Integrated ageing management of Atucha NPP

International Nuclear Information System (INIS)

Ranalli, Juan M.; Marchena, Martin H.; Zorrilla, Jorge R.; Antonaccio, Elvio E.; Brenna, Pablo; Yllanez, Daniela; Cruz, Gerardo Vera de la; Luraschi, Carlos; Sabransky, Mario

2013-01-01

Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor, twice as big as Atucha I finishing a delayed construction. With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

Integrated Ageing Management of Atucha NPP

International Nuclear Information System (INIS)

Ranalli, J.M.; Marchena, M.H.; Zorrilla, J.R.; Sabransky, M.

2012-01-01

Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor twice as big as Atucha I finishing a delayed construction . With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

Integrated ageing management of Atucha NPP

Energy Technology Data Exchange (ETDEWEB)

Ranalli, Juan M.; Marchena, Martin H.; Zorrilla, Jorge R.; Antonaccio, Elvio E.; Brenna, Pablo; Yllanez, Daniela; Cruz, Gerardo Vera de la; Luraschi, Carlos, E-mail: ranalli@cnea.gov.ar [Gerencia Coordinacion Proyectos CNEA-NASA, Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Sabransky, Mario, E-mail: msabransky@na-sa.com.ar [Departamento Gestion de Envejecimiento, Central Nuclear Atucha I-II Nucleoelectrica Argentina S.A., Provincia de Buenos Aires (Argentina)

2013-07-01

Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor, twice as big as Atucha I finishing a delayed construction. With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

Compact spent fuel storage at the Atucha I nuclear power plant

International Nuclear Information System (INIS)

Antonaccio, Carlos; Conde, Alberto; Flores, Alexis; Masciotra, Humberto; Sala, Guillermo; Zanni, Pablo

2000-01-01

The object of this report is to verify the possibility to increase the available storage of irradiated fuel assemblies, placed in the spent fuel pools of the Atucha I nuclear power plant. There is intends the realization of structural modifications in the storage bracket-suspension beam (single and double) for the upper and lower level of the four spent fuel pools. With these modifications that increase the storage capacity 25%, would arrive until the year 2014, it dates dear for the limit of the commercial operation of nuclear power plant. The increase of the capacity in function of the permissible stress for the supports of the bracket-suspension beam. They should be carried out 5000 re-accommodations of irradiated fuel assemblies. The task would demand approximately 3 years. (author)

ATUCHA I NPP - Emergency drill practice

International Nuclear Information System (INIS)

Sanda, Alejandro; Rosales, Gabriel

2008-01-01

Full text: Atucha I NPP performs an Emergency Drill Practice once a year. Its main goals are: -) Fulfill the requirements of the Argentine Nuclear Regulatory Authority (ARN) regarding Atucha I NPP's Operating License; -) Fulfill the commitment with the community regarding the safe and reliable operation Atucha I NPP; -) Verify the response of the Civil Organizations, Security Forces, and Armed Forces, as well as the correct application of the Emergency Plan; -) Perform the 'General Alarm Drill' periodic control; -) Perform a re-training of the members of the Security Advisor Internal Committee (CIAS) on the Internal and External Aspects of the Emergency Plan and on the related procedures; -) Test the Emergency Communications System. New goals are added every year, considering the Drill's scope. This drill comprises two different kinds of practices: Internal practices (practices in the station, with our personnel) and external practices (practices outside the station with governmental organizations). Internal practices comprise: -) Internal and external communications practices; -) Acoustic alarms; -) Personnel gathering in the Meeting Points; -) Safety of selected Meeting Points; -) Personnel count, selective evacuation; -) Iodide Potassium pills distribution; -) CICE (Internal Group for Emergency Control) Coordination. External practices comprise: -) Nuclear Regulatory Authority; -) Argentine Navy, Comando Area Naval Fluvial, Base Naval Zarate; -) Lima firemen; -) Zarate firemen; -) Municipal Civil Defense (Zarate and Lima); -) National Guard, Escuadron Atucha; -) Zarate Regional Hospital; -) Lima Police Department; -) Zarate Police Department; -) Argentine Coast Guard, Zarate; -) Local radios: Radio FM Libre, FM El Sitio; -) First Aid clinic. The following activities are performed together with the aforementioned organizations: -) Formation of an 'Operative committee'; -) Evacuation of citizens in a 3 km radio; -) Control of every access to Lima; -) Control of

Fracture mechanical analysis of relevant transients in the pressure vessel of Atucha I reactor

International Nuclear Information System (INIS)

Saavedra, Fernando M.

2001-01-01

The evolution of the applied stress intensity factor K I for 10 relevant transients of the nuclear power station Atucha I obtained from thermohydraulic data is analyzed according to the methodology proposed in Section XI of ASME Boiler and Pressure Vessel Code. Vast knowledge was thus obtained about basic concepts of fracture mechanics and its application to remanent life of nuclear components. Basic knowledge which commands the performance of nuclear power stations was also obtained, especially that related to the Atucha I utility [es

Measurement of the CNA I's (Atucha I nuclear power plant) control rods reactivity during its commissioning on January 8th, 1990

International Nuclear Information System (INIS)

Waldman, R.M.; Gomez, A.

