management.

  17. Safety reassessment of the Paks NPP (the AGNES project)

    International Nuclear Information System (INIS)

    Gado, J.; Hollo, E.; Kovacs, K.; Maroti, L.; Techy, Z.; Vidovszky, I.

    1995-01-01

    The reassessment of the Paks NPP safety according to internationally recognized criteria of the Advanced General and New Evaluation of Safety (AGNES) project is outlined. The Paks NPP consists of four WWER-440/V-213 units. The following groups of analysis have been performed: system analysis and description; analysis of design basis accidents; severe accidents analysis; level 1 probabilistic safety analysis. Postulated accidents (PA) and Anticipated Operational Occurrences (AOO) are estimated in detail for the following initiating events: increase/decrease in secondary heat removal; decrease in primary coolant inventory; increase/decrease of reactor coolant inventory; reactivity and power distribution anomalies; analysis of transients with the failure of reactor scram (ATWS); pressurized thermal shock analyses. Severe accident analysis was made for the accidents on in-vessel phase and containment phase, for radioactive release and for accident management

  18. Dissemination of Knowledge about NPP Instrumentation and Control Systems

    International Nuclear Information System (INIS)

    Yastrebenetsky, M.

    2016-01-01

    Full text: Instrumentation and control (I&C) systems are the most variable part in the nuclear power plants (NPP) comparatively with any other NPP systems. This statement is connected with the wide use of computers, rapid changes in information technologies, with the appearance of new computer complex electronic components, e.g., field programmable gate arrays (FPGA) and with appropriate point of their insertion into NPP I&C life cycle. The changes in NPP I&C systems require the dissemination of the knowledge about these systems. Lessons after Fukushima accident increase necessity of these actions. The elaboration and following dissemination of this knowledge took place in different directions: • Writing and issue of three new books about NPP I&C systems for specialists and for students which were issued in Ukrainian and USA public houses (the last book was issued in 2014); • Organization of five international scientific technical conferences, devoted to NPP I&C safety problems; • Elaboration of national (Ukrainian) standards and regulations pertaining to safety important NPP I&C systems (the last standard was issued in 2015) and participation in elaboration of international standards; • Lecturing for university students, NPP specialists and I&C designers. These actions in all directions are added to IAEA activity in the area NPP I&C systems (e.g., IAEA NP-T-3.12 “Core Knowledge on I&C systems in NPP”). (author

  19. Cytohematological indices of cattle adaptation to the chronic radiation effect in the exclusion zone of the Chernobyl NPP.; Tsitogematologicheskie pokazateli adaptatsii u krupnogo rogatogo skota pri khronicheskom radiatsionnom vozdejstvii v Zone otchuzhdeniya ChAEhS.

    Energy Technology Data Exchange (ETDEWEB)

    Panchenko, N A; Filimonov, I S; Zagorujko, E E; Gashchak, S P; Korisheva, A P [Myizhgaluzevij Naukovo-Tekhnyichnij Tsentr ` ` Ukrittya ` ` , Natsyional` na Akademyiya Nauk Ukrayini, Chornobil` (Ukraine); [Nauchno-Proizvodstvennoe Ob` ` edinenie Pripyat` , Chernobyl (Ukraine)

    1994-12-31

    Peripheral blood cells have been examined in cattle from the experimental farm in the 10 km zone of the Chernobyl NPP. With that aim 25 animals of different age groups and generations were investigation. Appearance of heteropholic granulocytes and << specific >> basophilic cells which heterogeneity is explained by their morphological and functional attribution has been observed.

  20. Comparative modeling analyses of Cs-137 fate in the rivers impacted by Chernobyl and Fukushima accidents

    Energy Technology Data Exchange (ETDEWEB)

    Zheleznyak, M.; Kivva, S. [Institute of Environmental Radioactivity, Fukushima University (Japan)

    2014-07-01

    The consequences of two largest nuclear accidents of the last decades - at Chernobyl Nuclear Power Plant (ChNPP) (1986) and at Fukushima Daiichi NPP (FDNPP) (2011) clearly demonstrated that radioactive contamination of water bodies in vicinity of NPP and on the waterways from it, e.g., river- reservoir water after Chernobyl accident and rivers and coastal marine waters after Fukushima accident, in the both cases have been one of the main sources of the public concerns on the accident consequences. The higher weight of water contamination in public perception of the accidents consequences in comparison with the real fraction of doses via aquatic pathways in comparison with other dose components is a specificity of public perception of environmental contamination. This psychological phenomenon that was confirmed after these accidents provides supplementary arguments that the reliable simulation and prediction of the radionuclide dynamics in water and sediments is important part of the post-accidental radioecological research. The purpose of the research is to use the experience of the modeling activities f conducted for the past more than 25 years within the Chernobyl affected Pripyat River and Dnieper River watershed as also data of the new monitoring studies in Japan of Abukuma River (largest in the region - the watershed area is 5400 km{sup 2}), Kuchibuto River, Uta River, Niita River, Natsui River, Same River, as also of the studies on the specific of the 'water-sediment' {sup 137}Cs exchanges in this area to refine the 1-D model RIVTOX and 2-D model COASTOX for the increasing of the predictive power of the modeling technologies. The results of the modeling studies are applied for more accurate prediction of water/sediment radionuclide contamination of rivers and reservoirs in the Fukushima Prefecture and for the comparative analyses of the efficiency of the of the post -accidental measures to diminish the contamination of the water bodies. Document

  1. ORSEC technological risks, Blayais NPP

    International Nuclear Information System (INIS)

    2016-01-01

    The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Blayais NPP (Gironde, France)

  2. The psychological background about human error and safety in NPP

    International Nuclear Information System (INIS)

    Zhang Li

    1992-01-01

    A human error is one of the factors which cause an accident in NPP. The in-situ psychological background plays an important role in inducing it. The author analyzes the structure of one's psychological background when one is at work, and gives a few examples of typical psychological background resulting in human errors. Finally it points out that the fundamental way to eliminate the unfavourable psychological background of safety production is to establish the safety culture in NPP along with its characteristics

  3. Decommissioning of Brennilis NPP

    International Nuclear Information System (INIS)

    Baize, Jean-Marc

    1998-01-01

    This EDF press communique give information related to the decommissioning of the Brennilis NPP. The following five items are developed in this report: 1. the level-2 decommissioning operations at the Brennilis NPP; 2. the Brennilis NPP, a pilot operation from the commissioning up to the decommissioning; 3. history of the Brennilis NPP decommissioning; 4. the types of radioactive wastes generated by the Brennilis NPP decommissioning; 5. the Brennilis NPP - a yard management as a function of the wastes. The document contains also seven appendices addressing the following subjects: 1. the share of decommissioning assigned to EDF and the decommissioning steps; 2. the EDF installations in course of decommissioning; 3. the CEA decommissioned installations or in course of decommissioning; 4. regulations; 5. costs; 6. waste management - principles; 7. data on the decommissioning yard

  4. NPP life management (abstracts)

    International Nuclear Information System (INIS)

    Litvinskij, L.L.; Barbashev, S.V.

    2002-01-01

    Abstracts of the papers presented at the International conference of the Ukrainian Nuclear Society 'NPP Life Management'. The following problems are considered: modernization of the NPP; NPP life management; waste and spent nuclear fuel management; decommissioning issues; control systems (including radiation and ecological control systems); information and control systems; legal and regulatory framework. State nuclear regulatory control; PR in nuclear power; training of personnel; economics of nuclear power engineering

  5. Accident management approach in Armenia

    International Nuclear Information System (INIS)

    Ghazaryan, K.

    1999-01-01

    In this lecture the accident management approach in Armenian NPP (ANPP) Unit 2 is described. List of BDBAs had been developed by OKB Gydropress in 1994. 13 accident sequences were included in this list. The relevant analyses had been performed in VNIIAES and the 'Guidelines on operator actions for beyond design basis accident (BDBA) management at ANPP Unit 2' had been prepared. These instructions are discussed

  6. Certain results and problems of experimental retrospective radiation monitoring in the estrangement zone of the Chernobyl NPP.; Nekotorye rezul`taty i problemy ehksperimental`noj retrospektivnoj dozimetrii v Zone otchuzhdeniya ChAEhS.

    Energy Technology Data Exchange (ETDEWEB)

    Bar` yakhtar, V G; Bugaj, A A; Gajchenko, V A; Koval` , G N; Proskura, N I [AN Ukrainskoj SSR, Kiev (Ukraine). Inst. Poluprovodnikov; [Admyinyistratsyiya zoni vyidchuzhennya, Chornobil` (Ukraine)

    1994-12-31

    Experimental methods of retrospective radiation monitoring in the estrangement zone of the Chernobyl NPP are described. It is shown that the method of thermoluminescence of quartz particles as well as the method of electron paramagnetic resonance of tooth enamel may be applied both to verify theoretical designs and experimental estimates and to accumulate experimental data on the most interesting and typical cases of accidental irradiation.

  7. Robustness of Electrical Systems of Nuclear Power Plants in Light of the Fukushima Daiichi Accident (ROBELSYS). Workshop Proceedings, Paris, France, 1-4 April 2014 - Robustness of Electrical Systems of NPP's in Light of the Fukushima Daiichi Accident. ROBELSYS Workshop Proceedings

    International Nuclear Information System (INIS)

    2015-01-01

    The March 2011 accident at Fukushima Daiichi triggered discussions about the significance of electrical power hazards and their treatment in safety analyses. In order to address these issues and provide relevant conclusions and recommendations to CSNI and CNRA, the Robustness in Electrical Systems (ROBELSYS) Technical Working Group was established in 2012 under the leadership of the Institut de Radioprotection et de Surete Nucleaire (IRSN) of France. The purpose of the ROBELSYS Technical Working Group was to organize an international workshop to identify and discuss the lessons learned from the Fukushima Daiichi accident. The workshop was focused on the provisions taken by various countries concerning national requirements and modifications to the plant designs in order to enhance the robustness of electrical systems, especially the protection against extreme external hazards. The ROBELSYS workshop was held at the OECD Conference Centre in Paris in April 1-4, 2014. A total of 105 participants attended the workshop representing industry and government organisations from 25 countries, as well as international organisations. A total of 34 technical presentations were given in seven sessions as follows: - 1: National Programmes on Evolution of Onsite and Offsite Electric Power Systems; - 2: Role of Electric Power in Severe Accident Management; - 3: Requirements for Robustness of Onsite Electric Power Systems; - 4: Simulation of Transients within NPP Plant Distribution Systems; - 5: Requirements for Equipment Used for Emergency Response; - 6: Margin Assessments for Modern Power Electronics; - 7: Digital Components in Power Systems. Items addressed in the workshop included: - Review of the lessons learned from the Fukushima accident concerning the robustness of electrical systems; - Review of the provisions already taken or planned after the Fukushima accident, regarding the sources, the distribution systems and the loads, and documenting the technical basis for these

  8. Robustness of Electrical Systems of Nuclear Power Plants in Light of the Fukushima Daiichi Accident (ROBELSYS). Workshop Proceedings, Paris, France, 1-4 April 2014. Appendix 2 (Cont'd) and Appendix 3 - Robustness of Electrical Systems of NPP's in Light of the Fukushima Daiichi Accident. ROBELSYS Workshop Proceedings. Appendices 2 and 3

    International Nuclear Information System (INIS)

    2015-01-01

    The March 2011 accident at Fukushima Daiichi triggered discussions about the significance of electrical power hazards and their treatment in safety analyses. In order to address these issues and provide relevant conclusions and recommendations to CSNI and CNRA, the Robustness in Electrical Systems (ROBELSYS) Technical Working Group was established in 2012 under the leadership of the Institut de Radioprotection et de Surete Nucleaire (IRSN) of France. The purpose of the ROBELSYS Technical Working Group was to organize an international workshop to identify and discuss the lessons learned from the Fukushima Daiichi accident. The workshop was focused on the provisions taken by various countries concerning national requirements and modifications to the plant designs in order to enhance the robustness of electrical systems, especially the protection against extreme external hazards. The ROBELSYS workshop was held at the OECD Conference Centre in Paris in April 1-4, 2014. A total of 105 participants attended the workshop representing industry and government organisations from 25 countries, as well as international organisations. A total of 34 technical presentations were given in seven sessions as follows: - 1: National Programmes on Evolution of Onsite and Offsite Electric Power Systems; - 2: Role of Electric Power in Severe Accident Management; - 3: Requirements for Robustness of Onsite Electric Power Systems; - 4: Simulation of Transients within NPP Plant Distribution Systems; - 5: Requirements for Equipment Used for Emergency Response; - 6: Margin Assessments for Modern Power Electronics; - 7: Digital Components in Power Systems. Items addressed in the workshop included: - Review of the lessons learned from the Fukushima accident concerning the robustness of electrical systems; - Review of the provisions already taken or planned after the Fukushima accident, regarding the sources, the distribution systems and the loads, and documenting the technical basis for these

  9. Integrated framework for the external cost assessment of nuclear power plant accident considering risk aversion: The Korean case

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Kang, Hyun Gook

    2016-01-01

    Recently, the estimation of accident costs within the social costs of nuclear power plants (NPPs) has garnered substantial interest. In particular, the risk aversion behavior of the public toward an NPP accident is considered an important factor when integrating risk aversion into NPP accident cost. In this study, an integrated framework for the external cost assessment of NPP accident that measures the value of statistical life (VSL) and the relative risk aversion (RRA) coefficient for NPP accident based on an individual-level survey is proposed. To derive the willingness to pay and the RRA coefficient for NPP accident risks, a survey was conducted on a sample of 1550 individuals in Korea. The estimation obtained a mean VSL of USD 2.78 million and an RRA coefficient of 1.315. Based on the estimation results in which various cost factors were considered, a multiplication factor of 5.16 and an external cost of NPP accidents of 4.39E−03 USD-cents/kW h were estimated. This study is expected to provide insight to energy policy decision-makers on analyzing the economic validity of NPP compared to other energy sources by reflecting the estimated external cost of NPP accident into the unit electricity generation cost of NPP. - Highlights: •External cost assessment framework for NPP is proposed considering risk aversion. •VSL was derived from WTP for mortality risk reduction from hypothetical NPP accident. •RRA was derived to integrate public risk aversion into external cost of NPP accident. •Individual-level survey was conducted to derive WTP and RRA for NPP accident risk. •The external cost was estimated considering the direct cost factors of NPP accident.

  10. The application of the assessment of nuclear accident status in emergency decision-making during nuclear accident

    International Nuclear Information System (INIS)

    Yang Ling

    2011-01-01

    Nuclear accident assessment is one of the bases for emergency decision-making in the situation of nuclear accident in NPP. Usually, the assessment includes accident status and consequence assessment. It is accident status assessment, and its application in emergency decision-making is introduced here. (author)

  11. Reconstruction of the Chernobyl emergency and accident management

    International Nuclear Information System (INIS)

    Schinner, F.; Andreev, I.; Andreeva, I.; Fritsche, F.; Hofer, P.; Lettner, E.; Seidelberger, E.; Kromp-Kolb, H.; Kromp, W.

    1998-01-01

    Full text of publication follows: on April 26, 1986 the most serious civil technological accident in the history of mankind occurred of the Chernobyl Nuclear Power Plant (ChNPP) in the former Soviet Union. As a direct result of the accident, the reactor was severely destroyed and large quantities of radionuclides were released. Some 800000 persons, also called 'liquidators' - including plant operators, fire-fighters, scientists, technicians, construction workers, emergency managers, volunteers, as well as medical and military personnel - were part of emergency measurements and accident management efforts. Activities included measures to prevent the escalation of the accident, mitigation actions, help for victims as well as activities in order to provide a basic infrastructure for this unprecedented and overwhelming task. The overall goal of the 'Project Chernobyl' of the Institute of Risk Research of the University of Vienna was to preserve for mankind the experience and knowledge of the experts among the 'liquidators' before it is lost forever. One method used to reconstruct the emergency measures of Chernobyl was the direct cooperation with liquidators. Simple questionnaires were distributed among liquidators and a database of leading accident managers, engineers, medical experts etc. was established. During an initial struggle with a number of difficulties, the response was sparse. However, after an official permit had been issued, the questionnaires delivered a wealth of data. Furthermore a documentary archive was established, which provided additional information. The multidimensional problem in connection with the severe accident of Chernobyl, the clarification of the causes of the accident, as well as failures and successes and lessons to be learned from the Chernobyl emergency measures and accident management are discussed. (authors)

  12. Expert software for accident identification

    International Nuclear Information System (INIS)

    Dobnikar, M.; Nemec, T.; Muehleisen, A.

    2003-01-01

    Each type of an accident in a Nuclear Power Plant (NPP) causes immediately after the start of the accident variations of physical parameters that are typical for that type of the accident thus enabling its identification. Examples of these parameter are: decrease of reactor coolant system pressure, increase of radiation level in the containment, increase of pressure in the containment. An expert software enabling a fast preliminary identification of the type of the accident in Krsko NPP has been developed. As input data selected typical parameters from Emergency Response Data System (ERDS) of the Krsko NPP are used. Based on these parameters the expert software identifies the type of the accident and also provides the user with appropriate references (past analyses and other documentation of such an accident). The expert software is to be used as a support tool by an expert team that forms in case of an emergency at Slovenian Nuclear Safety Administration (SNSA) with the task to determine the cause of the accident, its most probable scenario and the source term. The expert software should provide initial identification of the event, while the final one is still to be made after appropriate assessment of the event by the expert group considering possibility of non-typical events, multiple causes, initial conditions, influences of operators' actions etc. The expert software can be also used as an educational/training tool and even as a simple database of available accident analyses. (author)

  13. Peculiarities of hormonal regulation of physical development and bone tissue in children born after accident at Chernobyl nuclear power plant

    International Nuclear Information System (INIS)

    Antipkin, Y.G.; Arabskaya, L.P.

    2003-01-01

    Investigation of three groups of children being from 5 to 12 years old born after ChNPP accident was conducted. The 1 group consisted of 128 children lived in radionuclide contaminated territories. The 2 group consisted from 128 children born in families of the Chernobyl accident consequences liquidators (ACL). The 3 group consisted of 96 children lived in 'relatively clean' territories. Revealed age and gender differences in height growth activation periods, i.e. the second and third 'spurts' of height rise kids from the radiation study groups occur later than in children from 'conditionally clean' territories. Body height growth in children of both gender residing in radiation-contaminated territories occurs within the same age periods. Body height growth in kids born in families of the ChNPP accident liquidators occurred more fluently with neither pre-pubertal, nor pubertal 'spurt' of height in boys and no pubertal one - in girls, that is stipulated by low basal GH level (and low testosterone in boys)

  14. The role of the international Chornobyl Center in coordinating and conducting the work related to Chornobyl NPP closure and creation the new employment opportunities in Slavutych

    International Nuclear Information System (INIS)

    Nosovskij, A.V.

    2001-01-01

    The Slavutych division of the international Chornobyl Center (ICC) actively conducts its work in Slavutych from 1997. The following work was conducted during the last years: Documentation on the ChNPP 1-st Unit and 2-nd Unit decommissioning was developed. Comprehensive engineering and radiation survey of the 1-st Unit was conducted. Decommissioning database was created. On demand of Chornobyl NPP, the work on development the following documents was conducted: The 3-rd Unit shutdown program. Comprehensive program on ChNPP decommissioning. ChNPP personnel and Slavutych residents social protection program

  15. NPP service life management

    International Nuclear Information System (INIS)

    Elagin, Yu.P.

    2001-01-01

    Problems of NPP service life management and service life prolongation are reviewed. Methods for the prolongation of the French NPP service life are discussed, priority directions of nuclear block service life management in regard to aging in the context of the European program of investigation into the materials aging are identified. Questions of the provision of the 60 years service life of the Mihama 1 block (Japan) and decision of the problem of the control equipment aging in Great Britain are discussed. Situation with the prolongation of licenses on the NPP operation in the USA and Spain is considered [ru

  16. Meeting up-to-date safety requirements in the Russian NPP projects

    International Nuclear Information System (INIS)

    Tepkyan, G. O.; Yashkin, A. V.

    2014-01-01

    Safety features in Russian NPP designs are implemented by the combination of active and passive safety systems • Russian NPP designs are in compliance with up-to-date international and European safety requirements and refer to Generation III+ • Russian state-of-the-art designs have already implemented some design solutions, which take into account “post-Fukushima” requirements. Russian NPP design principles have been approved during the European discussions in spring 2012, including the IAEA extraordinary session addressed to Fukushima NPP accident

  17. Graphic console for analysis of severe accidents visualization of OEs, NAEs and calculation of the source term for the NPP-LV (CoGrAAS); Consola grafica para analisis de accidentes severos visualizacion de OEs, NAEs y calculo del termino fuente para la CLV (CoGrAAS)

    Energy Technology Data Exchange (ETDEWEB)

    Sandoval V, S.; Mendoza E, P. R.; Gonzalez C, J. M.; Cecenas F, M. [Instituto Nacional de Electricidad y Energias Limpias, Reforma 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico); Tijerina S, F., E-mail: francisco.tijerina@cfe.gob.mx [CFE, Central Nucleoelectrica Laguna Verde, Carretera Federal Cardel-Nautla Km 42.5, 91476 Municipio Alto Lucero, Veracruz (Mexico)

    2016-09-15

    In response to the Fukushima Daiichi nuclear power plant accident, the NRC conducted an analysis and issued recommendations to improve the safety of the nuclear reactors. These include strengthening and integrating emergency response capabilities and emphasizing periodic staff training, the performance of simulation exercises. As a tool to observe these recommendations, the Graphic Console was developed for Analysis of Severe Accidents, Visualization of OEs, NAEs and calculation of the source term for nuclear power plant of Laguna Verde (NPP-LV ; CoGrAAS). The CoGrAAS is a computer system that displays in an integrated, graphic and dynamic way the information of a catalog of previously simulated accident scenarios. Has core mimics, vessel, primary containment and safety systems, trend graph of thermodynamic and radiological variables and the emergency procedures (OEs), chronological list of events, windows with detailed information for the dry-well, among others. The use of CoGrAAS allows that staff to understand and become familiar with the thermo-hydraulic progression of actual scenarios that exceed the design basis including those with core damage as severe accidents. The system enables personnel to develop an integral vision of the scenarios during the exercises and drills by observing and analyzing the evolution of the main reactor, core and primary containment variables, the response of emergency systems and the influence of that progression on OEs and the emergency action levels (NAEs). The CoGrAAS allows o observe the radiological variables and obtain the source term, to make the projection of doses, at any time within the scenario evolution. Thus, not only can the phenomenology of severe accidents be analyzed and understood, it is also possible to exercise, verify and evaluate the performance of critical tasks in the application of procedures, guidelines and emergency management plans. (Author)

  18. Analysis of flooding possibilities of premises of Ignalina NPP

    International Nuclear Information System (INIS)

    1999-01-01

    Analysis of flooding possibilities of premises with safety related equipment of Ignalina NPP was performed. In calculations codes SQUIRT and RELAP5 was used. In most cases it was found that it would be enough time to take corrective measure in the case of flooding accident

  19. Chernobyl NPP decommissioning efforts - Past, Present and Future. Decommissioning Efforts on Chernobyl NPP site - Past, Present

    International Nuclear Information System (INIS)

    Kuchinskiy, V.