1990-01-01

Measurements were made on integral and differential calibration of rod 16, fuel racks RG and R3 and extinction reactivity during Atucha I nuclear power plant's commissioning on January 8th., 1990. These were the first physical measurements performed after the first critical nuclear power plant's commissioning. (Author) [es

Atucha II nuclear power plant digital simulation

International Nuclear Information System (INIS)

Santome, D.; Rovere, L.A.T.

1987-01-01

This paper describes the start-up of a digital simulation code apt to be performed in real time of Atucha II nuclear power plant, foreseeing its subsequent usage in a Basic Principles Simulator. Adaptability and modification of existing routines and development of modules in order to incorporate the necessary variables dynamics to couple the different modes, were the main tasks. The mathematical model used allows the representation of the following sub-systems: a) a reactor's core point model, which comprehends the neutronic kinetics, fission and decaying powers, thermal transfer and Xe-poisoning calculation; b) pressurizer, which considers two sub-systems that may or may not be in thermodynamic equilibrium, both in two phases; c) coolants and moderators bonds considering separate moderator loops with the aim of introducing asymmetric perturbations; d) secondary sub-subsystem, which includes the feed water loop, pumps, steam generators and control valves; e) steam generators; f) control and safety systems, including power control, steam generators levels, moderator's temperature primary loop system, limitations and protection. (Author)

Activity determination for neutron dosimetry in the vigilance programme for the pressure vessel in Atucha I nuclear power plant

International Nuclear Information System (INIS)

Furnari, J.C.; Cohen, I.M.; Ciriani, D.F.; Helzel Garcia, J.

1993-01-01

The methodologies for the activity determination of Co-60, Nb-93m and Nb-94 in flux monitors are presented. This was done in order to evaluate dose and damage caused by radiation received by pressure vessel materials of the Atucha I nuclear power plant for its surveillance program. (author)

Improvements related with the safety required by the Argentine Regulatory Authority to the Atucha I Nuclear Central; Mejoras relacionadas con la seguridad requeridas por la Autoridad Regulatoria Argentina a la Central Nuclear Atucha I

Energy Technology Data Exchange (ETDEWEB)

Calvo, J.; Michelin, C.; Navarro, R.; Waldman, R. [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250, 1429- Ciudad de Buenos Aires (Argentina)]. e-mail: jcalvo@sede.arn.gov.ar

2006-07-01

The Argentinean Nuclear Regulation Authority (ARN) verified the existence of changes in the state of some internal components of the reactor of the Atucha I Nuclear Power station that, of continuing in the time, it could take to an inconvenient degradation for the safety operation of the installation. In consequence, to the effects of preventing that reach this situation, at the end of 1999, the ARN required to the Responsible Entity for the operation of this power station the implementation of an important improvements program in the internal components of the reactor. Additionally, and based on the results of the Probabilistic Safety analysis, it was added the one mentioned improvements program the implementation of an alternative cooling system of the reactor core denominated Second Drain of Heat, due to it was determined that, for some accidental sequences, their performance would reduce considerably the probability of damage to the core. The concretion of the improvements program implied to the Responsible Entity the realization of an important quantity of engineering studies, tests and specific inspections that allowed to carry out changes on the control bars of the reactor and its guide tubes; the coolant channels; the sensors of neutron flow; and diverse components of the primary and moderator systems. On the other hand also it was implemented the system Second Drain of Heat, what represents a considerable effort to make compatible the instrumentation and control of last generation, with the instrumentation and existent control systems in the power station. Also, it was requested to be carried out an integrity of the pressure recipient for to demonstrate the existence of an acceptable margin for the difference among the acceptable limit temperatures and of ductile/fragile transition of the material for all the possible accidental scenarios during the useful life of the reactor. (Author)

Temporary storage facility for spent nuclear fuels at the Atucha I nuclear power station (CNA)

International Nuclear Information System (INIS)

Wasinger, K.

1983-01-01

According to plans of the Argentine Atomic Energy Commission (CNEA), the spent nuclear fuel elements of the Atucha I Nuclear Power Station are to be stored temporarily pending a decision about the ultimate disposal concept. The holding capacity of the first fuel storage facility built by the German KWU together with the whole power plant had been expanded in 1978 to a level good until mid-1982. In 1977, KWU drafted the concept of another fuel storage facility. Like the first one, it was designed as a wet storage system attached to the power plant installations and had a holding capacity of 6944 fuel elements, which corresponds to some 1100 te of uranium. This extends the storage capacity up until 1996. In 1978, KWU was commissioned by CNEA to plan the whole facility and deliver the mechanical and electrical equipment. CNEA themselves assumed responsibility for the construction work. The second fuel storage facility was commissioned three years after the start of construction. (orig.) [de

Pressure waves transient occurred in the steam generators feedwater lines of the Atucha-1 Nuclear Power Plant

International Nuclear Information System (INIS)

Balino, J.L.; Carrica, P.M.; Larreteguy, A.E.