    2017-01-01

    Two unique large-scale projects are underway at the moment within the Chernobyl - Exclusion zone - Shelter object transformation into ecologically safe system and the decommissioning of 3 Chernobyl NPP Units. As a result of beyond design accident in 1986 the entire territory of the industrial site and facilities located on it was heavily contaminated. Priority measures were carried out at the damaged Unit under very difficult conditions to reduce the accident consequences and works to ensure nuclear and radiation safety are continuous, and the Unit four in 1986 was transformed into the Shelter object. Currently, works at the Shelter object are in progress. Under assistance of the International Community new protective construction was built above the existing Shelter object - New Safe Confinement, which will ensure the SO Safety for the long term - within up to 100 years. The second major project is the simultaneous decommissioning of Chernobyl NPP Units 1, 2 and 3. Currently existing Chernobyl NPP decommissioning Strategy has been continuously improved starting from the Concept of 1992. Over the years the following was analyzed and taken into account: the results of numerous research and development works, international experience in decommissioning, IAEA recommendations, comments and suggestions from the governmental and regulatory bodies in the fields of nuclear energy use and radioactive waste management. In 2008 the final decommissioning strategy option for Chernobyl NPP was approved, that was deferred gradual dismantling (SAFSTOR). In accordance with this strategy, decommissioning will be carried out in 3 stages (Final Shutdown and Preservation, Safe Enclosure, Dismantling). The SAFSTOR strategy stipulates: -) the preservation of the reactor, the primary circuit and the reactor compartment equipment; -) the dismantling of the equipment external in relation to the reactor; -) the safe enclosure (under the supervision); -) the gradual dismantling of the primary

  20. Report on Fukushima Daiichi NPP precursor events

    International Nuclear Information System (INIS)

    2014-01-01

    The main questions to be answered by this report were: The Fukushima Daiichi NPP accident, could it have been prevented? If there is a next severe accident, may it be prevented? To answer the first question, the report addressed several aspects. First, the report investigated whether precursors to the Fukushima Daiichi NPP accident existed in the operating experience; second, the reasons why these precursors did not evolve into a severe accident. Third, whether lessons learned from these precursor events were adequately considered by member countries; and finally, if the operating experience feedback system needs to be improved, based on the previous analysis. To address the second question which is much more challenging, the report considered precursor events identified through a search and analysis of the IRS database and also precursors events based on risk significance. Both methods can point out areas where further work may be needed, even if it depends heavily on design and site-specific factors. From the operating experience side, more efforts are needed to ensure timely and full implementation of lessons learnt from precursor events. Concerning risk considerations, a combined use of risk precursors and operating experience may drive to effective changes to plants to reduce risk. The report also contains a short description and evaluation of selected precursors that are related to the course of the Fukushima Daiichi NPP accident. The report addresses the question whether operating experience feedback can be effectively used to identify plant vulnerabilities and minimize potential for severe core damage accidents. Based on several of the precursor events national or international in-depth evaluations were started. The vulnerability of NPPs due to external and internal flooding has clearly been addressed. In addition to the IRS based investigation, the WGRISK was asked to identify important precursor events based on risk significance. These precursors have

  1. SAT for NPP personnel training in USA

    International Nuclear Information System (INIS)

    Spinney, R.

    1995-01-01

    This discussion addressed the experience with the application of SAT at USA NPPs. In particular, the transition of NPP training processes, staff composition, and reporting structure from the TMI accident to present. As well, oversight and guidance activities of the INPO and more intensive inspection by the NRC began during this period. The average NPP training staff grew to 30-40 per unit, along with a change in reporting line from plant to corporate management. With the reduction of resources occurring in the late 1980s, overall training staff size decreased, the composition changed, and reporting line reverted to plant management. The overall lessons-learned for application of the SAT consisted of the need for simplification, management involvement, and exploitation of the technology

  2. Estimation of the total population moving into and out of the 20 km evacuation zone during the Fukushima NPP accident as calculated using 'Auto-GPS' mobile phone data

    International Nuclear Information System (INIS)

    Hayano, Ryugo S.; Adachi, Ryutaro

    2013-01-01

    The first objective data showing the geographical locations of people in Fukushima after the Fukushima Dai-ichi nuclear power plant accident, obtained by an analysis of GPS (Global Positioning System)-enabled mobile phone logs, are presented. The method of estimation is explained, and the flow of people into and out of the 20 km evacuation zone during the accident is visualized. (author)

  3. Lessons of the accident at Three Mile Island nuclear power plant

    International Nuclear Information System (INIS)

    Veksler, L.M.

    1983-01-01

    Measures taken in the USA for improving safety of NPPs after the accident at ''Three Mile Island'' nuclear power plant are considered. Activities, related to elimination of accident consequences are analyzed. Perspectives of resuming the NPP operation are discussed

  4. The IAEA Accident Management Programme

    International Nuclear Information System (INIS)

    Kabanov, L.; Jankowski, M.; Mauersberger, H.

    1993-01-01

    Accident prevention and mitigation programmes and the Emergency Response System (ERS) are important elements of the Agency's activities in the area of nuclear power plant (NPP) safety. Safety Codes and Guides on siting, design, quality assurance and the operation of NPPs have been produced and are used by NPP operating organizations. Nuclear safety evaluation services are provided by the IAEA. The Emergency Response System and the International Nuclear Event Scale (INES) have been developed. The framework for the development of an accident management programme has been set up. The main goal is to develop an Accident Management Manual to provide a systematic, structured approach to the development and implementation of an accident management programme at NPPs. An outline of the Manual has been distributed and the first draft is available. The component parts are: Co-ordinated research programmes (CRPs) on severe accident management and containment behaviour; the use of vulnerability analysis; mitigation of the effects of hydrogen, and generic symptom oriented emergency operating procedures. The IAEA provides guidance by the dissemination of information on methods for accident management; collates information on approaches in this field in different organizations and countries; and arranges exchange of experience and the promulgation of knowledge through the training of NPP managers and senior technical staff. (orig.)

  5. The IAEA Accident Management Programme

    Energy Technology Data Exchange (ETDEWEB)

    Kabanov, L.; Jankowski, M.; Mauersberger, H. (International Atomic Energy Agency, Vienna (Austria))

    1993-02-01

    Accident prevention and mitigation programmes and the Emergency Response System (ERS) are important elements of the Agency's activities in the area of nuclear power plant (NPP) safety. Safety Codes and Guides on siting, design, quality assurance and the operation of NPPs have been produced and are used by NPP operating organizations. Nuclear safety evaluation services are provided by the IAEA. The Emergency Response System and the International Nuclear Event Scale (INES) have been developed. The framework for the development of an accident management programme has been set up. The main goal is to develop an Accident Management Manual to provide a systematic, structured approach to the development and implementation of an accident management programme at NPPs. An outline of the Manual has been distributed and the first draft is available. The component parts are: Co-ordinated research programmes (CRPs) on severe accident management and containment behaviour; the use of vulnerability analysis; mitigation of the effects of hydrogen, and generic symptom oriented emergency operating procedures. The IAEA provides guidance by the dissemination of information on methods for accident management; collates information on approaches in this field in different organizations and countries; and arranges exchange of experience and the promulgation of knowledge through the training of NPP managers and senior technical staff. (orig.).

  6. Experience from the Inspection of Licensees' Outage Activities, Including Fire Protection Programmes, Event Response Inspections, and the Impact of the Fukushima Daiichi NPP Accident on Inspection Programmes. Workshop Proceedings, Chattanooga, Tennessee, United States, 7-10 April 2014

    International Nuclear Information System (INIS)

    2014-10-01

    The main purpose of the workshop was to provide a forum of exchange of information on the regulatory inspection activities. Participants had the opportunity to meet with their counterparts from other countries and organisations to discuss current and future issues on the selected topics. They developed conclusions regarding these issues and hopefully, identified methods to help improve their own inspection programmes. The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established working groups and groups of experts in specialised topics. The Working Group on Inspection Practices (WGIP) was formed in 1990 with the mandate '..to concentrate on the conduct of inspections and how the effectiveness of inspections could be evaluated..'. The WGIP facilitates the exchange of information and experience related to regulatory safety inspections between CNRA member countries. These proceedings cover the 12. International Workshop held by WGIP on regulatory inspection activities. This workshop, which is the twelfth in a series, along with many other activities performed by the Working Group, is directed towards this goal. The consensus from participants at previous workshops, noted that the value of meeting with people from other inspection organisations was one of the most important achievements. The focus of this workshop was on experience gained from regulatory inspection activities in three areas: - Inspection of Outage Activities Including Fire Protection Programmes. - Event Response Inspections. - The Impact of Inspection Programmes of the Fukushima Daiichi Nuclear Power Plant (NPP) Accident. The main objectives of the WGIP workshops are to enable inspectors to meet with inspectors from other organisations, to exchange information regarding regulatory inspection

  7. Development of Krsko Severe Accident Management Database (SAMD)

    International Nuclear Information System (INIS)

    Basic, I.; Kocnar, R.

    1996-01-01

    Severe Accident Management is a framework to identify and implement the Emergency Response Capabilities that can be used to prevent or mitigate severe accidents and their consequences. Krsko Severe Accident Management Database documents the severe accident management activities which are developed in the NPP Krsko, based on the Krsko IPE (Individual Plant Examination) insights and Generic WOG SAMGs (Westinghouse Owners Group Severe Accident Management Guidance). (author)

  8. Technical innovations at NPP Dukovany - for safe and efficient operation

    International Nuclear Information System (INIS)

    Sabata, M.; Vasa, I.

    2000-01-01

    Inherent features of the NPP Dukovany design provide a significant confidence in its nuclear safety assurance; among these features should be emphasised the reactor core stability and its control and protection system capability to hold the reactor in safe state following scram or accident conditions. Nevertheless, NPP Dukovany was designed in the early seventies, and current requirements for nuclear safety assurance are more strict and/or specific as a result of the technical development and lessons learned from nuclear accidents. The paper compares the safety design base established at the time of NPP Dukovany project implementation and the current reference design base. The paper also presents procedures applied to implement technical and operational measures which are introduced to fulfil the current basic safety criteria. The scope of such measures applied at NPP Dukovany is compared with that of EU countries introduced for the same reason - to meet the updated safety related requirements. Examples of some innovations already implemented or under implementation give an idea how NPP Dukovany proceeds in reaching the goal of harmonising its safety with the requirements to be met before the Czech Republic becomes a member country of the European Union. (author)

  9. Consideration on application of RAP to G-II NPP

    International Nuclear Information System (INIS)

    Shen Shen

    2010-01-01

    The design (D-RAP) for nuclear power plant has been adopted internationally in new-build advanced nuclear power plant design, which increases the ability of the risk-significant SSCs to carry out its functions during the accident circumstances especially in the severe accident situation, and reduces the risk of a nuclear power plant. The concept of reliability assurance program for advanced nuclear power plant can also be applied to nuclear power plants which second-generation NPP technology is used. Through analysis and research, the risk-significant SSCs in actual NPP can also be screened, and these SSCs can be managed appropriately, so that can improve the overall plant ability to against the severe accident, reduce the risk, and improve their safety and economy. Also such technology used does not exist any insurmountable technical difficulties and a lot of money input. (authors)

  10. EMAS at Doel NPP

    International Nuclear Information System (INIS)

    Nolan, Peter; Thoelen, Els

    1998-01-01

    In October 1995, Doel NPP of Electrabel, Belgium opted to seek registration under the EC Eco-management and Audit Scheme (EMAS). A comprehensive environmental management system (EMS) has been introduced and implemented, encompassing all four PWRs and the supporting departments. A critical step was to seek certification from an accredited environmental auditing body against the International Standard ISO 14001. This provided the foundation for the publicly available environmental statement required by EMAS. The complications of achieving EMAS at a time when national and international standards were being re-formulated were successfully overcome and Doel NPP passed its EMAS audit in June 1997. (author)

  11. Accidents - Chernobyl accident; Accidents - accident de Tchernobyl

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This file is devoted to the Chernobyl accident. It is divided in four parts. The first part concerns the accident itself and its technical management. The second part is relative to the radiation doses and the different contaminations. The third part reports the sanitary effects, the determinists ones and the stochastic ones. The fourth and last part relates the consequences for the other European countries with the case of France. Through the different parts a point is tackled with the measures taken after the accident by the other countries to manage an accident, the cooperation between the different countries and the groups of research and studies about the reactors safety, and also with the international medical cooperation, specially for the children, everything in relation with the Chernobyl accident. (N.C.)

  12. Annual activity report of Ignalina NPP Safety Analysis Group for 1995 year

    International Nuclear Information System (INIS)

    Ushpuras, E.; Augutis, J.; Bubelis, E.

    1995-01-01

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1995 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system. 18 refs., 9 tabs., 110 figs

  13. Annual activity report of Ignalina NPP Safety Analysis Group for 1994 year

    International Nuclear Information System (INIS)

    Ushpuras, E.; Kaliatka, A.; Chesna, B.; Dundulis, G.

    1995-01-01

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1994 are presented. ISAG is concentrated its research activities into 3 areas: the neutrons dynamics modeling, simulation of transient processes during loss of coolant accident and calculation of reactor building structure's streses and other mechanical properties in the case of accident. 6 refs., 13 tabs., 69 figs

  14. Annual activity report of Ignalina NPP Safety Analysis Group for the year 1997

    International Nuclear Information System (INIS)

    Ushpuras, E.; Augutis, J.; Bubelis, E.; Kaliatka, A

    1998-01-01

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for the year 1997 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system

  15. NPP life management program - status report for Slovenia

    International Nuclear Information System (INIS)

    Glumac, B.

    1998-01-01

    Status report on NPP life management in Slovenia is dealing with possible life extension of NPP Krsko which comprises: replacement of steam generator; power upgrade; exchange of plant process computer; snubber reduction program, additional forced ventilation cooling system. Fuel improvements are predicted as well as the problems of storing spent fuel, low and intermediate waste if the plant is to operate through 2023 and possibly beyond that date. Related research activities are concerned with radiation damage, modelling of reactor core parameters by Monte Carlo calculations and PSA and severe accidents studies. Most of the activities are performed in cooperation with foreign organisations

  16. About choosing the power unit of NPP

    International Nuclear Information System (INIS)

    Alekseev, P.N.; Mordashev, V.M.; Proshkin, A.A.; Stukalov, V.A.; Subbotin, S.A.; Tsibul'skij, V.F.; Chernilin, Yu.F.

    2008-01-01

    The present-day domestic nuclear power industry faces the necessity to make both process and economy related decisions. The mentioned decisions should cover all the aspects of the nuclear power complex. In particular, as of now, no substantiation of the present-day and the future requirements for the power unit of the WWER and fast reactor NPPs is available. The choice of the unit power of an NPP should involve consideration of all factors and should not be boiled down to the efforts to ensure the minimization of the investment and the operation constituents of the electric power generation costs. The aim of the present paper was to ensure elaboration of the recommendations to substantiate the optimal unit power of NPP power units based on the analysis of various factors to design, to construct and to operate an NPP (investment, time of construction, the unscheduled shutdown losses, the unification, the fabrication quality, the accident damage, etc.), and the electrical network potentialities and the regional electric power demands [ru

  17. Temelin NPP commissioning experiences

    International Nuclear Information System (INIS)

    Hanus, V.

    2002-01-01

    The Building Permit for the Temelin NPP with four VVER units was issued in 1986, which is a long time ago. Since then, however, was taken a route that is very different from what anybody imagined. Described are the legislative and design changes and given is a current condition of the power plant

  18. Dukovany NPP maintenance management

    International Nuclear Information System (INIS)

    Siegel, F.

    2005-01-01

    Maintenance planning and management for the technological equipment of the Dukovany NPP are described. A Maintenance Control and Evaluation System has been developed and is in use to help manage the complex maintenance issue. Practical examples of outputs of the System, with a comprehensive use of the cost, reliability and safety related data, are presented. (author)

  19. NPP Krsko decommissioning concept

    International Nuclear Information System (INIS)

    Novsak, M.; Fink, K.; Spiler, J.

    1996-01-01

    At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP KRSKO. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and the results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economical aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling all activities necessary for the decommissioning of the NPP KRSKO are presented. (author)

  20. NPP Krsko decommissioning concept

    International Nuclear Information System (INIS)

    Novsak, M.; Fink, K.; Spiler, J.

    1996-01-01

    At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP Krsko. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for a decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill the decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economic aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling of all activities necessary for the decommissioning of the NPP Krsko are presented. (author)

  1. Two managerial grids in NPP

    International Nuclear Information System (INIS)

    Zhao Hui

    2012-01-01

    Today, the nuclear power corporation (NPC) enjoys the profit of LCEP (the low carbon economic policy). at the same time, they also enduring more and more pressure. For example, the partner competition or the NPP potential occupational risk . The efficient counterplot of risk is the self-ability cultivation. It is essential to research the NPP managerial flow. The nuclear power plant (NPP) unit is a carrier of the NPC enterprise management system, and has taken on a new look 'pull one portion then the whole moving'. The NPP has three systematical characters, the security responsibility center, the man-machine system and the input-output system. The manufacturing system and the enterprise management system are the great constituents of the NPP managerial flows. Means of systems analysis, we can find out the truth of the NPP running interface. In CHINA, there are many operating experiences near 20 years. It indicates that the NPP manufacturing system and the enterprise system are the roots of the nuclear power corporation, the core of the all NPP systems must be based on it. So the ability cultivation is the work core to NPP. It is reliably to ensure the NPP to be up against problems, for instance, the security duty, the costing control and the man-machine system running harmoniously. This paper introduces the NPP managerial flow and the present state of QNPC, also come up with a proposal to refer for the NPC development actions of collective measure, specialization, standardization, fine. (author)

  2. Chernobyl'-92. Reports of the 3. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 2. Part 1. Methods for decontamination, dust suppression. Development and applicability of techniques for the accident effect elimination

    International Nuclear Information System (INIS)

    Senin, E.V.

    1992-01-01

    The means of decontamination have been considered. The requirements on radiation protection of equipment during radioactive contamination have been presented. New efficient methods for decontamination of technological equipment, units and systems of the Chernobyl' NPP were demonstrated. The variations and postects for burial of radioactive wastes and materials, radioactive water processing and application of polymer coatings were presented

  3. Tool to Assist the Management of Severe Accident Guide NPP Vandellos-II; Herramienta de Ayuda a la Gestion de las Guias de Accidentes Severos de CN. Vandellos-II

    Energy Technology Data Exchange (ETDEWEB)

    Gutierrez Varela, J.; Pontejo Calvente, A.; Martinez Fanegas, R.

    2013-07-01

    The objective of the project is the development of the software tool {sup M}anagement System Severe Accident Guide (GGAS) {sup w}hich makes tracking and optimal application of these guidelines by the Technical Support Center (CAT) Vandellos II.

  4. Accident Assessment

    International Nuclear Information System (INIS)

    Tripputi, Ivo; Lund, Ingemar

    2002-01-01

    There is a general feeling that decommissioning is an activity involving limited risks, compared to NPP operation, and in particular risks involving the general public. This is technically confirmed by licensing analysis and evaluations, where, once the spent fuel has been removed from the plant, the radioactivity inventory available to be released to the environment is very limited. Decommissioning activities performed so far in the world have also confirmed the first assumptions and no specific issue has been identified, in this field, to justify a completely new approach. Commercial interests in international harmonization, which could drive an in-depth discussion about the bases of this approach, are weak at the moment. However, there are several reasons why a discussion in an international framework about the Safety Case for decommissioning (and, in particular, about Accident Assessment) may be considered necessary and important, and why it may show some specific and peculiar aspects. An effort for a comprehensive and systematic D and D accident safety assessment of the decommissioning process is justified. It is necessary also to explore in a holistic way the aspects of industrial safety, and develop tools for the decision-making process optimization. The expected results are the implementation of appropriate and optimized protective measures in any event and of adequate on/off-site emergency plans for optimal public and workers protection. The experience from other decommissioning projects and large-scale industrial activities is essential to balance provisions and an Operating Experience review process (specific for decommissioning) should help to focus on real issues

  5. Scenarios catalog for the graphical console for analysis of severe accidents visualization of OEs, NAEs and calculation of source term of the NPP-LV; Catalogo de escenarios para la consola grafica para analisis de accidentes severos visualizacion de OEs, NAEs y calculo del termino fuente de la CLV

    Energy Technology Data Exchange (ETDEWEB)

    Sandoval V, S. [Instituto Nacional de Electricidad y Energias Limpias, Reforma 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico); Mendoza R, M. E.; Tijerina S, F.; Garcia C, T., E-mail: manuel.mendoza@cfe.gob.mx [CFE, Central Nucleoelectrica Laguna Verde, Carretera Federal Cardel-Nautla Km 42.5, 91476 Municipio Alto Lucero, Veracruz (Mexico)

    2016-09-15

    A nuclear power plant is operated at all times within the design criteria of structures, systems and components, and according to the operation technical specifications. For different areas of work of a nuclear power plant is necessary to carry out practices in which is useful to have the prediction of the thermo-hydraulic and radiological progression of scenarios that imply exceeding that design bases, even reaching the damage of the fuel in different degree. During the exercises and drills of the External Plan of Emergency Response, the projection of doses is done to exercise the different tasks of the plan. To make the projection of doses is required to have the radiological source term of the scenario on which is practiced. Because of this, was identified the convenience of having a catalog of scenarios for which the radiological source term was calculated. In 2004, a first version of the catalog was produced for a power of 2027 MW, and in 2011 the catalog was updated for extended power conditions, 2317 MW. Both versions were made using the severe accident simulator MAAP-3B. That catalog consists of a form and an optical storage device. The form contains tables and figures in which the characteristics of the scenario to be practiced are searched and the electronic files of the corresponding radiological source term are located in the storage device. Due to the recent development of the graphical console for analysis of severe accidents, visualization of OEs, NAEs and calculation of the source term for the nuclear power plant of Laguna Verde (NPP-LV) CoGrAAS, the catalog printed was replaced by an electronic catalog for the CoGrAAS. The new catalog retains the philosophy of the previous catalog, constituted by a wide collection of scenarios that involve different circumstances and phenomena, that can be used to practice different tasks during training exercises or simulacrums, and combined with the following advantages: the scenario selection is made from an

  6. Calculation of behaviour of the Juragua NPP containment with code TRACOV/MOD1

    International Nuclear Information System (INIS)

    Castillo Alvarez, J.; Valle Cepero, R.; Luis, J.; San Roman, J.C.; Pomier, L.

    1996-01-01

    The containment of Juragua NPP has some unique features, which differ from the rest of the PWR reactors design. Those features impose additional requirements for its numerical simulation. In this paper is analyzed the behaviour of the Juragua NPP containment during accident situation with double ended break of the primary pipelines with flow in both direction using the code TRACOV/MOD1. The results are compared with obtained by the designer. The main restrictions of the code are identified

  7. Main directions of works on radioactive waste management at 30-km zone near the Chernobyl' NPP

    International Nuclear Information System (INIS)

    Grushinskij, B.Ya.; Komarov, V.I.; Proskuryakov, A.N.; Kham'yanov, L.N.; Khubizov, S.B.; Ignatenko, E.I.; Ryzhkova, V.N.; Luppov, V.A.; Matskevich, G.V.; Frolov, V.N.

    1989-01-01

    Main points and stages of creating an specialized enterprise for centralized reprocessing and radioactive waste disposal are considered. The enterprise is intended for collection conditioning and burial of all types of radioactive wastes, formed during liquidation of accident effect at the Chernobyl' NPP as well as forming in operation of NPP. The enterprise is also used to decontaminate equipment and constructions, for reprocessing of secondary radioactive wastes forming during decontamination process of equipment constructions, transport and work clothes

  8. Radioactive Waste Management In The Chernobyl Exclusion Zone - 25 Years Since The Chernobyl Nuclear Power Plant Accident

    International Nuclear Information System (INIS)

    Farfan, E.; Jannik, T.

    2011-01-01

    Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities of the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste related problems in Ukraine and the Chernobyl Exclusion Zone, and in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program. The brief overview of the radioactive waste issues in the ChEZ presented in this article demonstrates that management of radioactive waste resulting from a beyond-designbasis accident at a nuclear power plant becomes the most challenging and the costliest effort during the mitigation and remediation activities. The costs of these activities are so high that the provision of radioactive waste final disposal facilities compliant with existing radiation safety requirements becomes an intolerable burden for the current generation of a single country, Ukraine. The nuclear accident at the Fukushima-1 NPP strongly indicates that accidents at nuclear sites may occur in any, even in a most technologically advanced country, and the Chernobyl experience shows that the scope of the radioactive waste management activities associated with the mitigation of such accidents may exceed the capabilities of a single country. Development of a special international program for broad international cooperation in accident related radioactive waste management activities is required to handle these issues. It would also be reasonable to consider establishment of a dedicated international fund for mitigation of accidents at nuclear sites, specifically, for handling radioactive waste problems in the ChEZ. The experience of handling Chernobyl radioactive waste management issues, including large volumes of radioactive soils and complex structures

  9. Fukushima-Daiichi after the severe accident (estimation)

    International Nuclear Information System (INIS)

    Otcenasek, Petr

    2011-01-01

    All facts about the Fukushima-Daiichi NPP and about the accident known at the time of publication are summarized and expected remedial actions and consequences of the accidents are deduced. The paper is structured as follows: (1) Accident initiation is known; (2) Logically inferred results; (3) Framework identification; (4) Survey; and (5) Economic and strategic impacts of the accident. Worldwide solidarity is mentioned in conclusion. (P.A.)

  10. Safety investigation of team performance in accidents

    International Nuclear Information System (INIS)

    Petkov, G.; Todorov, V.; Takov, T.; Petrov, V.; Stoychev, K.; Vladimirov, V.; Chukov, I.

    2004-01-01

    The paper presents the capacities of the performance evaluation of teamwork (PET) method. Its practicability and efficiency are illustrated by retrospective human reliability analyse of the famous nuclear and maritime accidents. A quantitative assessment of operators' performance on the base of thermo-hydraulic (T/H) calculations and full-scope simulator data for set of NPP design basic accidents with WWER is demonstrated. The last data are obtained on the 'WWER-1000' full-scope simulator of Kozloduy NPP during the regular practical training of the operators' teams. An outlook on the 'evaluation system of main control room (MCR) operators' reliability' project, based on simulator data of operators' training is given

  11. Experiments on The Retention of The Fission Product Iodine in Nuclear Reactor Accidents

    International Nuclear Information System (INIS)

    Bruchertseifer, H.; Cripps, R.; Guentay, S.; Jaeckel, B.

    2004-01-01

    The paper reports PSI participation in the ICHEMM Project (Iodine Chemistry and Mitigation Mechanisms) of the EU 5th Framework Programme, which has the objective of identifying new possible mitigation processes, or accident management measures, favouring the conversion of volatile iodine species, especially organic iodine released during a severe accident at a Nuclear Power Plant (NPP), into nonvolatile forms. Significant effort has been expended, firstly to develop analytical methods for determining concentrations of the common iodine species (iodide, iodate, molecular iodine and methyl iodide), and secondly to provide missing and important information on decomposition phenomena and involved reactions. Experiments have been conducted at PSI to obtain data on thermal (hydrolysis) and radiolytic decomposition of CH 3 I in aqueous solution under conditions as close as possible to those in an anticipated accident. Radioactive-labelled methyl iodide was used to monitor and quantify the decomposition and to determine the overall mass balance. Results have shown that CH 3 I hydrolysis at 90 o C will dominate over radiolysis at the dose rates (max. 0.4 Gy.s -1 ) employed in the experiments. Much increased decomposition rates of CH 3 I have been achieved with chemical reagents (additives), such as sodium thiosulphate or ammonium sulphide. After completion of the ICHEMM Project, further advances have been made from experiments carried out on additives (especially in combination with Aliquat 336) in terms of a fast and complete retention of iodine. The data from these experiments are of direct relevance to severe accident management for both PWR and BWR systems. The impact of the results on possible strategies for management of radioactive waste has also been investigated. (author)

  12. Experiments on The Retention of The Fission Product Iodine in Nuclear Reactor Accidents

    Energy Technology Data Exchange (ETDEWEB)

    Bruchertseifer, H.; Cripps, R.; Guentay, S.; Jaeckel, B

    2004-03-01

    The paper reports PSI participation in the ICHEMM Project (Iodine Chemistry and Mitigation Mechanisms) of the EU 5th Framework Programme, which has the objective of identifying new possible mitigation processes, or accident management measures, favouring the conversion of volatile iodine species, especially organic iodine released during a severe accident at a Nuclear Power Plant (NPP), into nonvolatile forms. Significant effort has been expended, firstly to develop analytical methods for determining concentrations of the common iodine species (iodide, iodate, molecular iodine and methyl iodide), and secondly to provide missing and important information on decomposition phenomena and involved reactions. Experiments have been conducted at PSI to obtain data on thermal (hydrolysis) and radiolytic decomposition of CH{sub 3}I in aqueous solution under conditions as close as possible to those in an anticipated accident. Radioactive-labelled methyl iodide was used to monitor and quantify the decomposition and to determine the overall mass balance. Results have shown that CH{sub 3}I hydrolysis at 90{sup o}C will dominate over radiolysis at the dose rates (max. 0.4 Gy.s{sup -1}) employed in the experiments. Much increased decomposition rates of CH{sub 3}I have been achieved with chemical reagents (additives), such as sodium thiosulphate or ammonium sulphide. After completion of the ICHEMM Project, further advances have been made from experiments carried out on additives (especially in combination with Aliquat 336) in terms of a fast and complete retention of iodine. The data from these experiments are of direct relevance to severe accident management for both PWR and BWR systems. The impact of the results on possible strategies for management of radioactive waste has also been investigated. (author)

  13. Spent fuel pool risk analysis for the Dukovany NPP

    Energy Technology Data Exchange (ETDEWEB)

    Hust' ak, S.; Jaros, M.; Kubicek, J. [UJV Rez, a.s., Husinec-Rez (Czech Republic)

    2013-07-01

    UJV Rez, a.s. maintains a Living Probabilistic Safety Assessment (Living PSA) program for Dukovany Nuclear Power Plant (NPP) in the Czech Republic. This project has been established as a framework for activities related to risk assessment and to support for risk-informed decision making at this plant. The most extensively used PSA application at Dukovany NPP is risk monitoring of instantaneous (point-in-time) risk during plant operation, especially for the purpose of configuration risk management during plant scheduled outages to avoid risk significant configurations. The scope of PSA for Dukovany NPP includes also determination of a risk contribution from spent fuel pool (SFP) operation to provide recommendations for the prevention and mitigation of SFP accidents and to be applicable for configuration risk management. This paper describes the analysis of internal initiating events (IEs) in PSA for Dukovany NPP, which can contribute to the risk from SFP operation. The analysis of those IEs was done more thoroughly in the PSA for Dukovany NPP in order to be used in instantaneous risk monitoring. (orig.)

  14. Feature extraction and sensor selection for NPP initiating event identification

    International Nuclear Information System (INIS)

    Lin, Ting-Han; Wu, Shun-Chi; Chen, Kuang-You; Chou, Hwai-Pwu

    2017-01-01

    Highlights: • A two-stage feature extraction scheme for NPP initiating event identification. • With stBP, interrelations among the sensors can be retained for identification. • With dSFS, sensors that are crucial for identification can be efficiently selected. • Efficacy of the scheme is illustrated with data from the Maanshan NPP simulator. - Abstract: Initiating event identification is essential in managing nuclear power plant (NPP) severe accidents. In this paper, a novel two-stage feature extraction scheme that incorporates the proposed sensor type-wise block projection (stBP) and deflatable sequential forward selection (dSFS) is used to elicit the discriminant information in the data obtained from various NPP sensors to facilitate event identification. With the stBP, the primal features can be extracted without eliminating the interrelations among the sensors of the same type. The extracted features are then subjected to a further dimensionality reduction by selecting the sensors that are most relevant to the events under consideration. This selection is not easy, and a combinatorial optimization technique is normally required. With the dSFS, an optimal sensor set can be found with less computational load. Moreover, its sensor deflation stage allows sensors in the preselected set to be iteratively refined to avoid being trapped into a local optimum. Results from detailed experiments containing data of 12 event categories and a total of 112 events generated with a Taiwan’s Maanshan NPP simulator are presented to illustrate the efficacy of the proposed scheme.

  15. Fukushima nuclear accident and the social responsibility of science

    International Nuclear Information System (INIS)

    Yoshioka, Hitoshi

    2011-01-01

    Five months had passed since Fukushima Daiichi Nuclear Power Plant (NPP) accident occurred but still there was no knowing when the accident ended. Released radioactivity seemed to be greater than one million terra Bq and if there occurred an explosive rupture of containment vessel due to the failure of containment vent or occurrence of steam explosion, the amount of released radioactivity might amount to be at least equivalent to or surpass that of Chernobyl NPP accident. There existed still a risk that overheating and meltdown of nuclear fuels might reoccur with loss of cooling due to a possible giant aftershock. This article described total views on significant disaster that the accident brought about on many neighboring residents or wide range of people. After a general discussion about what was social responsibility of scientists, social responsibility of scientists for Fukushima Daiichi NPP accident was discussed. Responsibility of omission was also argued. (T. Tanaka)

  16. Chernobyl'-92. Reports of the 3. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 1. Radiation monitoring. Migration of radionuclides in natural environment. Part 1

    International Nuclear Information System (INIS)

    Senin, E.V.

    1992-01-01

    Section Radiation monitoring comprises: atlas of area radioactive contamination as a result of the Chernobyl' nuclear power station accident, state of computerized radiation control system, hydrological monitoring, radiation situation in different areas, problems of radioactive monitoring and protection of water objects, methods for determining radionuclides content, radiochemical mechanisms of radionuclide migration mobility of the Chernobyl' effluents, the results of investigations into migration of radionuclides in soils, landscapes, bottom depositions, in the soil-plant chain

  17. Radiation protection in Bohunice NPP. Description of present status

    International Nuclear Information System (INIS)

    Dobis, L.

    2001-01-01

    Radiation protection (RP) at Bohunice NPP has reached the high international standard. The fact was approved by several independent international missions (OSART , WANO, WENRA, ...). A lot of modifications have been done in order to improve the standard of radiation protection. All the BSS requirements have been implemented into the plant regulations before the State Law No 290/1996 and 470/2000 came into the force. Internal audits are regularly performed at NPP in order to reveal potential deficiencies. In 2001 there were 4 such audits focused on quality assurance, software operation, LBB concept and limits and condition of safe operation. State Health Institute, the regulatory body in the radiation protection, performs the inspection at least ones a month. Good relationship with the inspectors of State Health Institute also contributes to the safe operation of the NPP. There were not any radiation accident. All anomalies or radiation events are investigated at a plant level. The results of root cause analysis and proposal of corrective actions are provided to IAEA and WANO databases for the distribution. The Radiation protection department of Bohunice NPP cooperates with the other Czech and Slovak NPPs. Regular meetings on radiation protection and lately also on emergency preparedness are organized. The cooperation is excellent. Occupational exposure is reviewed also with respect of ISOE data. Bohunice NPP (even with high dose burden caused by reconstruction of V1 NPP) can be found in the first half of world PWR speaking about the collective exposure per reactor. V2 NPP itself reaches the lowest collective exposure in the world. All doses are below the limits and kept ALARA. ALARA system has been established already in 1997 at Bohunice NPP and its results are obvious for example looking at dose results during the reconstruction works at V1 NPP. The operation of Bohunice NPP has negligible influence to its surroundings. The values of gas and liquid effluents move

  18. Study on integrated design and analysis platform of NPP

    International Nuclear Information System (INIS)

    Lu Dongsen; Gao Zuying; Zhou Zhiwei

    2001-01-01

    Many calculation software have been developed to nuclear system's design and safety analysis, such as structure design software, fuel design and manage software, thermal hydraulic analysis software, severe accident simulation software, etc. This study integrates those software to a platform, develops visual modeling tool for Retran, NGFM90. And in this platform, a distribution calculation method is also provided for couple calculation between different software. The study will improve the design and analysis of NPP

  19. The enhancement of Ignalina NPP in design and operational safety

    International Nuclear Information System (INIS)

    Negrivoda, G.

    1999-01-01

    Enhancement of Ignalina NPP design include: core design improvements; fuel channel integrity (multiple pressure tube rupture); improvements of shutdown systems; improvements of instrumentation and control devices; containment strength and tightness; design basis accident analysis; improvements of safety and support systems; seismic safety enhancement; Year 2000 project; cracks in pipes. Enhancement of operational safety includes: quality assurance; configuration management; safety management and safety culture; emergency operating procedures; training and full scope simulator; in-service inspection; fire protection and ageing monitoring and management

  20. Experience from the Inspection of Licensees' Outage Activities, Including Fire Protection Programmes, Event Response Inspections, and the Impact of the Fukushima Daiichi NPP Accident on Inspection Programmes. Workshop Proceedings, Chattanooga, Tennessee, United States, 7-10 April 2014 - Appendix: Compilation of Survey Responses

    International Nuclear Information System (INIS)

    2014-10-01

    This appendix provides the complete compilation of responses received to the questionnaire issued in conjunction with the workshop announcements. The responses are provided as received, with changes made only to the formatting. The OECD Nuclear Energy Agency (NEA) Committee on Nuclear Regulatory Activities (CNRA) Working Group on Inspection Practices (WGIP) sponsored the 12. International Workshop on Nuclear Regulatory Inspection Activities. The workshop was hosted by the U.S. NRC, in Chattanooga, Tennessee, United States of America on 7 -10 April 2014. The three workshop topics that were addressed were as follows: - Inspection of Outage Activities Including Fire Protection Programmes. - Event Response Inspections. - The Impact of Inspection Programmes of the Fukushima Daiichi NPP Accident. Each of the respondents was given the following instructions in relation to their response: - Only one response per country is required. If more than one person from your country is participating, please co-ordinate the responses accordingly. - Please provide responses on separate sheet and clearly identify the questionnaire part and topic. For preparation of the workshop, participants are invited to supply their national inspection approaches used in inspection of events and incidents according to the surveys. Actual issues that were discussed during the workshop were generated by the topic leaders based on the responses submitted by participants with their registration forms. This formats helps to ensure that issues considered most important by the workshop participants are covered during the group discussions. (authors)

  1. Approach to accident management in RBMK-1500

    International Nuclear Information System (INIS)

    Kaliatka, A.; Urbonavicius, E.; Uspuras, E.

    2008-01-01

    In order to ensure the safe operation of the nuclear power plants accident management programs are being developed around the world. These accident management programs cover the whole spectrum of accidents, including severe accidents. A lot of work is done to investigate the severe accident phenomena and implement severe accident management in NPPs with vessel-type reactors, while less attention is paid to channel-type reactors CANDU and RBMK. Ignalina NPP with RBMK-1500 reactor has implemented symptom based emergency operation procedures, which cover management of accidents until the core damage and do not extend to core damage region. In order to ensure coverage of the whole spectrum of accidents and meet the requirements of IAEA the severe accident management guidelines have to be developed. This paper presents the basic principles and approach to management of beyond design basis accidents at Ignalina NPP. In general, this approach could be applied to NPPs with RBMK-1000 reactors that are available in Russia, but the design differences should be taken into account

  2. The Effect of NPP's Stack Height to Radiation Dose

    International Nuclear Information System (INIS)

    Pandi, Liliana Yetta; Rohman, Budi

    2003-01-01

    The purpose of dose calculation for accidents is to analyze the capability of NPP to maintain the safety of public and workers in case an accident occurs on the Plant in a site. This paper calculates the Loss of Coolant Accident in PWR plant. The calculation results shows that no risks of serious radiation exposure are given to the neighboring public even if such a large accident occurred, and the effect of stack height can be predicted by analysis of the calculation results. The whole dose is calculated for some location (100 m, 300 m, 500 m, 700 m, 900 m, 1500 m, and 2000 m) with three difference stack height i.e. 0 m, 40 m and 100 m. The result of the whole dose calculation is under permitted criteria for whole dose : 0.25 Sv and thyroid dose : 3.0 Sv. The calculation of radiation dose in this paper use EEDCDQ code

  3. Dutch National Plan combat nuclear accidents

    International Nuclear Information System (INIS)

    1988-01-01

    This document presents the Dutch National Plan combat nuclear accidents (NPK). Ch. 2 discusses some important starting points which are determining for the framework and the performance of the NPK, in particular the accident typology which underlies the plan. Also the new accident-classification system for the Dutch nuclear power plants, the standardization for the measures to be taken and the staging around nuclear power plants are pursued. In ch. 3 the legal framework of the combat nuclear accidents is described. In particular the Nuclear-power law, the Accident law and the Municipality law are pursued. Also the role of province and municipality are described. Ch. 4 deals with the role of the owner/licensee of the object where the accident occurs, in the combat of accident. In ch. 5 the structure of the nuclear-accident combat at national level is outlined, subdivided in alarm phase, combat phase and the winding-up phase. In ch.'s 6-12 these phases are elaborated more in detail. In ch.'s 10-13 the measures to be taken in nuclear accidents, are described. These measures are distinguished with regard to: protection of the population and medical aspects, water economy, drinking-water supply, agriculture and food supply. Ch. 14 describes the responsibility of the burgomaster. Ch.'s 15 and 16 present an overview of the personnel, material, procedural and juridical modifications and supplements of existing structures which are necessary with regard to the new and modified parts of the structure. Ch. 17 indicates how by means of the appropriate education and exercise it can be achieved that all personnel, services and institutes concerned possess the knowledge and experience necessary for the activities from the NKP to be executed as has been described. Ch. 18 contains a survey of activities to be performed and a proposal how these can be realized. (H.W.). figs.; tabs

  4. Cernavoda NPP Knowledge Transfer

    International Nuclear Information System (INIS)

    Valache, C. M.

    2016-01-01

    Full text: The paper presents a description of the Knowledge Transfer (KT) process implemented at Cernavoda NPP, its designing and implementation. It is underlined that applying a KT approach should improve the value of existing processes of the organization through: • Identifying business, operational and safety risks due to knowledge gaps, • Transfer of knowledge from the ageing workforce to the peers and/or the organization, • Continually learning from successes and failures of individual or teams, • Convert tacit knowledge to explicit knowledge, • Improving operational and safety performance through creating both new knowledge and better access to existing knowledge. (author

  5. Operation safety at Ignalina NPP

    International Nuclear Information System (INIS)

    Zheltobriukh, G.

    1999-01-01

    An improvement of operational safety at Ignalina NPP covers: improvement of management structure and safety culture; symptom-based emergency operating procedures; staff training and full scope simulator; program of components ageing; metal inspection; improvement of fire safety. The first plan of Ignalina NPP Safety culture development for 1997 purposed to the SAR recommendation implementation was prepared and approved by the General Director

  6. Preparation for Ignalina NPP decommissioning

    International Nuclear Information System (INIS)

    Medeliene, D.

    2004-01-01

    Latest developments of atomic energy in Lithuania, works done to prepare Ignalina NPP for final shutdown and decommissioning are described. Information on decommissioning program for Ignalina NPP unit 1, decommissioning method, stages and funding is presented. Other topics: radiation protection, radioactive waste management and disposal. Key facts related to nuclear energy in Lithuania are listed

  7. Accidents - Chernobyl accident

    International Nuclear Information System (INIS)

    2004-01-01

    This file is devoted to the Chernobyl accident. It is divided in four parts. The first part concerns the accident itself and its technical management. The second part is relative to the radiation doses and the different contaminations. The third part reports the sanitary effects, the determinists ones and the stochastic ones. The fourth and last part relates the consequences for the other European countries with the case of France. Through the different parts a point is tackled with the measures taken after the accident by the other countries to manage an accident, the cooperation between the different countries and the groups of research and studies about the reactors safety, and also with the international medical cooperation, specially for the children, everything in relation with the Chernobyl accident. (N.C.)

  8. Revision of the AESJ Standard for Seismic Probabilistic Risk Assessment (PRA). Updating requirements based on the lessons learned from the Fukushima Dai-ichi NPP Accidents (3). Fragility evaluation and outline of the updated points

    International Nuclear Information System (INIS)

    Yamaguchi, Akira; Nakamura, Susumu; Mihara, Yoshinori

    2014-01-01

    Lessons learned from Great East Japan earthquake and other new findings had been accumulated on the fragility evaluation of buildings and components. And also new analysis and evaluation method had been proposed with the advancement of recent analysis and evaluation technology. These were reflected in revision of the AESJ Standard for Seismic Probabilistic Risk Assessment (PRA). Scope of the fragility evaluation were extended to all equipment on the site, severe accident management equipment including portable equipment and earthquake concomitant incident (such as tsunami) countermeasure equipment. This article described outlines of updating points of the fragility evaluation of the AESJ Standard for Seismic PRA; (1) requirements for seismic induced other risk evaluations such as fire, inundation and tsunami, (2) simulation technology based on recent findings such as three dimensional responses of buildings / structures and its effect on equipment, (3) requirements of the fragility evaluation for various failure mode of several equipment such as severe accident management equipment, fine failure mode of buildings / structures, failures of equipment related with earthquake concomitant incidents (embankment and seawall) and spent fuel pool, and (4) requirements for the fragility evaluation of aftershocks and soil deformation due to fault displacement. (T. Tanaka)

  9. Challenges and Enhancements to Defence-in-Depth (DiD) in Light of the Fukushima Daiichi NPP Accident. Proceedings of a Joint CNRA/CSNI Workshop, Paris, France, 5 June 2013

    International Nuclear Information System (INIS)

    Niel, Jean-Christophe; Autorite de surete nucleaire - ASN; ); Echavarri, Luis; ); Schneider, Thierry; ); Borchardt, Bill; Wanner, Hans; Park, Youn Won; Glenn, Tracy; Regaldo, Jacques; Fuketa, Toyoshi; Repussard, Jacques; Bolshov, Leonid; Chevet, Pierre Frank

    2014-01-01

    An international Workshop on Challenges and Enhancements to Defence in Depth (DiD) in Light of the Fukushima Daiichi Accident was jointly organised by the NEA Committee on Nuclear Regulatory Activities (CNRA) and the NEA Committee on the Safety on Nuclear Installations (CSNI), with input from the NEA Committee on Radiation Protection and Public Health (CRPPH), on 5 June 2013 in Paris. About 100 participants from NEA member countries, India, the International Atomic Energy Agency (IAEA), the World Association of Nuclear Operators (WANO) and Eurelectric held in-depth discussions on the defence-in-depth concept and its implementation in the post-Fukushima context. They also considered additional steps to be taken at the national and international levels to address the challenges identified and to make further enhancements to nuclear safety, along with future NEA activities in support of these processes. The concept of DiD - of multiple levels of protection - has been developed and refined by the nuclear safety community over many years. The concept is based on the experience and practice of high hazard industry in general as well as developments within the nuclear industry. The accident at the Fukushima Daiichi Nuclear Power Station in Japan on the 11 March 2011 demonstrated the importance of the concept of DiD, how these multiple levels of protection can operate and how some can be challenged. Just as with the nuclear accidents at Three Mile Island and Chernobyl and accidents from other industries (e.g. chemical, aerospace, oil and gas), the NEA felt it important that lessons learned are used to further develop the concept and implementation of Defence-in-Depth to help ensure and enhance the safe operation of nuclear power plants around the world. The NEA has therefore looked at the concept and implementation of Defence-in-Depth and possible challenges and enhancements. It was noted that a great deal of interest has been shown in this area, particularly in the

  10. NPP unusual events: data, analysis and application

    International Nuclear Information System (INIS)

    Tolstykh, V.

    1990-01-01

    Subject of the paper are the IAEA cooperative patterns of unusual events data treatment and utilization of the operating safety experience feedback. The Incident Reporting System (IRS) and the Analysis of Safety Significant Event Team (ASSET) are discussed. The IRS methodology in collection, handling, assessment and dissemination of data on NPP unusual events (deviations, incidents and accidents) occurring during operations, surveillance and maintenance is outlined by the reports gathering and issuing practice, the experts assessment procedures and the parameters of the system. After 7 years of existence the IAEA-IRS contains over 1000 reports and receives 1.5-4% of the total information on unusual events. The author considers the reports only as detailed technical 'records' of events requiring assessment. The ASSET approaches implying an in-depth occurrences analysis directed towards level-1 PSA utilization are commented on. The experts evaluated root causes for the reported events and some trends are presented. Generally, internal events due to unexpected paths of water in the nuclear installations, occurrences related to the integrity of the primary heat transport systems, events associated with the engineered safety systems and events involving human factor represent the large groups deserving close attention. Personal recommendations on how to use the events related information use for NPP safety improvement are given. 2 tabs (R.Ts)

  11. Postulated accidents

    International Nuclear Information System (INIS)

    Ullrich, W.

    1980-01-01

    This lecture on 'Postulated Accidents' is the first of a series of lectures on the dynamic and transient behaviour of nuclear power plants, especially pressurized water reactors. The main points covered will be: Reactivity Accidents, Transients (Intact Loop) and Loss of Cooland Accidents (LOCA) including small leak. This lecture will discuss the accident analysis in general, the definition of the various operational phases, the accident classification, and, as an example, an accident sequence analysis on the basis of 'Postulated Accidents'. (orig./RW)

  12. IPEEE Review of other external events of the NPP Asco; Revision del IPEEE de sucesos externos de C.N. Asco

    Energy Technology Data Exchange (ETDEWEB)

    Canadell, F.; Aleman, A.; Beltran, F.; Pifarre, D.; Hernandez, H.; Gasca, C.

    2011-07-01

    Within the process of maintaining and updating the risk analysis of the NPP Asco, results from the review of the vulnerability study of the plant against severe accidents caused by external success (Individual Plant Examination of External Events, IPEEE).

  13. The challenge of backup power in the NPP after the accident at Fukushima, alternatives; El reto de la energia de resplado en las CC.NN. despues del accidente de Fukushima, alternativas

    Energy Technology Data Exchange (ETDEWEB)

    Contreras, C.; Gomez, A.; Gavilan, C.; Archilla, J.; Tagle, J. A.

    2014-07-01

    After the accident in Fukushima has been demonstrated the importance of having in the first hours with an independent power supply of the emergency diesel generators. In conclusion it can be said that usual (Pb batteries) storage technology is insufficient, since much more space in the rooms would be needed to achieve the required stored energy. And although just appear on the market solutions alternatives, the most advanced battery technologies still have some problems to be able to use in these applications with guarantees. A solution that arises is the combination of batteries and fuel cells. On the other hand is needed a closer collaboration with researchers and developers of batteries so that they take into account the needs of plants, so that manufactured batteries with more density energy, more power and they are more reliable. These features provide benefits in other fields besides nuclear plants. (Author)

  14. Severe accident training simulator APROS SA

    International Nuclear Information System (INIS)

    Raiko, Eerikki; Salminen, Kai; Lundstroem, Petra; Harti, Mika; Routamo, Tomi

    2003-01-01

    APROS SA is a severe accident training simulator based on the APROS simulation environment. APROS SA has been developed in Fortum Nuclear Services Ltd to serve as a training tool for the personnel of the Loviisa NPP. Training with APROS SA gives the personnel a deeper understanding of the severe accident phenomena and thus it is an important part of the implementation of the severe accident management strategy. APROS SA consists of two parts, a comprehensive Loviisa plant model and an external severe accident model. The external model is an extension to the Loviisa plant model, which allows the simulation to proceed into the severe accident phase. The severe accident model has three submodels: the core melting and relocation model, corium pool model and fission product model. In addition to these, a new thermal-hydraulic solver is introduced to the core region of the Loviisa plant model to replace the more limited APROS thermal-hydraulic solver. The full APROS SA training simulator has a graphical user interface with visualizations of both severe accident management panels at the operator room and the important physical phenomena during the accident. This paper describes the background of the APROS SA training simulator, the severe accident submodels and the graphical user interface. A short description how APROS SA will be used as a training tool at the Loviisa NPP is also given

  15. The Fukushima accident

    International Nuclear Information System (INIS)

    Maqua, M.; Stueck, R.

    2012-01-01

    On 11 March 2011, the Tohoku earthquake and the subsequent tsunami hit the Japanese east coast, causing more than 15,000 fatalities. To this date, 3,000 people are still missing. The Fukushima Dai-ichi NPP was the nuclear installation that was most affected by the tsunami. The earthquake cut off the NPP from the national grid. About 45 minutes later, the tsunami flooded units 1-4 and led to core meltdown events with large releases for units 1, 2 and 3. Unit 4 had been in refuelling outage at that time and lost the cooling of the spent fuel pool for several days. Considerable hydrogen explosions occurred in units 1, 3 and 4. Shortly after the accident, TEPCO started to mitigate the consequences of the accident by providing external cooling to the reactors and by removing the radioactive debris from the site. Great emphasis was laid on effective radiation protection measures for the clean-up workers. Thus, up to now there has been no fatality due to the radiation caused by the Fukushima accident. The main steps of the accident sequences are described, taking into account the latest findings of investigations performed by TEPCO or on behalf of the regulatory body. The presentation focuses on the description of the status of the Fukushima Dai-ichi nuclear power plant and the future steps for cleaning-up the site. In the presentation, the major phases of the roadmap that TEPCO has developed for the clean-up are highlighted. The risks associated with the current plant status and the clean-up phases are described. Abstract the content of the manuscript in a few lines.

  16. Effect of natural circulation on RCS depressurization strategy in PWR NPP

    International Nuclear Information System (INIS)

    Zhang Kun; Tong Lili; Cao Xuewu

    2009-01-01

    The natural circulation model of Chinese Qinshan Nuclear Power Plant (NPP) Unit 2 is built using SCDAP/RELAP5 code. Selecting TMLB' accident as the base sequence, this paper analyzes the natural circulation phenomena in high-pressure core melt severe accident. In order to study the effect of natural circulation on RCS depressurization strategy, the accident progressions of RCS depressurization with and without natural circulation are simulated, respectively. According to the results, the natural circulation can delay the initiation of RCS depressurization and the whole accident progression, but it does not evidently influence the results of RCS depressurization. (authors)

  17. Assessment of the event at Rovno NPP owing to the unexpected opening and obstruction of the safety valve lock mechanism of the pressure compensator

    International Nuclear Information System (INIS)

    Alonso, C.

    1993-01-01

    The main objective of this analysis is to be able to identify the sequence of the accident and evaluate the real frequency observed in similar nuclear power plants, according to the experience registered in the data bases of the NPP accident information system (ISI-AES) as well as the quality assurance information system (ISKO). This work describes how the analysis of events in a VVER-440 reactor NPP was performed

  18. Radiation accidents and defence of population

    International Nuclear Information System (INIS)

    Memmedov, A.M.

    2002-01-01

    Full text: Development of nuclear physics, the fundamental and the applied researches in the field of radioactive insured wide possibility for application of radionuclides and ionizing radiation source in the different fields of national economy. Application of radionuclides in chemical, metallurgical, food industry, in agriculture and etc. Fields provide a large economic profit. It's hard to apprise significance of ionizing radiation source using in medicine for diagnostics and treatment of different disease. Nuclear power engineering and nuclear industry are developing intensively. At same time nuclear power, ionizing radiation sources incur potential treat for surroundings and health of population. As even that stage of protective measure development: there is no possibility of that happening of radiation accidents. A radiation accident qualifies as loss of ionizing radiation sources direction, which provoked by disrepair equipment, natural calamity or other causes which could bring to unplanned irradiation of population or radioactive pollution of surroundings. At present some following typical cases connected with radiation accident have been chosen: Contentious using or keeping of ionizing radiation source with breach of established requires; Loss, theft of ionizing radiation sources or radiation plants, instruments; Leaving the sources of ionizing radiation in the holes; Refusal radiation technic exploited in industry, medicine, SRI and etc; Disrepair in nuclear transport means of conveyance; Crashes and accidents at NPP and at other enterprises of nuclear industry. The radiation accidents according to character, degree and scales have been divided into two groups: Radiation accidents not connected with NPP; Accidents in the nuclear engineering and industry; The radiation accidents not connected with NPP according their consequence divide into 5 groups; accidents which do not come to irradiation of personal, persons from population (more PN-permissible norm

  19. NPP Prevlaka - Preparation of construction

    International Nuclear Information System (INIS)

    Bojic, K.

    1984-01-01

    On the basis of study 'Optimal electricity generation structure till the year 2000' production of 3 x 500 MWe in nuclear power plants has been anticipated. Second Croatian-Slovenian NPP project will be based on the same principles the first one (NPP Krsko) was based on. Preconstruction investigation studies are performed at site Prevlaka on river Sava downstream of Zagreb. Licensing procedure has started with republic Urban countryside planning activities. Preconstruction activities are planned to be finished by the end of 1986. while the construction is expected to start during 1987. Parallel to investigation studies for NPP Prevlaka, evaluation of nuclear technology and reactor type is planned to be made. (author)

  20. The seismic reassessment Mochovce NPP

    International Nuclear Information System (INIS)

    Baumeister, P.

    2004-01-01

    The design of Mochovce NPP was based on the Novo-Voronez type WWER-440/213 reactor - twin units. Seismic characteristic of this region is characterized by very low activity. Mochovce NPP site is located on the rock soil with volcanic layer (andesit). Seismic reassessment of Mochovce NPP was done in two steps: deterministic approach up to commissioning confirmed value Horizontal Peak Ground Acceleration HPGA=0.1 g and activities after commissioning as a consequence of the IAEA mission indicate higher hazard values. (author)

  1. Technology for NPP decantate treatment realized at Kola NPP

    International Nuclear Information System (INIS)

    Stakhiv, Michael; Avezniyazov, Slava; Savkin, Alexander; Fedorov, Denis; Dmitriev, Sergei; Kornev, Vladimir

    2007-01-01

    At Moscow SIA 'Radon' jointly with JSC 'Alliance Gamma', the technology for NPP Decantate Treatment was developed, tested and realized at Kola NPP. This technology consists of dissolving the salt residue and subsequent treatment by ozonization, separation of the deposits formed from ozonization and selective cleaning by ferro-cyanide sorbents. The nonactive salt solution goes to an industrial waste disposal site or a repository specially developed at NPP sites for 'exempt waste' products by IAEA classification. This technology was realized at Kola NPP in December 2006 year. At this time more than 1000 m 3 of decantates log time stored are treated. It allows solving very old problem to empty decantates' tanks at NPPs in environmentally safe manner and with high volume reduction factor. (authors)

  2. NPOESS Preparatory Project (NPP) Science Overview

    Science.gov (United States)

    Butler, James J.

    2011-01-01

    NPP Instruments are: (1) well understood thanks to instrument comprehensive test, characterization and calibration programs. (2) Government team ready for October 25 launch followed by instrument activation and Intensive Calibration/Validation (ICV). NPP Data Products preliminary work includes: (1) JPSS Center for Satellite Applications and Research (STAR) team ready to support NPP ICV and operational data products. (2) NASA NPP science team ready to support NPP ICV and EOS data continuity.

  3. Workflow in Almaraz NPP

    International Nuclear Information System (INIS)

    Gonzalez Crego, E.; Martin Lopez-Suevos, C.

    2000-01-01

    Almaraz NPP decided to incorporate Workflow into its information system in response to the need to provide exhaustive follow-up and monitoring of each phase of the different procedures it manages. Oracle's Workflow was chosen for this purpose and it was integrated with previously developed applications. The objectives to be met in the incorporation of Workflow were as follows: Strict monitoring of procedures and processes. Detection of bottlenecks in the flow of information. Notification of those affected by pending tasks. Flexible allocation of tasks to user groups. Improved monitoring of management procedures. Improved communication. Similarly, special care was taken to: Integrate workflow processes with existing control panels. Synchronize workflow with installation procedures. Ensure that the system reflects use of paper forms. At present the Corrective Maintenance Request module is being operated using Workflow and the Work Orders and Notice of Order modules are about to follow suit. (Author)

  4. The Chernobyl NPP decommissioning: Current status and alternatives

    International Nuclear Information System (INIS)

    Mikolaitchouk, H.; Steinberg, N.

    1996-01-01

    After the Chernobyl accident of April 26, 1986, many contradictory decisions were taken concerning the Chernobyl nuclear power plant (NPP) future. The principal source of contradictions was a deadline for a final shutdown of the Chernobyl NPP units. Alterations in a political and socioeconomic environment resulted in the latest decision of the Ukrainian Authorities about 2000 as a deadline for a beginning of the Chernobyl NPP decommissioning. The date seems a sound compromise among the parties concerned. However, in order to meet the data a lot of work should be done. First of all, a decommissioning strategy has to be established. The problem is complicated due to both site-specific aspects and an absence of proven solutions for the RBMK-type reactor decommissioning. In the paper the problem of decommissioning option selection is considered taking into account an influence of the following factors: relevant legislative and regulatory requirements; resources required to carry out decommissioning (man-power, equipment, technologies, waste management infrastructure, etc.); radiological and physical status of the plant, including structural integrity and predictable age and weather effects; impact of planned activities at the destroyed unit 4 and within the 30-km exclusion zone of the Chernobyl NPP; planed use of the site; socio-economic considerations

  5. Key developments in the advanced NPP with WWER-640/V-407 reactor plant design

    International Nuclear Information System (INIS)

    Dragunov, Yu.G.; Mokhov, V.A.; Nikitenko, M.P.; Afrov, A.M.

    1999-01-01

    The report covers the main design features of advanced NPP equipped with WWER-640 reactor, that take into account the up-to-date approaches in the process of forming safety concepts. An approach to accident management has been analysed, beyond design-basis accidents included. A description of principal safety systems has been presented as well as the interrelation of their operation. The principal features of the systems design have been shown. (author)

  6. Annual activity report of Ignalina NPP Safety Analysis Group for 1996 year

    International Nuclear Information System (INIS)

    Ushpuras, E.; Augutis, J.; Bubelis, E.

    1997-03-01

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1996 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system. Ignalina Safety Analysis Report was prepared on the basis of these results. 37 refs., 9 tabs., 96 figs

  7. Shock absorber in Ignalina NPP

    International Nuclear Information System (INIS)

    Bulavas, A.; Muralis, J.

    1996-09-01

    Theoretical calculation and experimental analysis of models of shock absorber in Ignalina NPP is presented. The results obtained from the investigation with model of shock absorber coincide with the theoretical calculation. (author). 2 figs., 3 refs

  8. Dukovany NPP - Safely 16 TERA

    International Nuclear Information System (INIS)

    Vlcek, J.

    2008-01-01

    In this presentation increasing of power output of the Dukovany NPP is reviewed. To operate all Dukovany Units safely with the perspective of long-term operation (LTO) of 50 - 60 years it is proposed.

  9. Modernization programme at Dukovany NPP

    International Nuclear Information System (INIS)

    Trnka, M.

    2000-01-01

    The main goal of each NPP is to produce electricity safely, economically and without influence to environment. For Dukovany NPP it means to upgrade all documentation and perform the Equipment Upgrading Programme. All these activities are time and money consuming and therefore the determination of priority of all items was necessary. In the presentation there are mentioned some important changes in documentation, results of PSA studies and reason for Equipment Upgrading Programme performance. It was selected the most important item from the list of Equipment Upgrading Programme the I and C upgrading. Management has decided that Dukovany NPP will become among the best NPPs with WWER type of reactor. It seems this decision is the best way how to extend lifetime of the NPP. (author)

  10. Radiobiological effects in organisms of plants and animals exposed to ionizing irradiation in the Chernobyl NPP zone

    International Nuclear Information System (INIS)

    Panchenko, N.A.; Arkhipov, N.P.; Alesina, M.Y.; Kuchma, V.I.; Gaschak, S.P.; Burov, N.I.

    1997-01-01

    Influence of ionizing radiation on forest ecosystems most clearly revealed itself near the Chernobyl NPP (ChNPP), were magnitudes of absorbed doses reached 'lethal' values, as applied to conifers. Main contribution to absorbed dose was due to beta-radiation of short-living radionuclides. To largest extent the radiobiological effects appeared at injured plantations of pines and firs. Nevertheless, during the first year maximum absorbed doses influenced also on leaf-bearing trees (birch, alder, asp) which then rehabilitated themselves completely

  11. Ideal scaling of BETHSY 9.1.B test results to NPP

    International Nuclear Information System (INIS)

    Petelin, S.; Guntel, I.

    1995-01-01

    The transient scenario standard problem 27 (ISP-27) was implemented in the RELAP5 analysis of small break loss of coolant accident for Krsko nuclear power plant (Krsko NPP). The objective was to evaluate the effectiveness of ISP-27 proposed accident management procedure for real NPP and to compare the physical phenomena known from experimental background with the phenomena predicted by RELAP5 simulation of real plant transient. The analyses showed that, if relevant break, power scaling criteria, primary and secondary pressure are fulfilled the RELAP5 model of Krsko NPP cannot completely ensure the simulation of typical thermal-hydraulic phenomena observed in BETHSY facility during ISP-27. Much better satisfaction is observed on ideal scaled up model. (author)

  12. Measuring Risk Aversion for Nuclear Power Plant Accident: Results of Contingent Valuation Survey in Korea

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Kang, Hyun Gook

    2015-01-01

    Within the evaluation of the external cost of nuclear energy, the estimation of the external cost of nuclear power plant (NPP) severe accident is one of the major topics to be addressed. For the evaluation of the external cost of NPP severe accident, the effect of public risk averse behavior against the group accidents, such as NPP accident, dam failure, must be addressed. Although the equivalent fatalities from a single group accident are not common and its risk is very small compared to other accidents, people perceive the group accident more seriously. In other words, people are more concerned about low probability/high consequence events than about high probability/low consequence events having the same mean damage. One of the representative method to integrate the risk aversion in the external costs of severe nuclear reactor accidents was developed by Eeckoudt et al., and he used the risk aversion coefficient, mainly based on the analysis of financial risks in the stock markets to evaluate the external cost of nuclear severe accident. However, the use of financial risk aversion coefficient to nuclear severe accidents is not appropriate, because financial risk and nuclear severe accident risk are entirely different. In this paper, the individual-level survey was conducted to measure the risk aversion coefficient and estimate the multiplication factor to integrate the risk aversion in the external costs of NPP severe accident. This study propose an integrated framework on estimation of the external cost associated with severe accidents of NPP considering public risk aversion behavior. The theoretical framework to estimate the risk aversion coefficient/multiplication factor and to assess economic damages from a hypothetical NPP accident was constructed. Based on the theoretical framework, the risk aversion coefficient can be analyzed by conducting public survey with a carefully designed lottery questions. Compared to the previous studies on estimation of the

  13. Measuring Risk Aversion for Nuclear Power Plant Accident: Results of Contingent Valuation Survey in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Hun; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

    2015-05-15

    Within the evaluation of the external cost of nuclear energy, the estimation of the external cost of nuclear power plant (NPP) severe accident is one of the major topics to be addressed. For the evaluation of the external cost of NPP severe accident, the effect of public risk averse behavior against the group accidents, such as NPP accident, dam failure, must be addressed. Although the equivalent fatalities from a single group accident are not common and its risk is very small compared to other accidents, people perceive the group accident more seriously. In other words, people are more concerned about low probability/high consequence events than about high probability/low consequence events having the same mean damage. One of the representative method to integrate the risk aversion in the external costs of severe nuclear reactor accidents was developed by Eeckoudt et al., and he used the risk aversion coefficient, mainly based on the analysis of financial risks in the stock markets to evaluate the external cost of nuclear severe accident. However, the use of financial risk aversion coefficient to nuclear severe accidents is not appropriate, because financial risk and nuclear severe accident risk are entirely different. In this paper, the individual-level survey was conducted to measure the risk aversion coefficient and estimate the multiplication factor to integrate the risk aversion in the external costs of NPP severe accident. This study propose an integrated framework on estimation of the external cost associated with severe accidents of NPP considering public risk aversion behavior. The theoretical framework to estimate the risk aversion coefficient/multiplication factor and to assess economic damages from a hypothetical NPP accident was constructed. Based on the theoretical framework, the risk aversion coefficient can be analyzed by conducting public survey with a carefully designed lottery questions. Compared to the previous studies on estimation of the

  14. Radiation accident at the South Urals in 1957

    International Nuclear Information System (INIS)

    Nikipelov, B.V.; Romanov, G.N.; Buldakov, L.A.; Babaev, N.S.; Kholina, Yu.B.; Mikerin, E.I.

    1989-01-01

    Radiation accidents with release of radioactive substances into environment which took place in the South Ural in 1957 is evaluated. Scientific researches conducted since 1957 are described. Scientific data of unique fundamental and applied value were obtaibed. Recommendations for the organization and content of radiation sanctuary are developed. Scientific researches permitted to make reliable long-turm prediction of radiation situation developed owing to the Chernobyl NPP accident and to work out practical recommendations so as to reduce adverse aftereffects of the accident

  15. The ASSET service. Will another accident occur in the nuclear industry? In which country? When?

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, B [International Atomic Energy Agency, Vienna (Austria)

    1997-10-01

    The presentation discusses the following issues: prevention of accidents at nuclear power plants(NPP); promotion of self assessment of NPP safety; guidance of self assessment; the ASSET methodology; plant defence in depth; safety culture; operating experience feedback;guidance for ASSET peer-review; ASSET missions conducted at the request of the IAEA member states.

  16. The ASSET service. Will another accident occur in the nuclear industry? In which country? When?

    International Nuclear Information System (INIS)

    Thomas, B.

    1997-01-01

    The presentation discusses the following issues: prevention of accidents at nuclear power plants(NPP); promotion of self assessment of NPP safety; guidance of self assessment; the ASSET methodology; plant defence in depth; safety culture; operating experience feedback;guidance for ASSET peer-review; ASSET missions conducted at the request of the IAEA member states

  17. Analysis of the radioactive aerosols sampled with Lepestok respirators during work in the Chernobyl' NPP region

    International Nuclear Information System (INIS)

    Borisova, L.I.; Polevov, V.N.; Borisov, N.B.; Basmanov, P.I.

    1989-01-01

    Aerosols sampled with Lepestok type respirators in the Chernobyl' NPP region following the accident were analysed by gamma-spectroscopic and optical-radiographic methods and nuclide ratio of the aerosol sediment after respirators usage were determined. Parameters of the sampled gamma-active aerosol particles were obtained. ref. 1; tabs. 3

  18. Modelling of distribution of emissions from point source on the territory of the Belarusian NPP

    International Nuclear Information System (INIS)

    Cherkasova, V.V.; Smirnova, T.V.

    2016-01-01

    The work is devoted to the numerical assessment of the possible spread of emissions on the territory of the Belarusian NPP considering the wind pattern of the area in question. The results will help to develop draft guidelines for the operator to response to nuclear radiation accident. (authors)

  19. Unmanned aerial complexes as a way of NPP and environment radiation monitoring

    International Nuclear Information System (INIS)

    Babak, V.P.; Kanchenko, V.A.; Klyuchnikov, A.A.; Krasnov, V.A.; Chepur, N.L.

    2012-01-01

    As a example of the using of unmanned aircraft for video monitoring and radiation background measurement in the accident area at the NPP Fukushima -1 are shown the efficiency of its use. The analyse of possible environmental monitoring remotely piloted ultralight unmanned aerial vehicle are carried out

  20. Results from modernization of the containment localization systems of the Kozloduy NPP units 3 and 4

    International Nuclear Information System (INIS)

    Sabinov, S.

    2005-01-01

    The improvements of the Accident Localization System (SLA) of units 3 and 4 systematically implemented by Kozloduy NPP shows an important direction for increasing the safety of NPP with WWER-440/V-230 containments. During the years Kozloduy NPP implemented a large scope of activities aimed in full resolution of all generic shortcomings identified in the original design of these containments. These activities allowed already in 2002 to justify that integrity of the containment is assured for all postulated events and the radiological consequences for all DBAs and BDBAs without core degradation are within the regulatory limits. The last phase of this modernization was oriented toward achieving the same goals in case of severe accidents by installation of systems for avoiding long term pressurization of the SG compartments and by installation of a system for keeping of negative pressure (slight vacuum) during the late phases of development of the accidents thus minimizing significantly the uncontrolled radioactive releases from the containment and assured controlled purified release of radioactivity to environment, and for elimination of conditions for H2 deflagration within the localization system. This paper summarizes the results of the whole modernization process with an emphasis of the implementation of the latest phase successfully completed by Kozloduy NPP in first quarter of 2005 which allowed the plant to demonstrate remarkable mitigation capability for a comprehensive set of very low probability severe accidents scenarios in line with the approach now being promoted for the modern design NPPs

  1. Development of the model MAAP5-DOSE for dose analysis in Cofrentes NPP

    International Nuclear Information System (INIS)

    Gonzalez, C.; Diaz, P.; Ibanez, L.; Lamela, B.; Serrano, C.

    2013-01-01

    Iberdrola Ingenieria y Construccion has developed a model of Cofrentes NPP with code MAAP5-DOSE in order to be able to assess in realistic conditions the the expected dose in points and radiological consequences of severe accident of local action.

  2. Social problems and territorial experiences from closing down Tihange NPP

    International Nuclear Information System (INIS)

    Lizin, A.M.

    2000-01-01

    The town of Huy, better known by the name of the NPP Tihange, which is the nearby village, accounts to 50,000 inhabitants including the surrounding region. An Advisory Committee at a community level was set up concerned with the emergency services and the NPP related problems. One of the outstanding problems is the planned interim storage for radioactive waste. The unsolved question of long term storage in Belgium resulted in the fact that general situation is not promising for launching the debate on the future of nuclear energy. The mission of the delegation from Huy visited Tokaimura with the aim to measure the scale of real responsibilities and the concern against nuclear power that the accident created in the population

  3. 'Kozloduy' NPP geological environment as a barrier against radionuclide migration

    International Nuclear Information System (INIS)

    Antonov, D.

    2000-01-01

    The aim of this report is to present an analysis of the geological settings along Kozloduy NPP area from the viewpoint of a natural, protective barrier against unacceptable radionuclides migration in the environment. Possible sources of such migration could be an eventual accident in an active nuclear plant; radioactive releases from decommissioned Power Units or from temporary or permanent radioactive waste repositories. The report is directed mainly to the last case, and especially to the site selection for near surface short lived low and intermediate level (LILW) radioactive repository. The main conclusion of the geological settings assessment and of the many years monitoring is that the Kozloduy NPP area offers good possibilities for site selection of LILW repository. (author)

  4. Safety analysis of Ignalina NPP during shutdown conditions

    International Nuclear Information System (INIS)

    Kaliatka, A.; Uspuras, E.

    2000-01-01

    The accident analysis for the Ignalina NPP with RBMK-1500 reactors at normal operating conditions and at minimum controlled power level (during startup of the reactor) has been performed in the frame of the project I n-Depth Safety Assessment of the Ignalina NPP , which was completed in 1996. However, the plant conditions during the reactor shutdown differ from conditions during reactor operation at full power (equipment status in protection systems, set points for actuation of safety and protection systems, etc.). Results of RELAP5 simulation of two worst initiating events during reactor shutdown - Pressure Header rupture in case of steam reactor cooldown as well as Pressure Header rupture in case of water reactor cooldown are discussed in the paper. Results of analysis shown that reactor are reliably cooled in both cases. Further analysis for all range of initial events during reactor shutdown and at shutdown conditions is recommended. (author)

  5. Application of Robotic System for Emergency Response in NPP

    International Nuclear Information System (INIS)

    Jeong, Kyung Min; Seo, Yong Chil; Shin, Ho Chul; Lee, Sung Uk; Cho, Jae Wan; Choi, Young Soo; Kim, Chang Hoi; Kim, Seung Ho

    2010-01-01

    Increasing energy demand and concerns over climate change make increasing use of nuclear power plant in worldwide. Even though the probability of accident is greatly reduced, safety is the highest priority issue in the nuclear energy industry. Applying highly reliable and conservative 'defense in depth' concepts with the design and construction of NPP, there are very little possibilities with which accidents are occur and radioactive materials are released to environments in NPP. But NPP have prepared with the emergency response procedures and conduct exercises for post-accident circumstance according to the procedures. The application of robots for emergency response task for post-accident in nuclear facilities is not a new concept. Robots have been sent to recover the damaged reactor at Chernobyl where human workers could receive a lifetime dose of radiation in minutes. Based on NRC's TMI-2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. The first robot was lowered into the basement through a hatch and human operators monitoring in a control room drove it through mud, water and debris, capturing the initial post-accident images of the reactor's basement. It was used for several years equipped with various tools allowing it to scour surfaces, scoop samples and vacuum sludge. A second version carried a core sampler to determine the intensity and depth of the radiation that had permeated into the walls. To perform cleanup tasks, they built Workhorse that featured system redundancy and had a boom extendable to reach high places, but it was never used because it had too many complexities and to clean and fix. While remote robotics technology has proven to remove the human from the radioactive environment, it is also difficult to make it useful because it may requires skill about remote control and obtaining remote

  6. Application of Robotic System for Emergency Response in NPP

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyung Min; Seo, Yong Chil; Shin, Ho Chul; Lee, Sung Uk; Cho, Jae Wan; Choi, Young Soo; Kim, Chang Hoi; Kim, Seung Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    Increasing energy demand and concerns over climate change make increasing use of nuclear power plant in worldwide. Even though the probability of accident is greatly reduced, safety is the highest priority issue in the nuclear energy industry. Applying highly reliable and conservative 'defense in depth' concepts with the design and construction of NPP, there are very little possibilities with which accidents are occur and radioactive materials are released to environments in NPP. But NPP have prepared with the emergency response procedures and conduct exercises for post-accident circumstance according to the procedures. The application of robots for emergency response task for post-accident in nuclear facilities is not a new concept. Robots have been sent to recover the damaged reactor at Chernobyl where human workers could receive a lifetime dose of radiation in minutes. Based on NRC's TMI-2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. The first robot was lowered into the basement through a hatch and human operators monitoring in a control room drove it through mud, water and debris, capturing the initial post-accident images of the reactor's basement. It was used for several years equipped with various tools allowing it to scour surfaces, scoop samples and vacuum sludge. A second version carried a core sampler to determine the intensity and depth of the radiation that had permeated into the walls. To perform cleanup tasks, they built Workhorse that featured system redundancy and had a boom extendable to reach high places, but it was never used because it had too many complexities and to clean and fix. While remote robotics technology has proven to remove the human from the radioactive environment, it is also difficult to make it useful because it may requires skill about remote control and

  7. Operational behaviour of WWER nuclear power units after Chernobyl accident

    International Nuclear Information System (INIS)

    Milivojevic, S.; Spasojevic, D.

    2000-01-01

    The indicators of effectiveness of WWER operation, in 1987-1998 were analyzed. For three groups of nuclear units (WWER, NPP Kozloduy, NPP Paks), the trends of Indicators flow were established. The comparative analysis of forced outage rate, and load factor of WWERs and nuclear units all in the world was carried out; it gives the general picture of accident influence on the states and the relations of these indicators in considered period (author)

  8. External Cost Assessment of Nuclear Power Plant Accident considering Public Risk Aversion Behavior: the Korean Case

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Hun; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    The conventional approach for monetary valuation of NPP accident consequence consists of calculating the expected value of various accident scenarios. However, the main criticism of the conventional approach is that there is a discrepancy between the social acceptability of the risk and the estimated expected value of NPP accident. Therefore, an integrated framework for the estimation of the external cost associated with an NPP accident considering the public risk aversion behavior was proposed in this study based on the constructed theoretical framework for estimating both the value of statistical life (VSL) and the risk aversion coefficient associated with an NPP accident to take account of the accident cost into the unit electricity generation cost of NPP. To estimate both parameters, an individual-level survey was conducted on a sample of 1,364 participants in Korea. Based on the collected survey responses, both parameters were estimated based on the proposed framework and the external cost of NPP accident was estimated based on the consequence analysis and considering the direct cost factors for NPP accident. Internalization of external costs into the comprehensive energy production cost has been considered as a potentially efficient policy instrument for a more sustainable energy supply and use. However, the internalization of externalities, such as public health damage, have raised a number of generic policy issues in a nuclear energy sector, with specific challenges resulting from the distinct characteristics of external cost estimation. Especially, the major challenge remained to address the public safety concerns regarding a nuclear accident, which can be specified as low-probability high-consequence accident, driven by the aspects of public risk aversion.

  9. External Cost Assessment of Nuclear Power Plant Accident considering Public Risk Aversion Behavior: the Korean Case

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Kang, Hyun Gook

    2016-01-01

    The conventional approach for monetary valuation of NPP accident consequence consists of calculating the expected value of various accident scenarios. However, the main criticism of the conventional approach is that there is a discrepancy between the social acceptability of the risk and the estimated expected value of NPP accident. Therefore, an integrated framework for the estimation of the external cost associated with an NPP accident considering the public risk aversion behavior was proposed in this study based on the constructed theoretical framework for estimating both the value of statistical life (VSL) and the risk aversion coefficient associated with an NPP accident to take account of the accident cost into the unit electricity generation cost of NPP. To estimate both parameters, an individual-level survey was conducted on a sample of 1,364 participants in Korea. Based on the collected survey responses, both parameters were estimated based on the proposed framework and the external cost of NPP accident was estimated based on the consequence analysis and considering the direct cost factors for NPP accident. Internalization of external costs into the comprehensive energy production cost has been considered as a potentially efficient policy instrument for a more sustainable energy supply and use. However, the internalization of externalities, such as public health damage, have raised a number of generic policy issues in a nuclear energy sector, with specific challenges resulting from the distinct characteristics of external cost estimation. Especially, the major challenge remained to address the public safety concerns regarding a nuclear accident, which can be specified as low-probability high-consequence accident, driven by the aspects of public risk aversion

  10. NPP Decommissioning: the concept; state of activities

    International Nuclear Information System (INIS)

    Nemytov, S.; Zimin, V.

    2001-01-01

    The main principles of NPP decommissioning concept in Russia are given. The conditions with fulfillment of works on NPP unit pre-decommissioning and decommissioning including: development of the normative documentation, creation of special fund for financing NPP decommissioning activities, deriving the Gosatomnadzor license for decommissioning of shut down NPP units, development of the equipment and technologies for waste and spent fuel management are presented. The decommissioning cost and labour intensity of one WWER-440 unit are shown. The practical works, executed on shut down units at Beloyarsk NPP (Unit1 and 2) and Novo Voronezh NPP (Unit 1 and 2) are outlined

  11. Accident on the Chernobyl nuclear power plant. Getting over the consequences and lessons learned

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Prister, B.S.

    2006-01-01

    The book is devoted to the 20 anniversary of the accident on the 4th Power Unit of the Chernobyl NPP. The power plant construction history, accident reasons, its consequences, the measures on its liquidation are represented. The current state of activity on the Chernobyl power unit decommission, the 'Shelter' object conversion into the ecologically safe system is described. The future of the Chernobyl NPP site and disposal zone is discussed

  12. [The results of a cytogenetic examination of children who were victims of the accident at the Chernobyl Atomic Electric Power Station and who reside in an ecologically unfavorable region].

    Science.gov (United States)

    Frolov, V M; Baryliak, I R; Peresadin, M O; Khrypko, S V; Kuziuberdina, K M

    1994-01-01

    It has been detected that children evacuated from the zone with the elevated radioactivity level have the increased number of chromosomal and chromatid aberrations. The frequency of chromatid aberrations is 2.1-fold lower in country-side children than in children from industrial towns. Cytogenetic disturbances in immunocompetent cells correlate with the level of immune imbalance. Children born in families of liquidators of the ChNPP accident in the first year after their return from the accident zone have substantial cytogenetic and immune disturbances. Children living near sources of atmospheric pollution are characterized by the 3-4-fold increase in frequencies of chromatid anomalies and by the development of a pronounced immunodeficiency.

  13. Accident management

    International Nuclear Information System (INIS)

    Lutz, R.J.; Monty, B.S.; Liparulo, N.J.; Desaedeleer, G.

    1989-01-01

    The foundation of the framework for a Severe Accident Management Program is the contained in the Probabilistic Safety Study (PSS) or the Individual Plant Evaluations (IPE) for a specific plant. The development of a Severe Accident Management Program at a plant is based on the use of the information, in conjunction with other applicable information. A Severe Accident Management Program must address both accident prevention and accident mitigation. The overall Severe Accident Management framework must address these two facets, as a living program in terms of gathering the evaluating information, the readiness to respond to an event. Significant international experience in the development of severe accident management programs exist which should provide some direction for the development of Severe Accident Management in the U.S. This paper reports that the two most important elements of a Severe Accident Management Program are the Emergency Consultation process and the standards for measuring the effectiveness of individual Severe Accident Management Programs at utilities

  14. Kadurumba, CH

    African Journals Online (AJOL)

    Kadurumba, CH. Vol 33, No 3 (2014) - Research papers. Kinematics and Dynamic Evaluation of the Screw Conveyor of a Cassava Centrifuge Dewatering Machine Abstract PDF · Vol 33, No 3 (2014) - Research papers. Performance Optimization of a Cassava Pelleting Machine Abstract PDF. ISSN: 2467-8821. AJOL African ...

  15. Unavoidable Accident

    OpenAIRE

    Grady, Mark F.

    2009-01-01

    In negligence law, "unavoidable accident" is the risk that remains when an actor has used due care. The counterpart of unavoidable accident is "negligent harm." Negligence law makes parties immune for unavoidable accident even when they have used less than due care. Courts have developed a number of methods by which they "sort" accidents to unavoidable accident or to negligent harm, holding parties liable only for the latter. These sorting techniques are interesting in their own right and als...

  16. Containment integrity analysis under accidents

    International Nuclear Information System (INIS)

    Lin Chengge; Zhao Ruichang; Liu Zhitao

    2010-01-01

    Containment integrity analyses for current nuclear power plants (NPPs) mainly focus on the internal pressure caused by design basis accidents (DBAs). In addition to the analyses of containment pressure response caused by DBAs, the behavior of containment during severe accidents (SAs) are also evaluated for AP1000 NPP. Since the conservatism remains in the assumptions,boundary conditions and codes, margin of the results of containment integrity analyses may be overestimated. Along with the improvements of the knowledge to the phenomena and process of relevant accidents, the margin overrated can be appropriately reduced by using the best estimate codes combined with the uncertainty methods, which could be beneficial to the containment design and construction of large passive plants (LPP) in China. (authors)

  17. Surveillance of Strontium-90 in Foods after the Fukushima Daiichi Nuclear Power Plant Accident.

    Science.gov (United States)

    Nabeshi, Hiromi; Tsutsumi, Tomoaki; Uekusa, Yoshinori; Hachisuka, Akiko; Matsuda, Rieko; Teshima, Reiko

    2015-01-01

    As a result of the Fukushima Daiichi nuclear power plant (NPP) accident, various radionuclides were released into the environment. In this study, we surveyed strontium-90 ((90)Sr) concentrations in several foodstuffs. Strontium-90 is thought to be the third most important residual radionuclide in food collected after the Fukushima Daiichi, NPP accident after following cesium-137 ((137)Cs) and cesium-134 ((134)Cs). Results of (90)Sr analyses indicated that (90)Sr was detect in 25 of the 40 radioactive cesium (r-Cs) positive samples collected in areas around the Fukushima Daiichi NPP, ranging in distance from 50 to 250 km. R-Cs positive samples were defined as containing both (134)Cs and (137)Cs which are considered to be indicators of the after-effects of the Fukushima Daiichi NPP accident. We also detected (90)Sr in 8 of 13 r-Cs negative samples, in which (134)Cs was not detected. Strontium-90 concentrations in the r-Cs positive samples did not significantly exceed the (90)Sr concentrations in r-Cs negative samples or the (90)Sr concentration ranges in comparable food groups found in previous surveys before the Fukushima Daiichi NPP accident. Thus, (90)Sr concentrations in r-Cs positive samples were indistinguishable from the background (90)Sr concentrations arising from global fallout prior to the Fukushima accident, suggesting that no marked increase of (90)Sr concentrations has occurred in r-Cs positive samples as a result of the Fukushima Daiichi NPP accident.

  18. Spain in South Ukraine NPP

    International Nuclear Information System (INIS)

    Ibanez, M.

    1994-01-01

    A Technical Assistance Protocol was signed between the Governments of the GIS and the Commission of the European Union (CEU) on August 2, 1991 and this was the starting point of the TACIS program. In this article, the activities described are those related to the TACIS-92/93/94 on site technical assistance to South Ukraine NPP (SUK NPP). Within the scope of the TACIS 92 Program the CEU and the Ukrainian Authorities agreed a list of projects to be implemented at South Ukraine NPP with the aim to improve the operational safety of the plant. This part of the program is called TACIS 92 on-site activities. The total budget allocated to these projects is a MECU. The European Union ''utility'' selected to lead this program at South Ukraine NPP was UNESA and the first contract to cover our activities was signed in July 1993 between the CEU (Mr. Pablo Benavides) and UNESA (Mr. Pedro Rivero). The projects will be implemented at SUK NPP but according to the contract UNESA is ''The Consultant'' and GOSKOMATON (The Ukrainian Sate Committee on Nuclear Power Utilization) is the ''Recipient Institution''. (Author)

  19. Polish media and public opinion on NPP Mochovce commissioning

    International Nuclear Information System (INIS)

    Latek, Stanislaw

    1999-01-01

    The so called 'Mochovce Problem' was one of the major topics in Polish media in the period from May to July 1998. The nuclear power plant commissioning caused an unexpectedly strong reaction, especially in the newspapers, slightly less so in electronic media. Faced with clearly hostile media reaction to Mochovce NPP, the National Atomic Energy Agency representatives, together with atomic and nuclear experts, undertook to change these attitudes. In numerous interviews, letters to the editors and talks with journalists, they attempted to correct the mistakes, explain the true safety situation in the nuclear power plant, by whom it was constructed, who supervised and tested the systems and so on. The completion of Mochovce NPP construction improved significantly the electricity balance in Slovakia, thus decreasing the pressure for continuing the operation of older Bohunice V1 units beyond their design lifetime. For this reason, as well as in view of striving for improvement in environmental factors beyond Polish southern border, especially after Kyoto/97 decisions on greenhouse gases emissions, the public opinion in Poland should support the Mochovce NPP construction. In 1996 Poland has signed with Slovakia a bilateral inter-governmental agreement on the prompt notification on nuclear accidents and on the cooperation in the nuclear safety and radiological protection matters. On the basis of this agreement the experts from Polish National Atomic Energy Agency are in perpetual contact with Slovakian Nuclear Regulatory Body and in each and every moment can obtain full and comprehensive information on the plant parameters iportant for nuclear safety. The experts explanations, together with the NAEA top management visit to the plant itself, brought some results. The media became less aggressive, and Polish public and authorities - contrary to the Austrians - do not protest loudly against the commissioning of this newest European NPP. Now, in December 1998, the tune of

  20. Regulatory approach to NPP ageing in Bulgaria

    International Nuclear Information System (INIS)

    Vassilev, D.

    2000-01-01

    In this contribution summary information of Kozloduy NPP units is presented. The nuclear legislation, regulatory approach for managing safety aspects on NPP ageing, short term programme, complex programme PRG'97 ant other aspects of ageing management are discussed

  1. Some problems of NPP personnel training

    International Nuclear Information System (INIS)

    Vajshnis, P.P.; Kumkov, L.P.; Omel'chuk, V.V.

    1984-01-01

    Shortcomings of NPP personnel training are discussed. Development of full-scale training systems is necessary for qualitative training operative personnel. Primary problems that should be necessarily solved for ensuring effective training NPP personnel are considered

  2. An accident diagnosis algorithm using long short-term memory

    Directory of Open Access Journals (Sweden)

    Jaemin Yang

    2018-05-01

    Full Text Available Accident diagnosis is one of the complex tasks for nuclear power plant (NPP operators. In abnormal or emergency situations, the diagnostic activity of the NPP states is burdensome though necessary. Numerous computer-based methods and operator support systems have been suggested to address this problem. Among them, the recurrent neural network (RNN has performed well at analyzing time series data. This study proposes an algorithm for accident diagnosis using long short-term memory (LSTM, which is a kind of RNN, which improves the limitation for time reflection. The algorithm consists of preprocessing, the LSTM network, and postprocessing. In the LSTM-based algorithm, preprocessed input variables are calculated to output the accident diagnosis results. The outputs are also postprocessed using softmax to determine the ranking of accident diagnosis results with probabilities. This algorithm was trained using a compact nuclear simulator for several accidents: a loss of coolant accident, a steam generator tube rupture, and a main steam line break. The trained algorithm was also tested to demonstrate the feasibility of diagnosing NPP accidents. Keywords: Accident Diagnosis, Long Short-term Memory, Recurrent Neural Network, Softmax

  3. Regulatory aspects of NPP safety

    International Nuclear Information System (INIS)

    Kastchiev, G.

    1999-01-01

    Extensive review of the NPP Safety is presented including tasks of Ministry of Health, Ministry of Internal Affairs, Ministry of Environment and Waters, Ministry of Defense in the field of national system for monitoring the nuclear power. In the frame of national nuclear safety legislation Bulgaria is in the process of approximation of the national legislation to that of EC. Detailed analysis of the status of regulatory body, its functions, organisation structure, responsibilities and future tasks is included. Basis for establishing the system of regulatory inspections and safety enforcement as well as intensification of inspections is described. Assessment of safety modifications is concerned with complex program for reconstruction of Units 1-4 of Kozloduy NPP, as well as for modernisation of Units 5 and 6. Qualification and licensing of the NPP personnel, Year 2000 problem, priorities and the need of international assistance are mentioned

  4. Individual protection of NPP personnel

    International Nuclear Information System (INIS)

    Koshcheev, V.S.; Gol'dshtejn, D.S.; Chetverikova, Z.S.

    1983-01-01

    Specific features of NPP personnel individual protection are considered, mainly with respect to maintenance and repair works on various type reactors. The major concern is given to the selection and application reglamentations of the individual protection system (IPS), employment of sanitary locks, the organization of individual protection under the conditions of a heating microclimate. The ways are specified to the development and introduction of the most effective IPS and improvement of the entire NPP personnel individual protection system with respect to providing the necessary protection effect for maintaining high working capability of the personnel and minimizing the IPS impact on human organism functional systems. The accumulated experience in the personnel individual protection can be applied during construction and operation of NPP's in CMEA member-countries [ru

  5. Safety culture at Mochovce NPP

    International Nuclear Information System (INIS)

    Markus, Jozef; Feik, Karol

    2002-01-01

    This article presents the approach of Mochovce NPP to the Safety culture. It presents activities, which have been taken by Mochovce NPP up to date in the area of Safety culture enhancement with the aim of getting the term into the subconscious of each employee, and thus minimising the human factor impact on occurrence of operational events in all safety areas. The article furthermore presents the most essential information on how the elements characterising a continuous progress in reaching the planned Safety culture goals of the company management have been implemented at Mochovce NPP, as well as the management's efforts to get among the best nuclear power plant operators in this area and to be an example for the others. (author)

  6. Multimedia system for the visitors' centre at the Ignalina NPP

    International Nuclear Information System (INIS)

    Alvers, Margareta

    1999-01-01

    The contents illustrated with video clips, animations, photographs, show the follwing: History of Ignalina NPP (INPP) growing; Visaginas - how the town came into being; Lake Druksiai; Development of nuclear power; Technical data of INPP; Description of INPP; Characteristic features of RBMK reactors; Reactor design; Technical parametres of RBMK-1500 reactor; Nuclear reaction and nuclear fission; Types of nuclear reactors; Circuits and systems; Radiation safety; Safety systems at the INPP; Upgrading nuclear safety at INPP following the Chernobyl accident; Safety problems at MP; Radioactive waste management in the world; RW Management at MP; Energy in Lithuania (thermal power stations, cogeneration plants, producing biogas from organic waste)

  7. Reconstruction of the size of nuclear fuel particle aerosol by the investigation of a radionuclide behaviour in body of the Chernobyl accident witnesses

    International Nuclear Information System (INIS)

    Kutkov, V.A.

    1996-01-01

    As a result of the Chernobyl NPP (ChNPP) accident aerosol particles of dispersed nuclear fuel were released to the atmosphere. Inhalation of those aerosol became the source of internal exposure for witnesses of the Chernobyl accident. To assess correctly internal doses from a mixture of radionuclides present in air in the form of aerosol particles one mast assign each radionuclide to a certain inhalation class by its chemical speciation in aerosol and define the airborne characteristics (the activity median aerodynamic diameter, AMAD and the standard geometric deviation, fig) of that particular aerosol. Moreover, information on any particular radionuclide is useless for other components since, in such a mixture, the radionuclides are generally independent and may belong to different particles. On the contrary, all nuclear fuel particle (NFP) radionuclides belong to the same particle, being matrix-bound. The collective behaviour of the matrix-bound radionuclides in the environment and in the human barrier organs makes it possible to spread to the aerosol of NFP any estimates of AMAD and β g obtained for any particular NFP radionuclide. This is principal feature of NFP aerosol as distinguished from a mere mixture of aerosol particles carry different radionuclides. (author)

  8. NPP construction cost in Canada

    International Nuclear Information System (INIS)

    Gorshkov, A.L.

    1988-01-01

    The structure of capital costs during NPP construction in Canada is considered. Capital costs comprise direct costs (cost of the ground and ground rights, infrastructure, reactor equipment, turbogenerators, electrotechnical equipment, auxiliary equipment), indirect costs (construction equipment and services, engineering works and management services, insurance payments, freight, training, operating expenditures), capital per cents for the period of construction and cost of heavy water storages. It proceeds from the analysis of the construction cost structure for a NPP with the CANDU reactor of unit power of 515, 740 and 880 MW, that direct costs make up on the average 62%

  9. NPP Krsko secondary side analysis

    International Nuclear Information System (INIS)

    Fabijan, Lj.

    1987-01-01

    The purpose of this work is to analyze secondary side thermohydraulics response on steam generator tube plugging in order to ensure nominal NPP power. We had established that the additional opening of the governing valve No. 3 and 4 can compensate pressure drop caused by steam generator tube plugging. Two main steam flows with four governing valves were simulated. Steam expansion in turbine and feed water system was modeled separately. All important process point and steam moisture changes impact on nominal NPP power were analysed. (author)

  10. Improvements in emergency management in nuclear power plants after the Fukushima accident: ORE, CAE and CAGE; Mejoras en la gestion de emergencias en centrales nucleares tras el accidente de Fukushima: ORE, CAE y CAGE

    Energy Technology Data Exchange (ETDEWEB)

    Gimenez Gonzalez, S.; Sanchez Lombardia, A.; Martin Calvarro, J. M.; Calvin Cuartero, M.

    2016-08-01

    After Fukushima accident European NPP safety was checked by means of homogenous stress test promoted by European council. At Spain CSN issued Technical instructions to confirm safety NPP margins were appropriate . As a result of this assessment licensees promoted improving NPP safety by strengthen ERO; a new Support Emergency center (CAE) and construction of a new alternative management centre (CAGE) at each site. European countries have been improving and reinforced NPP safety in a similar way to Spain. (Author)

  11. Positive and negative aspects of the Kozloduy NPP; AEhS Kozloduy - plyusy i minusy

    Energy Technology Data Exchange (ETDEWEB)

    Kouzmanov, K [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

    1996-12-31

    This opening address delivered by the Kozloduy NPP General Director summarizes the benefits and drawbacks of the Kozloduy NPP. It is emphasized that the plant supplies 40% of the national electricity demand and has been running without any accidents or environmental contamination. The production cost of the electricity produced is between two and three times less than the one from thermal stations. Among the disadvantages are: great initial investments; the need to handle and store properly the radioactive waste; the need for modernization and reconstruction in order to improve safety.

  12. Concept of space NPP radiation safety and its realization in the Kosmos-1900 satellite

    International Nuclear Information System (INIS)

    Gryaznov, G.M.; Nikolaev, V.S.; Serbin, V.I.; Tyugin, V.M.

    1989-01-01

    A standard NPP for a space vehicle, radioactivity composition and radiation safety systems are considered. Plausible accidents on board the space vehicle and requirements to system operation reliability are discussed. The main reactor characteristics situation on board the Kosmos-1900 satellite and completion of its flight are described. The experience in providing radiation safety of space NPP has shown that it is sufficient to use two independent systems: a drift system and a reactor dispersion system based on separation of its structure by active means

  13. How to reduce the number of accidents

    CERN Multimedia

    2012-01-01

    Among the safety objectives that the Director-General has established for CERN in 2012 is a reduction in the number of workplace accidents.   The best way to prevent workplace accidents is to learn from experience. This is why any accident, fire, instance of pollution, or even a near-miss, should be reported using the EDH form that can be found here. All accident reports are followed up. The departments investigate all accidents that result in sick leave, as well as all the more common categories of accidents at CERN, essentially falls (slipping, falling on stairs, etc.), regardless of whether or not they lead to sick leave. By studying the accident causes that come to light in this way, it is possible to take preventive action to avoid such accidents in the future. If you have any questions, the HSE Unit will be happy to answer them. Contact us at safety-general@cern.ch. HSE Unit

  14. The V-1 NPP and V-2 NPP upgrading

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities in the V-1 NPP and V-2 NPP upgrading as well as maintenance carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. The V-1 NPP applied the so called 'Small Backfitting Programme'covering 81 points of the Czechoslovak Atomic energy Commission Decree No 5/91. Continual upgrading continued after the Backfitting Programme completion with the Safety Report and following Nuclear Regulatory Authority of Slovak Republic (NRA SR) Decrees No 1/94 and 110/94 setting spheres and procedure for adopting and implementation of measures enabling the units to operate further on. Results of expert missions, analyses and assessments of components identified by Basic Engineering became the basis for the development of the Gradual Reconstruction Programme. The Programme outputs underwent economic and probabilistic assessing their contribution to nuclear safety. This process resulted in finalizing the Gradual Reconstruction Programme which started to be implemented in 1996 and will be completed in 1999. It is implemented by the REKON consortium and covers 17 areas including Instrumentation and Control, self-consumption emergency supply, leakage monitoring, emergency core cooling system, seismic reinforcement and radioactivity localisation. Both units will reach internationally acceptable safety standards for the remaining life-time period. The V-2 NPP Upgrading and Safety Enhancement Programme includes results of activities performed in the course of last years to define all important activities leading to enhancement of nuclear safety and performance reliability and effectiveness within the plant life-time period and to establish conditions for extending the life-time of these units for 40 years. The V-2 NPP Upgrading and Safety Enhancement Programme aims to assure safe operation with a probability of the core damages less than 10 -4 /reactor · year

  15. Preventing accidents

    Science.gov (United States)

    2005-08-01

    As the most effective strategy for improving safety is to prevent accidents from occurring at all, the Volpe Center applies a broad range of research techniques and capabilities to determine causes and consequences of accidents and to identify, asses...

  16. Analysis of Fukushima Daiichi Accident Using HFACS

    International Nuclear Information System (INIS)

    Mohamed, Saeed Almheiri

    2013-01-01

    The shadow of Fukushima Daiichi nuclear power plant (NPP) accident is still too big and will last long. On the other hand, it could still teach us lots of lessons to better design and operate nuclear power plants. In this paper, we will be focusing on the Fukushima Daiichi accident, especially on human organizational factors. We will analyze the accident using Human Factors Analysis and Classification System (HFACS) in order to better understand the organizational climate of TEPCO 1 and NISA 2 that led to Fukushima Daiichi Accident. HFACS was developed for the U. S. aviation industry and has been used at many industries like the rail and mining industries. We found that the HFACS to be greatly beneficial in investigating the latent and organizational causes for the accident. The application results show that the causes of Fukushima Daiichi accident were spread out from sharp end (i.e. Unsafe Act) to blunt end (i. e. Organizational Influences). This means that the corresponding countermeasures should cover from front line staff to management. Thus, we managed to develop a better understanding on how to prevent similar errors or violations. The incident and near-miss have a lot of helpful information because it may show the actual and latent deficiencies of complex systems. We applied the HFACS into Fukushima Daiichi accident to better locate the causes related to both sharp and blunt ends of operation of NPP. In order to derive useful lessons from the accident analysis, the analyst should try to find the similarities not differences from the incident. It is imperative that whatever accident/incident analysis systems we use, we should fully utilize the disastrous Fukushima accident

  17. Analysis of Fukushima Daiichi Accident Using HFACS

    Energy Technology Data Exchange (ETDEWEB)

    Mohamed, Saeed Almheiri [Korea Advanced Institue of Science and Technology, Daejeon (Korea, Republic of)

    2013-10-15

    The shadow of Fukushima Daiichi nuclear power plant (NPP) accident is still too big and will last long. On the other hand, it could still teach us lots of lessons to better design and operate nuclear power plants. In this paper, we will be focusing on the Fukushima Daiichi accident, especially on human organizational factors. We will analyze the accident using Human Factors Analysis and Classification System (HFACS) in order to better understand the organizational climate of TEPCO{sup 1} and NISA{sup 2} that led to Fukushima Daiichi Accident. HFACS was developed for the U. S. aviation industry and has been used at many industries like the rail and mining industries. We found that the HFACS to be greatly beneficial in investigating the latent and organizational causes for the accident. The application results show that the causes of Fukushima Daiichi accident were spread out from sharp end (i.e. Unsafe Act) to blunt end (i. e. Organizational Influences). This means that the corresponding countermeasures should cover from front line staff to management. Thus, we managed to develop a better understanding on how to prevent similar errors or violations. The incident and near-miss have a lot of helpful information because it may show the actual and latent deficiencies of complex systems. We applied the HFACS into Fukushima Daiichi accident to better locate the causes related to both sharp and blunt ends of operation of NPP. In order to derive useful lessons from the accident analysis, the analyst should try to find the similarities not differences from the incident. It is imperative that whatever accident/incident analysis systems we use, we should fully utilize the disastrous Fukushima accident.

  18. Feed water distribution pipe replacement at Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Savolainen, S.; Elsing, B. [Imatran Voima Loviisa NPP (Finland)

    1995-12-31

    Imatran Voima Oy operates two WWER-440 reactors. Unit 1 has been operating since 1977 and unit 2 since 1981. First damages of feed water distribution (FWD) pipe were observed in 1989. The FWD-pipe T-connection had suffered from severe erosion corrosion damages. Similar damages have been been found also in other WWER-440 type NPPs. In 1989 the nozzles of the steam generator YB11 were inspected. No signs of the damages or signs of erosion were detected. The first damaged nozzles were found in 1992 in steam generators of both units. In 1992 it was started studying different possibilities to either repair or replace the damaged FWD-pipes. Due to the difficult conditions for repairing the damaged nozzles it was decided to study different FWD-pipe constructions. In 1991 two new feedwater distributors had been implemented at Dukovany NPP designed by Vitckovice company. Additionally OKB Gidropress had presented their design for new collector. In spring 1994 all the six steam generators of Rovno NPP unit 1 were replaced with FWD-pipes designed by OKB Gidropress. After the implementation an experimental program with the new systems was carried out. Due to the successful experiments at Rovno NPP Unit 1 it was decided to implement `Gidropress solution` during 1994 refueling outage into the steam generator YB52 at Loviisa 2. The object of this paper is to discuss the new FWD-pipe and its effects on the plant safety during normal and accident conditions. (orig.).

  19. Feed water distribution pipe replacement at Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Savolainen, S; Elsing, B [Imatran Voima Loviisa NPP (Finland)

    1996-12-31

    Imatran Voima Oy operates two WWER-440 reactors. Unit 1 has been operating since 1977 and unit 2 since 1981. First damages of feed water distribution (FWD) pipe were observed in 1989. The FWD-pipe T-connection had suffered from severe erosion corrosion damages. Similar damages have been been found also in other WWER-440 type NPPs. In 1989 the nozzles of the steam generator YB11 were inspected. No signs of the damages or signs of erosion were detected. The first damaged nozzles were found in 1992 in steam generators of both units. In 1992 it was started studying different possibilities to either repair or replace the damaged FWD-pipes. Due to the difficult conditions for repairing the damaged nozzles it was decided to study different FWD-pipe constructions. In 1991 two new feedwater distributors had been implemented at Dukovany NPP designed by Vitckovice company. Additionally OKB Gidropress had presented their design for new collector. In spring 1994 all the six steam generators of Rovno NPP unit 1 were replaced with FWD-pipes designed by OKB Gidropress. After the implementation an experimental program with the new systems was carried out. Due to the successful experiments at Rovno NPP Unit 1 it was decided to implement `Gidropress solution` during 1994 refueling outage into the steam generator YB52 at Loviisa 2. The object of this paper is to discuss the new FWD-pipe and its effects on the plant safety during normal and accident conditions. (orig.).

  20. Safety aspects of NPP ageing

    International Nuclear Information System (INIS)

    1995-01-01

    Preparation of safety practices on assessment and management of aging of major NPP components important to safety, CRP on management of aging of concrete containment buildings, CRP on management of aging of in-containment instrumentation and control cables are outlined

  1. Qualification of NPP operations personnel

    International Nuclear Information System (INIS)

    Wang Jiao.

    1987-01-01

    Competence of personnel is one of the important problems for safety operation of nuclear power plant. This paper gives a description of some aspects, such as the administration of NPP, posts, competence of personnel, training, assessing the competence and personnel management

  2. Dosimetry problems when evaluating radiation effects on the personnel, restoration work participants, and human population due to the Chernobyl accident

    International Nuclear Information System (INIS)

    Abramov, Yu.V.; Osanov, D.P.; Gimadova, T.I.; Gus'kov, V.M.; Kruchkov, V.P.; Pavlov, D.A.; Shaks, A.I.

    1993-01-01

    System of radiation monitoring operations of the Chernobyl NPP personnel is described for the period from the date of accident up to present time as well as of persons worked in the Chernobyl NPP 30 km zone, servicemen, and human population. Unsatisfactory organization of radiation on monitoring is marked and causes of this fact are considered. 8 refs.; 3 figs

  3. Analysis of accident sequences and source terms at waste treatment and storage facilities for waste generated by U.S. Department of Energy Waste Management Operations, Volume 3: Appendixes C-H

    International Nuclear Information System (INIS)

    Mueller, C.; Nabelssi, B.; Roglans-Ribas, J.

    1995-04-01

    This report contains the Appendices for the Analysis of Accident Sequences and Source Terms at Waste Treatment and Storage Facilities for Waste Generated by the U.S. Department of Energy Waste Management Operations. The main report documents the methodology, computational framework, and results of facility accident analyses performed as a part of the U.S. Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies are assessed, and the resultant radiological and chemical source terms are evaluated. A personal computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for calculation of human health risk impacts. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also provide discussion of specific accident analysis data and guidance used or consulted in this report

  4. Analysis of accident sequences and source terms at waste treatment and storage facilities for waste generated by U.S. Department of Energy Waste Management Operations, Volume 3: Appendixes C-H

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, C.; Nabelssi, B.; Roglans-Ribas, J. [and others

    1995-04-01

    This report contains the Appendices for the Analysis of Accident Sequences and Source Terms at Waste Treatment and Storage Facilities for Waste Generated by the U.S. Department of Energy Waste Management Operations. The main report documents the methodology, computational framework, and results of facility accident analyses performed as a part of the U.S. Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies are assessed, and the resultant radiological and chemical source terms are evaluated. A personal computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for calculation of human health risk impacts. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also provide discussion of specific accident analysis data and guidance used or consulted in this report.

  5. Comparative radiation impact on biota and man in the area affected by the accident at the Chernobyl nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Fesenko, S.V. [Russian Institute of Agricultural Radiology and Agroecology, Kievskoe shosse, Kaluga region, Obninsk 249020 (Russian Federation) and International Atomic Energy Agency, Agency' s Laboratories, Seibersdorf A-2444 (Austria)]. E-mail: s.fesenko@iaea.org; Alexakhin, R.M. [Russian Institute of Agricultural Radiology and Agroecology, Kievskoe shosse, Kaluga region, Obninsk 249020 (Russian Federation); Geras' kin, S.A. [Russian Institute of Agricultural Radiology and Agroecology, Kievskoe shosse, Kaluga region, Obninsk 249020 (Russian Federation); Sanzharova, N.I. [Russian Institute of Agricultural Radiology and Agroecology, Kievskoe shosse, Kaluga region, Obninsk 249020 (Russian Federation); Spirin, Ye.V. [Russian Institute of Agricultural Radiology and Agroecology, Kievskoe shosse, Kaluga region, Obninsk 249020 (Russian Federation); Spiridonov, S.I. [Russian Institute of Agricultural Radiology and Agroecology, Kievskoe shosse, Kaluga region, Obninsk 249020 (Russian Federation); Gontarenko, I.A. [Russian Institute of Agricultural Radiology and Agroecology, Kievskoe shosse, Kaluga region, Obninsk 249020 (Russian Federation); Strand, P. [Norwegian Radiation Protection Authority, Oesteras (Norway)

    2005-07-01

    A methodological approach for a comparative assessment of ionising radiation effects on man and non-human species, based on the use of Radiation Impact Factor (RIF) - ratios of actual exposure doses to biota species and man to critical dose is described. As such doses, radiation safety standards limiting radiation exposure of man and doses at which radiobiological effects in non-human species were not observed after the Chernobyl accident, were employed. For the study area within the 30 km ChNPP zone dose burdens to 10 reference biota groups and the population (with and without evacuation) and the corresponding RIFs were calculated. It has been found that in 1986 (early period after the accident) the emergency radiation standards for man do not guarantee adequate protection of the environment, some species of which could be affected more than man. In 1991 RIFs for man were considerably (by factor of 20.0-1.1 x 10{sup 5}) higher compared with those for selected non-human species. Thus, for the long term after the accident radiation safety standards for man are shown to ensure radiation safety for biota as well.

  6. Comparative radiation impact on biota and man in the area affected by the accident at the Chernobyl nuclear power plant

    International Nuclear Information System (INIS)

    Fesenko, S.V.; Alexakhin, R.M.; Geras'kin, S.A.; Sanzharova, N.I.; Spirin, Ye.V.; Spiridonov, S.I.; Gontarenko, I.A.; Strand, P.

    2005-01-01

    A methodological approach for a comparative assessment of ionising radiation effects on man and non-human species, based on the use of Radiation Impact Factor (RIF) - ratios of actual exposure doses to biota species and man to critical dose is described. As such doses, radiation safety standards limiting radiation exposure of man and doses at which radiobiological effects in non-human species were not observed after the Chernobyl accident, were employed. For the study area within the 30 km ChNPP zone dose burdens to 10 reference biota groups and the population (with and without evacuation) and the corresponding RIFs were calculated. It has been found that in 1986 (early period after the accident) the emergency radiation standards for man do not guarantee adequate protection of the environment, some species of which could be affected more than man. In 1991 RIFs for man were considerably (by factor of 20.0-1.1 x 10 5 ) higher compared with those for selected non-human species. Thus, for the long term after the accident radiation safety standards for man are shown to ensure radiation safety for biota as well

  7. Accident management for severe accidents

    International Nuclear Information System (INIS)

    Bari, R.A.; Pratt, W.T.; Lehner, J.; Leonard, M.; Disalvo, R.; Sheron, B.

    1988-01-01

    The management of severe accidents in light water reactors is receiving much attention in several countries. The reduction of risk by measures and/or actions that would affect the behavior of a severe accident is discussed. The research program that is being conducted by the US Nuclear Regulatory Commission focuses on both in-vessel accident management and containment and release accident management. The key issues and approaches taken in this program are summarized. 6 refs

  8. Environmental monitoring of the Kozloduy NPP: 20 year experience

    Energy Technology Data Exchange (ETDEWEB)

    Aleksiev, A; Tsochev, S; Dimitrov, M; Avramov, V [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

    1996-12-31

    The radiation monitoring system of the Kozloduy NPP is described and the assessment of the environmental impact of the power plant is presented. Measurements are carried out in 36 control points distributed in 3 areas: radiation protected area (3 km diameter), radiation controlled area (12 km) and surveillance area (100 km). Comparison of radiation monitoring data for 1993 with data recorded in the pre-operational period (1972-74) show that no significant changes can be detected in the activity of {sup 90} Sr and gross beta activity. An increase in Cs-137 activity (38 Bq/kg d.w. versus 7 Bq/kg d.w.) is found in the soil and bottom sediments in the Danube river, which is attributed to Chernobyl accident. The Kozloduy NPP operation is continuously monitored for release of artificial radionuclides by gaseous and liquid effluents. It is reported that the average population exposure in the 30 km area due to liquid effluents is 3-4.10{sup -4} man Sv/a. A system for automated continuous radiation monitoring in 10 control stations is available in case of radiation accidents. It is supplemented by a mobile laboratory. Meteorological measurements are carried out by automatic station MC-10 and a second station is under construction. 21 refs., 2 figs., 6 tabs.

  9. Environmental monitoring of the Kozloduy NPP: 20 year experience

    International Nuclear Information System (INIS)

    Aleksiev, A.; Tsochev, S.; Dimitrov, M.; Avramov, V.

    1995-01-01

    The radiation monitoring system of the Kozloduy NPP is described and the assessment of the environmental impact of the power plant is presented. Measurements are carried out in 36 control points distributed in 3 areas: radiation protected area (3 km diameter), radiation controlled area (12 km) and surveillance area (100 km). Comparison of radiation monitoring data for 1993 with data recorded in the pre-operational period (1972-74) show that no significant changes can be detected in the activity of 90 Sr and gross beta activity. An increase in Cs-137 activity (38 Bq/kg d.w. versus 7 Bq/kg d.w.) is found in the soil and bottom sediments in the Danube river, which is attributed to Chernobyl accident. The Kozloduy NPP operation is continuously monitored for release of artificial radionuclides by gaseous and liquid effluents. It is reported that the average population exposure in the 30 km area due to liquid effluents is 3-4.10 -4 man Sv/a. A system for automated continuous radiation monitoring in 10 control stations is available in case of radiation accidents. It is supplemented by a mobile laboratory. Meteorological measurements are carried out by automatic station MC-10 and a second station is under construction. 21 refs., 2 figs., 6 tabs

  10. Structural analysis of NPP components and structures

    International Nuclear Information System (INIS)

    Saarenheimo, A.; Keinaenen, H.; Talja, H.

    1998-01-01

    Capabilities for effective structural integrity assessment have been created and extended in several important cases. In the paper presented applications deal with pressurised thermal shock loading, PTS, and severe dynamic loading cases of containment, reinforced concrete structures and piping components. Hydrogen combustion within the containment is considered in some severe accident scenarios. Can a steel containment withstand the postulated hydrogen detonation loads and still maintain its integrity? This is the topic of Chapter 2. The following Chapter 3 deals with a reinforced concrete floor subjected to jet impingement caused by a postulated rupture of a near-by high-energy pipe and Chapter 4 deals with dynamic loading resistance of the pipe lines under postulated pressure transients due to water hammer. The reliability of the structural integrity analysing methods and capabilities which have been developed for application in NPP component assessment, shall be evaluated and verified. The resources available within the RATU2 programme alone cannot allow performing of the large scale experiments needed for that purpose. Thus, the verification of the PTS analysis capabilities has been conducted by participation in international co-operative programmes. Participation to the European Network for Evaluating Steel Components (NESC) is the topic of a parallel paper in this symposium. The results obtained in two other international programmes are summarised in Chapters 5 and 6 of this paper, where PTS tests with a model vessel and benchmark assessment of a RPV nozzle integrity are described. (author)

  11. Chromosomal aberrations in blood lymphocytes of the residents of 30-km Chernobyl NPP exclusion zone

    International Nuclear Information System (INIS)

    Bezdrobna, Larysa; Tsyganok, Tetyana; Romanova, Olena; Tarasenko, Larysa; Tryshyn, Volodymyr; Klimkina, Ludmila

    2016-01-01

    A comparative cytogenetic examination of 33 self-settlers in the 30 km ChNPP Exclusion Zone and 31 residents in villages of Yahotyn district, Kyiv region was carried out in 1998-99. The levels of soil contamination of their residential areas with "1"3"7Cs, "9"0Sr and "2"3"8","2"3"9"+"2"4"0Pu were 74–477 kBq/m"2, 33–288 kBq/m"2 and 1.5-10.0 kBq/m"2, respectively for the former, and 1.9–5.8 kBq/m"2, 0.6–2.8 kBq/m"2 and 0.01-0.05 kBq/m"2, respectively for the latter. Using various data about the radiation situation in the Exclusion Zone, the effective doses on whole-body of the self-settlers were estimated to be 30–333 mSv for the whole residing period after the accident. The mean frequencies of aberrant cells and chromosomal aberrations for the Zone self-settlers were significantly higher than those for the residents in Yahotyn district, while the values of the latter group were found to be above the spontaneous levels reported in literatures. The individual variability in the distribution of the same indices was significantly larger for the self-settlers than for the Yahotyn residents. The compared groups also differ in the distribution of aberrations in cells. A repeated examination of 20 Zone self-settlers was conducted in 2001. A significant decrease in chromosome type aberration frequency was found at the expense of fragments frequency decrease. However, the total frequency of chromosomal aberrations didn't differ in 1998-99 and in 2001. (author)

  12. Accident transient processes at NPPs with the WWER type reactors

    International Nuclear Information System (INIS)

    Bukrinskij, A.M.

    1982-01-01

    Thermal-physical and nuclear-physical transient processes at NPPs with the WWER type reactors during accidents with the main technological equipment failures and the accidents with loss of coolant in the primary and secondary coolant circuits are considered. Mathematical methods used for these processes modelling is described. Examples of concrete calculations for accidents with different failures are given. Comparative analysis of the results of dynamic tests at the Novo-Voronezh-3 reactor is presented. It is concluded that the modern NPP design is impossible without application of mathematical modelling methods. The mathematical modelling of transients is also necessary for proper and safe NPP operation. Mathematical modelling of accidents at NPPs is a comparatively new method of investigation. Its success and development are completely based on the progress in modern computer development. With their improvement the mathematical models will become more complicate and adequacy of real physical process representation by their means will increase

  13. Research on sever accident emergency simulation system for CPR1000

    International Nuclear Information System (INIS)

    Yang Zhifei; Liao Yehong; Liang Manchun; Li Ke; Yang Jie; Chen Yali

    2015-01-01

    The enhanced capability to nuclear power plant (NPP) severe accident management and emergency response depends heavily on exercises. Since the exercise scene is usually monotonous and not realistic, and conduct of exercise has a high cost, the effect of enhancing the capability is limited. Thus, the development of a Sever Accident Emergency Simulation System (SAESS) is necessary. SAESS is able to connect NPP simulator, and simulates the process of severe accident management, personnel evacuation, the dispersion of radioactive plume, and emergency response of emergency organizations. The system helps to design several of exercise scenes and optimize the disposal strategy in different severe accidents. In addition, the system reduces the cost of emergency exercise by computer simulation, benefits the research of exercise, increases the efficiency of exercise and enhances the emergency decision-making capability. This paper introduces the design and application of SAESS. (author)

  14. Operating and mathematical representation of resonances between flow parameters oscillations and structure vibrations of NPP

    Energy Technology Data Exchange (ETDEWEB)

    Proskuryakov, K.N.; Yang Shan Afshar, E.; Polyakov, N.I. [Nuclear Power Plant Department of Moscow Power Engineering Institute Technical Univ., Moscow (Russian Federation)

    2007-07-01

    The experimental data that have been obtained from the measurements of noise signals in primary circuit of NPP with reactor of WWER-1000 are presented. The causes of resonant interaction between Eigen-Frequencies of Oscillations of the Coolant Pressure (EFOCP) and structure vibrations are discussed. An application-oriented approach to the problem of identification of abnormal phenomena of thermal-hydraulic parameters is proposed. Logarithmic Decrement {delta} is determined. The bigger damping ratio {zeta} provides bigger {delta} and correspondingly smaller values of Q-factor and amplitude X(t)max. All experimental units intended for NPP severe accident investigation must satisfy to the NPP Q-factor criterion of similarity. (authors)

  15. Operating and mathematical representation of resonances between flow parameters oscillations and structure vibrations of NPP

    International Nuclear Information System (INIS)

    Proskuryakov, K.N.; Yang Shan Afshar, E.; Polyakov, N.I.

    2007-01-01

    The experimental data that have been obtained from the measurements of noise signals in primary circuit of NPP with reactor of WWER-1000 are presented. The causes of resonant interaction between Eigen-Frequencies of Oscillations of the Coolant Pressure (EFOCP) and structure vibrations are discussed. An application-oriented approach to the problem of identification of abnormal phenomena of thermal-hydraulic parameters is proposed. Logarithmic Decrement δ is determined. The bigger damping ratio ζ provides bigger δ and correspondingly smaller values of Q-factor and amplitude X(t)max. All experimental units intended for NPP severe accident investigation must satisfy to the NPP Q-factor criterion of similarity. (authors)

  16. Electrical Grid Conditioning For First NPP Integration, a Systems Engineering Approach Incorporating Quality Function Deployment

    Energy Technology Data Exchange (ETDEWEB)

    Pwani, Henry; James, J. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    Nuclear power plant has a high potential to cause serious harm to environment as evidenced by effects of Fukushima and Chernobyl accidents. A reliable electrical power is required for a NPP to facilitate cooling after a shutdown. Failure of electrical power supply during shutdown increases core damage probability. Research shows that a total of 39% of LOOP related events in US are electrical grid centered. In Korea, 38% and 29% of all events that led to NPP shutdown at Hanul units 3-6 and at Hanbit units 3-6 respectively were electrical related. Electric grids for both operating and new NPPs must therefore be examined and upgraded for reliability improvement in order to enhance NPP safety.

  17. Safety regulation - twenty years after Chernobyl accident

    International Nuclear Information System (INIS)

    Aleksashin, P.P.; Bukrinskij, A.M.; Gordon, B.G.

    2006-01-01

    Main stages of development, successes, achievements and shortcomings of activity of supervision body after the Chernobyl NPP accident are analysed. The estimation of the realized variations of the functions of the state supervision department is carried out. Results of the twenty year period of improvement of the supervision body are summed up. The measures for increasing the efficiency of the supervision body operation are outlined [ru

  18. Investigation of evaluation method for marine radiological impact during an accident

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    In 2012, JNES carried out to investigate the measurement information of radionuclide released to the ocean at Fukushima Daiichi NPP accident, the foreign regulation for marine radiological impact, and the evaluation method for release and diffusion to the ocean at the accident inside and outside Japan. (author)

  19. Analytical support for SAMG development as a part of accident management

    International Nuclear Information System (INIS)

    Honcarenko, R.

    1999-01-01

    The decision to built up and implement a comprehensive Accident Management Program applying best world-wide knowledge made during last year at Temelin. A small group of engineers dedicated to Accident Management was formed at Temelin NPP as a part of the plant organisation scheme. A short summary of these activities performed by this group is presented. (author)

  20. Development of Krsko Severe Accident Management Guidance (SAMG)

    International Nuclear Information System (INIS)

    Cizel, F.

    1999-01-01

    In this lecture development of severe accident management guidances for Krsko NPP are described. Author deals with the history of severe accident management and implementation of issues (validation, review of E-plan and other aspects SAMG implementation guidance). Methods of Westinghouse owners group, of Combustion Engineering owners group, of Babcock and Wilcox owners group, of the BWR owners group, as well as application of US SAMG methodology in Europe and elsewhere are reviewed

  1. Chernobyl NPP: Completion of LRW Treatment Plant and LRW Management on Site - 12568

    Energy Technology Data Exchange (ETDEWEB)

    Fedorov, Denis; Adamovich, Dmitry [SIA ' RADON' , Moscow (Russian Federation); Klimenko, I.; Taranenko, L. [IVL Engineering, Kiev (Ukraine)

    2012-07-01

    Since a beginning of ChNPP operation, and after a tragedy in 1986, a few thousands m3 of LRW have been collected in a storage tanks. In 2004 ChNPP started the new project on creation of LRW treatment plant (LRWTP) financed from EBRD fund. But it was stopped in 2008 because of financial and contract problems. In 2010 SIA RADON jointly with Ukrainian partners has won a tender on completion of LRWTP, in particular I and C system. The purpose of LRTP is to process liquid rad-wastes from SSE 'Chernobyl NPP' site and those liquids stored in the LRWS and SLRWS tanks as well as the would-be wastes after ChNPP Power Units 1, 2 and 3 decommissioning. The LRTP design lifetime - 20 years. Currently, the LRTP is getting ready to perform the following activities: 1. retrieval of waste from tanks stored at ChNPP LWS using waste retrieval system with existing equipment involved; 2. transfer of retrieved waste into LRTP reception tanks with partial use of existing transfer pipelines; 3. laboratory chemical and radiochemical analysis of reception tanks contest to define the full spectrum of characteristics before processing, to acknowledge the necessity of preliminary processing and to select end product recipe; 4. preliminary processing of the waste to meet the requirements for further stages of the process; 5. shrinkage (concentrating) of preliminary processed waste; 6. solidification of preliminary processed waste with concrete to make a solid-state (end product) and load of concrete compound into 200-l drums; 7. curing of end product drums in LRTP curing hall; 8. radiologic monitoring of end product drums and their loading into special overpacks; 9. overpack radiological monitoring; 10. send for disposal (ICSRM Lot 3); The current technical decisions allow to control and return to ChNPP of process media and supporting systems outputs until they satisfy the following quality norms: salt content: < 100 g/l; pH: 1 - 11; anionic surface-active agent: < 25 mg/l; oil

  2. Integrated assessment of radio-ecological situation using Gis-technology and spatial data bank of environment of NPP 30-km area

    International Nuclear Information System (INIS)

    Lev, T.D.; Tishchenko, O.G.; Piskun, V.N.

    2011-01-01

    In accordance with the requirements of IAEA on providing information-analytical and cartographic materials for NPP emergency systems Institute for safety problems of NPP is creating the spatial data bank taking into account geographical features, socio-economic indexes and information of monitoring of NPP environment. Based on analysis of connection between ecological parameters and geographical features of locality the specific of radio-ecological conditions of territories of NPP 30-m area is exposed by the example of Rivne and Khmel'nickiy NPP. Determination on critical territories maximally influencing on forming of the radiation dose for a population will allow to develop in good time preventive and protective measures for a population at the different scenarios of accident situation.

  3. ASSET experience at Paks NPP

    International Nuclear Information System (INIS)

    Szabo, I.

    1997-01-01

    At Paks NPP special attention has been paid to international reviews since the very beginning of operation. Several international teams visited Paks in order to provide independent assessment of plant performance, conditions and safety. Paks NPP Management has the further intention to invite international reviews regularly (yearly) in the future as well. The experience gained during these reviews helped to establish a unified process of preparation for the reviews, performing them and handling the results. The Safety Department is in charge of organization of the whole process. All these reviews have their specific features and they are focused on different areas. The ASSET reviews provides the assessment of plant performance and safety through the analysis of safety significant events, which have occurred at the nuclear power plant. This approach makes this review specific and different from the other ones

  4. Retrofitting of NPP Computer systems

    International Nuclear Information System (INIS)

    Pettersen, G.

    1994-01-01

    Retrofitting of nuclear power plant control rooms is a continuing process for most utilities. This involves introducing and/or extending computer-based solutions for surveillance and control as well as improving the human-computer interface. The paper describes typical requirements when retrofitting NPP process computer systems, and focuses on the activities of Institute for energieteknikk, OECD Halden Reactor project with respect to such retrofitting, using examples from actual delivery projects. In particular, a project carried out for Forsmarksverket in Sweden comprising upgrade of the operator system in the control rooms of units 1 and 2 is described. As many of the problems of retrofitting NPP process computer systems are similar to such work in other kinds of process industries, an example from a non-nuclear application area is also given

  5. ASSET experience at Paks NPP

    Energy Technology Data Exchange (ETDEWEB)

    Szabo, I [Operational Safety Dept., Paks NPP, Paks (Hungary)

    1997-10-01

    At Paks NPP special attention has been paid to international reviews since the very beginning of operation. Several international teams visited Paks in order to provide independent assessment of plant performance, conditions and safety. Paks NPP Management has the further intention to invite international reviews regularly (yearly) in the future as well. The experience gained during these reviews helped to establish a unified process of preparation for the reviews, performing them and handling the results. The Safety Department is in charge of organization of the whole process. All these reviews have their specific features and they are focused on different areas. The ASSET reviews provides the assessment of plant performance and safety through the analysis of safety significant events, which have occurred at the nuclear power plant. This approach makes this review specific and different from the other ones.

  6. Nuclear Fuel in Cofrentes NPP

    International Nuclear Information System (INIS)

    2002-01-01

    Fuel is an essential in the nuclear power generating business because of its direct implications on safety, generating costs and the operating conditions and limitations of the facility. Fuel management in Cofrentes NPP has been targeted at optimized operation, enhanced reliability and the search for an in-depth knowledge of the design and licensing processes that will provide Iberdrola,as the responsible operator, with access to independent control of safety aspects related to fuel and free access to manufacturing markets. (Author)

  7. NPP Krsko Living PSA Concept

    International Nuclear Information System (INIS)

    Vrbanic, I.; Spiler, J.

    2000-01-01

    NPP Krsko developed PSA model of internal and external initiators within the frame of the Individual Plant Examination (IPE) project. Within this project PSA model was used to examine the existing plant design features. In order to continue with use of this PSA model upon the completion of IPE in various risk-informed applications in support of plant operation and evaluations of design changes, an appropriate living PSA concept needed to be defined. The Living PSA concept is in NPP Krsko considered as being a set of activities pursued in order to update existing PSA model in a manner that it appropriately represents the plant design, operation practice and history. Only a PSA model which is being updated in this manner can serve as a platform for plant-specific risk informed applications. The NPP Krsko living PSA concept is based on the following major ponts. First, the baseline PSA model is defined, which is to be maintained and updated and which is to be reference point for any risk-informed application. Second, issues having a potential for impact on baseline PSA model are identified and procedure and responsibilities for their permanent monitoring and evaluation are established. Third, manner is defined in which consequential changes to baseline PSA model are implemented and controlled, together with associated responsibilities. Finally, the process is defined by which the existing version of baseline PSA model is superseded by a new one. Each time a new version of baseline PSA model is released, it would be re-quantified and the results evaluated and interpreted. By documenting these re-quantifications and evaluations of results in a sequence, the track is being kept of changes in long-term averaged risk perspective, represented by long-term averaged frequencies of core damage and pre-defined release categories. These major topics of NPP Krsko living PSA concept are presented and discussed in the paper. (author)

  8. Welding facilities for NPP assembling

    International Nuclear Information System (INIS)

    Rojtenberg, S.S.

    1987-01-01

    Recommendations concerning the choice of equipment for welding in pre-assembling work shops, in the enlarging assembling shops and at the assembling site, are given. Advanced production automatic welders and semiautomatic machines, applied during the NPP equipment assembling as well as automatic machines specially produced for welding the main reactor components and pipelines are described. Automatic and semiautomatic machine and manual welding post supply sources are considered

  9. Nuclear accidents

    International Nuclear Information System (INIS)

    1987-01-01

    On 27 May 1986 the Norwegian government appointed an inter-ministerial committee of senior officials to prepare a report on experiences in connection with the Chernobyl accident. The present second part of the committee's report describes proposals for measures to prevent and deal with similar accidents in the future. The committee's evaluations and proposals are grouped into four main sections: Safety and risk at nuclear power plants; the Norwegian contingency organization for dealing with nuclear accidents; compensation issues; and international cooperation

  10. New approach of second Romanian NPP siting

    International Nuclear Information System (INIS)

    Mauna, Traian

    2010-01-01

    The NPP sitting studies in Romania began before 1975. The first Romanian NPP CANDU 6 type reactor gone to erection in 1980 on Cernavoda site planned to have 5 units. Gained the experience from Cernavoda NPP sitting, the first mission of new multi-branch of specialists team was to choose new NPP sites adapting the NPP Cernavoda project to the new parameters of close water cooling circuit and hard less and no rock foundation strata. The studies were carrying out in different stages on the inner rivers Olt, Mures, Somes in Transylvania historical region. This paper tries to reconsider shortly the old analysis according to the last IAEA Safety Standards, taking into account the new NPP generation requirement. Paper is focused on geological aspects and other local sites characteristics. (authors)

  11. Licensing of the Ignalina NPP

    International Nuclear Information System (INIS)

    Kutas, S.

    1999-01-01

    Since 1991 State Nuclear Power Safety Inspectorate (VATESI) has regulated Ignalina NPP operation by issuing annual operating permits. Those have been issued following submission of specified documents by the Ignalina NPP that have been reviewed by VATESI. However, according to to the procedures that are now established in the Law on Nuclear Energy and subordinate regulations the use of nuclear energy in the Republic of Lithuania is subject to strict licensing. Therefore a decision about the licence for continued operation of unit 1 should be taken. Licence would be granted by VATESI in cooperation with the Ministry of Health, Ministry of Environment and the institutions of local authorities. Ignalina NPP presented to the VATESI safety analysis report (SAR) with other documents. SAR was made mainly by foreign experts and financed by European Bank for Reconstruction and Development (EBRD). VATESI in this process is supported by western regulators. A special project LAP - Licensing Assistance Project was launched to help VATESI perform licensing according western practices

  12. On the NPP structural reliability

    International Nuclear Information System (INIS)

    Klemin, A.I.; Polyakov, E.F.

    1980-01-01

    Reviewed are the main statements peculiarities and possibilities of the first branch guiding technical material (GTM) ''The methods of calculation of structural reliability of NPP and its systems at the stage of projecting''. It is stated, that in GTM presented are recomendations on the calculation of reliability of such specific systems, as the system of the reactor control and protection the system of measuring instruments and automatics and safe systems. GTM are based on analytical methods of modern theory of realibility with the Use of metodology of minimal cross sections of complex systems. It is stressed, that the calculations on the proposed methods permit to calculate a wide complex of reliability parameters, reflecting separately or together prorerties of NPP dependability and maintainability. For NPP, operating by a variable schedule of leading, aditionally considered are parameters, characterizing reliability with account of the proposed regime of power change, i.e. taking into account failures, caused by decrease of the obtained power lower, than the reguired or increase of the required power higher, than the obtained

  13. Modelization of the initiator success of the accident of Fukushima Daiichi in the NPP of ZION by the code MAAP-5; Modelizacion del suceso iniciador del accidente de Fukushima Daiichi en la C.N. de ZION mediante el codigo MAAP-5

    Energy Technology Data Exchange (ETDEWEB)

    Kevin Fernandez, M.; Jimenez, G.; Batteira, P.

    2013-07-01

    The main objective of the project is the modeling of the accident with a code new in the industry, MAAP5, and in a different nuclear plant, as well as various parameters sensitivity analysis to assess their influence on the evolution of the accident. The paper presents the analysis of the evolution of the simulated accident, as well as the evaluation of different sensitivity analyses performed on different parameters influence on the evolution: pre-accident conditions, actions of operator, etc. Operator actions, not referred to in the emergency procedures, which could influence the behavior of the reactor vessel during severe accident progression were analyzed.

  14. Investigation of Chernobyl NPP and recovery of environment and medical service in Ukraine

    International Nuclear Information System (INIS)

    Narabayashi, Tadashi; Hamamoto, Kazuko; Mizumachi, Wataru; Okamoto, Koji

    2013-01-01

    Fukushima Daiichi NPP accident will be terminated, if sufficient care of recovery for heart of people, economy and environment leads to happy Fukushima. It might be taken more than 20 years or more. The overseas NPP investigation group in the study committee for safety regulatory of NPP in PES division in JSME visited Chernobyl NPP, Ministry of Emergencies, National Institute for Strategic Studies under the President of Ukraine, Chernobyl Center, Slavutych, Research Center for Radiation Medicine of the National Academy of Medical Sciences of Ukraine, National University of Life and Environmental Science of Ukraine, Institute for Safety Problems of Nuclear Power Plants and Chernobyl Museum. The investigation of bases of their new technology for deep LRW cleaning of Fukushima genesis from the whole range of radionuclides, including uranium and transuranic elements, organic impurities and simultaneous concentration of radioactive components in a small volume. The recovery of environment and care of heart of people were good in Ukraine. The lessons derived from the accident, we can decide what we should do. (author)

  15. Preparedness and planning for nuclear accidents at national level

    International Nuclear Information System (INIS)

    Shiukshta, A.

    1998-01-01

    National plan for the protection of population in the case in nuclear accident at Ignalina NPP is presented. The plan was elaborated and approved in 1995, tested in a number of training and practical operations and positively evaluated by experts. The plan provides for measures of protection, their scope, schedule, executive officers and organizations and procedure of implementation

  16. Modeling of coherent heat and mass-exchange phenomena for a specter of primary circuit leaks in a NPP with WWER-1000 type reactor

    International Nuclear Information System (INIS)

    Stanev, I.; Mladenova, S.; Hadjiev, V.

    2004-01-01

    Subject of study are the inter-relations between the primary leak parameters, the containment pressure and the functioning of the WWER-1000/V320 plant systems. The model includes systems for normal operation and safety systems, which are actuated in the initial stage of the accident. The studied specter of primary leaks includes diameters from 10 to 60 mm. The model is based on the design features of unit 5 in NPP Kozloduy. This paper presents a fragment of the work, performed jointly by Atoma Consult Ltd and NPP Kozloduy Plc on the validation of the symptom oriented emergency operation procedures for units 5 and 6 in NPP Kozloduy. (authors)

  17. Metamorphosis of NPP A1, V1, V2

    International Nuclear Information System (INIS)

    Dobak, D.; Moncekova, M.

    2005-01-01

    In this book the history of construction, commissioning and exploitation of NPP A1, NPP V1 and NPP V2 in Jaslovske Bohunice is presented on documentary photos. Vicinity around of these NPPs is presented, too

  18. Ignalina NPP: living and working conditions

    International Nuclear Information System (INIS)

    Chiuzhas, A.

    1998-01-01

    The conference was devoted to discuss the social problems related with the operation of Ignalina NPP. The main topics are the following: analysis of public opinion of surrounding region of Ignalina NPP including neighbouring Daugavpils district in Latvia, environment impact evaluation of Daugavpils district, assessment of the influence of Ignalina NPP operation to the development of business in the region, investigation of problems of Visaginas town - residence of Ignalina NPP personnel. The specificity of Visaginas (former Sniechkus) is defined by the majority of non-native Lithuanians living there. Cultural transformation and political organization of the region were surveyed as well

  19. Safety enhancement concept for NPP of new generation with VVER reactors

    International Nuclear Information System (INIS)

    Bezlepkin, V.; Kukhtevich, I.; Semashko, S.; Svetlov, S.; Solodovnikov, A.

    2004-01-01

    With the present day conditions, in order to successfully promote new NPP designs in the electric power markets, it is necessary to ensure enhanced technical/economic performances provided that international safety requirements are properly adhered to. When compared with high-powered nuclear power plants, NPP VVER-640 design (medium powered) possesses a number of advantages for the regions with undeveloped energy systems. Reduced specific energy intensity of the core adopted in this type of reactor allows to ensure the emergency cooldown of the reactor plant by passive means and to minimize the 'human factor' risk and external effects and provide sound substantiations as to how to retain corium inside RPV in case of severe accidents. At the same time, high-powered NPPs seem to be promising for regions with developed energy systems. Among such designs, NPP VVER-1000 and VVER-1500 designs are the most desirable. Configuration of new generation NPP with VVER-1500 is to be selected based on the gained experience in designing NPPs of previous generations considering the latest safety requirements and situation in the domestic and global energy markets for the time being and in the short run. Recent IAEA publications and latest EUR requirements insist that the following key safety indices should be established for new NPP designs: - aggregated frequency of core melting is 10 -6 (1/year); - frequency of maximum accident release is 10 -7 (1/year). To meet the aforementioned criteria, it is necessary to implement some safety assurance principles recommended by IAEA (in-depth defence, single failure, redundancy, diversity, etc.), application of deterministic and probabilistic methods for selection of safety assurance activities and means and use of reasonable combination of active and passive systems. Application of VVER-640 concept to high-powered NPPs seems to be a formidable task due to a number of reasons, namely, it is quite difficult to carry out cooldown process

  20. The RELAP5-Based NPA of the VVER Type Paks NPP

    International Nuclear Information System (INIS)

    Guba, A.; Toth, I.; Mandy, C.; Stubbe, E.

    1999-01-01

    NPA is a data driven interactive graphical tool for visualisation of different plant conditions. Data generated by the analysis code RELAP5/MOD3.2 are processed and displayed on a computer monitor. The NPA model of Paks NPP Unit 3 was developed with the aim to demonstrate the phenomena occurring in different transient/accident scenarios. This VVER-specific NPA development is a result of a cooperation between BELGATOM and KFKI-AEKI. (author)

  1. Regulation Plans on Severe Accidents developed by KINS Severe Accident Regulation Preparation TFT

    International Nuclear Information System (INIS)

    Kim, Kyun Tae; Chung, Ku Young; Na, Han Bee

    2016-01-01

    Some nuclear power plants in Fukushima Daiichi site had lost their emergency reactor cooling function for long-time so the fuels inside the reactors were molten, and the integrity of containment was damaged. Therefore, large amount of radioactive material was released to environment. Because the social and economic effects of severe accidents are enormous, Korean Government already issued 'Severe Accident Policy' in 2001 which requires nuclear power plant operators to set up 'Quantitative Safety Goal', to do 'Probabilistic Safety Analysis', to install 'Severe Accident Countermeasures' and to make 'Severe Accident Management Plan'. After the Fukushima disaster, a Special Safety Inspection was performed for all operating nuclear power plants of Korea. The inspection team from industry, academia, and research institutes assessed Korean NPPs capabilities to cope with or respond to severe accidents and emergency situation caused by natural disasters such as a large earthquake or tsunami. As a result of the special inspection, about 50 action items were identified to increase the capability to cope with natural disaster and severe accidents. Nuclear Safety Act has been amended to require NPP operators to submit Accident Management Plant as part of operating license application. The KINS Severe Accident Regulation Preparation TFT had first investigated oversea severe accident regulation trend before and after the Fukushima accident. Then, the TFT has developed regulation draft for severe accidents such as Severe accident Management Plans, the required design features for new NPPs to prevent severe accident against multiple failures and beyond-design external events, countermeasures to mitigate severe accident and to keep the integrity of containment, and assessment methodology on safety assessment plan and probabilistic safety assessment

  2. Regulation Plans on Severe Accidents developed by KINS Severe Accident Regulation Preparation TFT

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyun Tae; Chung, Ku Young; Na, Han Bee [KINS, Daejeon (Korea, Republic of)

    2016-05-15

    Some nuclear power plants in Fukushima Daiichi site had lost their emergency reactor cooling function for long-time so the fuels inside the reactors were molten, and the integrity of containment was damaged. Therefore, large amount of radioactive material was released to environment. Because the social and economic effects of severe accidents are enormous, Korean Government already issued 'Severe Accident Policy' in 2001 which requires nuclear power plant operators to set up 'Quantitative Safety Goal', to do 'Probabilistic Safety Analysis', to install 'Severe Accident Countermeasures' and to make 'Severe Accident Management Plan'. After the Fukushima disaster, a Special Safety Inspection was performed for all operating nuclear power plants of Korea. The inspection team from industry, academia, and research institutes assessed Korean NPPs capabilities to cope with or respond to severe accidents and emergency situation caused by natural disasters such as a large earthquake or tsunami. As a result of the special inspection, about 50 action items were identified to increase the capability to cope with natural disaster and severe accidents. Nuclear Safety Act has been amended to require NPP operators to submit Accident Management Plant as part of operating license application. The KINS Severe Accident Regulation Preparation TFT had first investigated oversea severe accident regulation trend before and after the Fukushima accident. Then, the TFT has developed regulation draft for severe accidents such as Severe accident Management Plans, the required design features for new NPPs to prevent severe accident against multiple failures and beyond-design external events, countermeasures to mitigate severe accident and to keep the integrity of containment, and assessment methodology on safety assessment plan and probabilistic safety assessment.

  3. Accident tolerant fuel analysis

    International Nuclear Information System (INIS)

    2014-01-01

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced ''RISMC toolkit'' that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional ''accident-tolerant'' (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant

  4. Prediction of hydrogen concentration in nuclear power plant containment under severe accidents using cascaded fuzzy neural networks

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Geon Pil; Kim, Dong Yeong; Yoo, Kwae Hwan; Na, Man Gyun, E-mail: magyna@chosun.ac.kr

    2016-04-15

    Highlights: • We present a hydrogen-concentration prediction method in an NPP containment. • The cascaded fuzzy neural network (CFNN) is used in this prediction model. • The CFNN model is much better than the existing FNN model. • This prediction can help prevent severe accidents in NPP due to hydrogen explosion. - Abstract: Recently, severe accidents in nuclear power plants (NPPs) have attracted worldwide interest since the Fukushima accident. If the hydrogen concentration in an NPP containment is increased above 4% in atmospheric pressure, hydrogen combustion will likely occur. Therefore, the hydrogen concentration must be kept below 4%. This study presents the prediction of hydrogen concentration using cascaded fuzzy neural network (CFNN). The CFNN model repeatedly applies FNN modules that are serially connected. The CFNN model was developed using data on severe accidents in NPPs. The data were obtained by numerically simulating the accident scenarios using the MAAP4 code for optimized power reactor 1000 (OPR1000) because real severe accident data cannot be obtained from actual NPP accidents. The root-mean-square error level predicted by the CFNN model is below approximately 5%. It was confirmed that the CFNN model could accurately predict the hydrogen concentration in the containment. If NPP operators can predict the hydrogen concentration in the containment using the CFNN model, this prediction can assist them in preventing a hydrogen explosion.

  5. Thirtieth anniversary of reactor accident in A-1 Nuclear Power Plant Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Kuruc, J.; Matel, L.

    2007-01-01

    The facts about reactor accidents in A-1 Nuclear Power Plant Jaslovske Bohunice, Slovakia are presented. There was the reactor KS150 (HWGCR) cooled with carbon dioxide and moderated with heavy water. A-1 NPP was commissioned on December 25, 1972. The first reactor accident happened on January 5, 1976 during fuel loading. This accident has not been evaluated according to the INES scale up to the present time. The second serious accident in A-1 NPP occurred on February 22, 1977 also during fuel loading. This INES level 4 of reactor accident resulted in damaged fuel integrity with extensive corrosion damage of fuel cladding and release of radioactivity into the plant area. The A-1 NPP was consecutively shut down and is being decommissioned in the present time. Both reactor accidents are described briefly. Some radioecological and radiobiological consequences of accidents and contamination of area of A-1 NPP as well as of Manivier Canal and Dudvah River as result of flooding during the decommissioning are presented (authors)

  6. Analysis of transients for NPP with VVER-440 using the code SiTAP

    International Nuclear Information System (INIS)

    Kalinenko, V.

    1994-06-01

    The report contains analysis of transients ''Loop connection'' and ''Steam generator tube rupture'' for nuclear power plants (NPP) with VVER-440. To obtain more detailed information about NPP's dynamic characteristics, various variants of initial and boundary conditions are considerd. Calculation of these transients was performed using the SiTAP code developed at the Nuclear Safety Institute of the Russian Research Centre ''Kurchatov Institute''. SiTAP code is a multifunctional computer tool for fast analysis of transient and accidental processes of VVER type reactors for engineers working in the field of NPP dynamics. SiTAP can be used form comparative analysis of several variants of accident scenarios to find out the conditions leading to most serious consequences from a safety point of view. In such cases, additional analyses using best-estimate codes should be carried out. The results of SiTAP for a faulty loop connection leading to a boron dilution accident are intended to be used as boundary conditions for a more detailed anlaysis with the aid of the three-dimensional reactor core model DYN3D, developed in the Research Centre Rossendorf for the simulation of reactivity initiated accidents. (orig.)

  7. The application of the health effects models to the severe accident consequence analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Yang Ling; Yeung, M.R.

    1998-01-01

    Health Effect Model (HEM) is an important model used in the analysis of severe accidents consequence of the Nuclear Power Plants (NPP). The accuracy of HEM affects the reliability of the assessment for the accidents consequences, and furthermore, the effectiveness of the emergency countermeasures taken for the health protection of the public around the NPPs. Based on the NUREG/CR4214 series reports, the paper sets appropriate parameters for HEM by studying both early and late HEMs used for domestic NPP accident consequence analysis. In the study, the Guangdong Daya Bay NPP is chosen as an example study to calculate the health risk of the Hong Kong population caused by Daya Bay NPP

  8. Radiation monitoring in the NPP environment, control of radioactivity in NPP-environment system

    International Nuclear Information System (INIS)

    Egorov, Yu.A.

    1987-01-01

    Problems of radiation monitoring and control of the NPP-environment system (NPPES) are considered. Radiation control system at the NPP and in the environment provides for the control of the NPP, considered as the source of radioactive releases in the environment and for the environmental radiation climate control. It is shown, that the radiation control of the NPP-environment system must be based on the ecological normalization principles of the NPP environmental impacts. Ecological normalization should be individual for the NPP region of each ecosystem. The necessity to organize and conduct radiation ecological monitoring in the NPP regions is pointed out. Radiation ecological monitoring will provide for both environmental current radiation control and information for mathematical models, used in the NPPES radiation control

  9. Display systems for NPP control

    International Nuclear Information System (INIS)

    Rozov, S.S.

    1988-01-01

    Main trends in development of display systems used as the means for image displaying in NPP control systems are considered. It is shown that colour display devices appear to be the most universal means for concentrated data presentation. Along with digital means the display systems provide for high-speed response, sufficient for operative control of executive mechanisms. A conclusion is drawn that further development of display systems will move towards creation of large colour fields (on reflection base or with multicolour gas-discharge elements)

  10. Emergency preparedness at Barsebaeck NPP in Sweden

    International Nuclear Information System (INIS)

    Olsson, R.; Lindvall, C.

    1998-01-01

    On-site emergency preparedness plan at Barsebaeck NPP is presented. In an emergency the responsibility of the NPP is to alarm the emergency organizations, spend all efforts to restore safe operation, assess the potential source term as to size and time, protect their own personnel, inform personnel and public. Detailed emergency procedures overview is provided

  11. Safety culture in Ignalina NPP, regulatory view

    Energy Technology Data Exchange (ETDEWEB)

    Maksimovas, G [VATESI (Lithuania)

    1997-09-01

    The presentation describes how success on the way to a high level Safety Culture in Ignalina NPP may be achieved by daily, well motivated activities with good attitude and proper management participation, ensuring the development and proper implementation of Safety Culture principles within the activities of Operational organization of Ignalina NPP.

  12. Safety culture in Ignalina NPP, regulatory view

    International Nuclear Information System (INIS)

    Maksimovas, G.

    1997-01-01

    The presentation describes how success on the way to a high level Safety Culture in Ignalina NPP may be achieved by daily, well motivated activities with good attitude and proper management participation, ensuring the development and proper implementation of Safety Culture principles within the activities of Operational organization of Ignalina NPP

  13. Constructive approaches to the space NPP designing

    International Nuclear Information System (INIS)

    Eremin, A.G.; Korobkov, L.S.; Matveev, A.V.; Trukhanov, Yu.L.; Pyshko, A.P.

    2000-01-01

    An example of designing a space NPP intended for power supply of telecommunication satellite is considered. It is shown that the designing approach based on the introduction of a leading criterion and dividing the design problems in two independent groups (reactor with radiation shield and equipment module) permits to develop the optimal design of a space NPP [ru

  14. NPP Bohunice experience with ASSET services

    International Nuclear Information System (INIS)

    Klimo, J.

    1996-01-01

    The general description of Bohunice NPP ASSET experience history was given at the last annual workshop in 1995. In my short presentation I would like to pay attention to the progress in this area which was achieved at our NPP during the last year. (author)

  15. NPP Bohunice experience with ASSET services

    Energy Technology Data Exchange (ETDEWEB)

    Klimo, J [Bohunice NPP (Slovakia)

    1997-12-31

    The general description of Bohunice NPP ASSET experience history was given at the last annual workshop in 1995. In my short presentation I would like to pay attention to the progress in this area which was achieved at our NPP during the last year. (author).

  16. Bohunice V1 NPP upgrading programme

    International Nuclear Information System (INIS)

    Kerak, J.

    2001-01-01

    The paper describes whole process of Bohunice V1 NPP nuclear safety and operational reliability level increase which has been performed since units commissioning (1. unit in 1978, 2. unit in 1980), continued Small Reconstruction (1991 -1993) and finished Gradual Upgrading(1994 -2000). The main purpose is to last stage -Gradual upgrading of Bohunice V1 NPP. (author)

  17. Achievements and challenges of Paks NPP

    International Nuclear Information System (INIS)

    Bajsz, J.; Katona, T.

    2002-01-01

    As the six year long safety upgrading program at Paks NPP is approaching its final stage this year, it is a good opportunity to draw the conclusion: what have been done and how have measures influenced the safety of the plant. In its first part the paper gives an overview of the program's main issues, assesses the results from the point of view of safety, reliability and cost effectiveness as well. In the second part a survey of future tasks follows: (1) Hungary is joining to the EU. The accession process so far has not revealed any major problems concerning nuclear safety which could be seen as obstacles toward the membership. However the plant should be ready to meet the increasing level of safety regulations. Further safety upgrading measures are planned, mostly in the field of severe accident management. (2) The electricity market liberalisation in Hungary will start in 2003 and being a EU member state, the full market opening will happen within a few years. The plant has to take into account the specificity of market functioning. The most important thing is to preserve the present cost advantage of nuclear electricity generation within the market conditions. The paper presents measures performed and planned to keep the unit generation cost competitive. (3) The first unit at Paks will mark its 20't'h anniversary this year. Lifetime management issues are at the centre of the engineering activities. The work already started to prepare the lifetime extension for 20 years. The program for the license renewal, which was elaborated jointly with the nuclear regulatory body will be described.(author)

  18. Normal accidents

    International Nuclear Information System (INIS)

    Perrow, C.

    1989-01-01

    The author has chosen numerous concrete examples to illustrate the hazardousness inherent in high-risk technologies. Starting with the TMI reactor accident in 1979, he shows that it is not only the nuclear energy sector that bears the risk of 'normal accidents', but also quite a number of other technologies and industrial sectors, or research fields. The author refers to the petrochemical industry, shipping, air traffic, large dams, mining activities, and genetic engineering, showing that due to the complexity of the systems and their manifold, rapidly interacting processes, accidents happen that cannot be thoroughly calculated, and hence are unavoidable. (orig./HP) [de

  19. Seismic characterization of the NPP Krsko site

    International Nuclear Information System (INIS)

    Obreza, J.

    2000-01-01

    The goal of NPP Krsko PSA Project Update was the inclusion of plant changes (i.e. configuration/operational related) through the period January 1, 1993 till the OUTAGE99 (April 1999) into the integrated Internal/External Level 1/Level 2 NPP Krsko PSA RISK SPECTRUM model. NPP Krsko is located on seismotectonic plate. Highest earthquake was recorded in 1917 with magnitude 5.8 at a distance of 7-9 km. Site (founded) on Pliocene sediments which are as deep as several hundred meters. No surface faulting at the Krsko site has been observed and thus it is not to be expected. NPP Krsko is equipped with seismic instrumentation, which allows it to complete OBE (SSE). The seismic PSA successfully showed high seismic margin at Krsko plant. NPP Krsko seismic design is based on US regulations and standards

  20. Neutronic calculations for Angra-1 steam line break accident

    International Nuclear Information System (INIS)

    Ponzoni Filho, Pedro; Sato, Sadakatu

    2000-01-01

    The reduction of boron concentration in the Boron Injection Tank (BIT), to the room temperature solubility level, makes necessary a reanalysis of the steam line break accident of Angra 1 NPP. This paper describes the neutronic calculation related to this reanalysis. The main steps of the work were: review of reactivity parameters used in the accident simulation; search of xenon profiles that cause the most severe core power distribution; calculation of hot channel factors and other neutronic parameters necessary for DNBR determination. The final conclusion, related to the steam line break accident, states the BIT concentration may be reduced to 2000 ppm. (author)