1993-01-01

The pressure transient occurred at Atucha I Nuclear Power Plant in March 1990 is simulated. The transient was due to the fast closure of a flow control valve at the steam generators feedwater lines. The system was modelled, including the actuation of the relief valves. The minimum closure time for no actuation of the relief valves and the evolution of the velocity and piezo metric head for different cases were calculated. (author)

Atucha II NPP full scope simulator modelling with the thermal hydraulic code TRACRT

International Nuclear Information System (INIS)

Alonso, Pablo Rey; Ruiz, Jose Antonio; Rivero, Norberto

2011-01-01

In February 2010 NA-SA (Nucleoelectrica Argentina S.A.) awarded Tecnatom the Atucha II full scope simulator project. NA-SA is a public company owner of the Argentinean nuclear power plants. Atucha II is due to enter in operation shortly. Atucha II NPP is a PHWR type plant cooled by the water of the Parana River and has the same design as the Atucha I unit, doubling its power capacity. Atucha II will produce 745 MWe utilizing heavy water as coolant and moderator, and natural uranium as fuel. A plant singular feature is the permanent core refueling. TRAC R T is the first real time thermal hydraulic six-equations code used in the training simulation industry for NSSS modeling. It is the result from adapting to real time the best estimate code TRACG. TRAC R T is based on first principle conservation equations for mass, energy and momentum for liquid and steam phases, with two phase flows under non homogeneous and non equilibrium conditions. At present, it has been successfully implemented in twelve full scope replica simulators in different training centers throughout the world. To ease the modeling task, TRAC R T includes a graphical pre-processing tool designed to optimize this process and alleviate the burden of entering alpha numerical data in an input file. (author)

Permission of change of limits in the vapor generators of the Atucha I Nuclear Central; Permiso de cambio de limites en los GVs de la CNA-I

Energy Technology Data Exchange (ETDEWEB)

Ventura, M. [Autoridad Regulatoria Nuclear, Av. Libertador 8250 (1429), Capital Federal (Argentina)]. e-mail: mventura@sede.arn.gov.ar

2006-07-01

In the mark of the modification of the Atucha-I Nuclear Central Installation (CNA-I) as consequence of the Introduction of the System 'Second Drain of Heat' (SSC), the Entity Responsible for the CNA-I (NASA) requested authorization to the Nuclear Regulatory Authority (ARN) to modify the value of the minimum level of water in the secondary side in the Steam generators (GVs) to activate the signal 'shoot of the Cut of the Reactor' (RESA-LLV). As the level in the GVs is one of those parameters that are used to shoot the Emergency Feeding System (RX), component of the SSC System, also was analyzed the change in the activation of the shoot signal of the 'Second Drain of Heat' (2SSC-LLV). The ARN uses for the study of the nuclear safety of nuclear power plants, the series of prediction programs RELAP5/MOD3.X. It participates of the evaluation and maintenance activities of these codes through specific agreements with the U.S. Nuclear Regulatory Commission (US-NRC). It is necessary to account with programs of this type since the ARN it licenses the construction and operation of Nuclear Power Plants (NPPs) and other outstanding facilities and it inquires its operation according to its own standards. With these tools its are auditing the calculations that the Responsible Entities of the operation make to guarantee the operability of the NPPs assisting the mentioned standards. The analysis with computational codes is used as a tool to achieve the best understanding in the behavior of the plant in union with the engineering approach, the manual calculations, the data analysis and the experience in the operation of the machine. (Author)

How Belgium helped establish a surveillance programme for Argentina's Atucha-2

Energy Technology Data Exchange (ETDEWEB)

Mitev, Lubomir [NucNet, Brussels (Belgium)

2015-02-15

Collaboration between Belgian experts and Argentina on the commissioning of Argentine reactors helped overcome problems caused by delays with construction. Marc Scibetta, deputy manager for nuclear materials science, from the Belgian Nuclear Research Centre (SCK CEN) gave an interview in which he told some facts to Lubomir Mitev of NucNet. The cooperation between SCK CEN an Argentina's Comision Nacional de Energia Atomica (CNEA) started in 2002. The first project was a support for the safety evaluation of the Atucha-1 reactor pressure vessel. When Argentina resumed the construction of Atucha-2 in 2006 - originally, construction started in 1981 but was suspended in 1985 due to financial reasons -, SCK CEN was asked to develop and implement a surveillance programme for the unit.

Summary of severe accident assessment for Atucha 2 Nuclear Power Plant using RELAP5/SCDAPSIM Mod3.6

International Nuclear Information System (INIS)

Bonelli, Analia; Mazzantini, Oscar; Siefken, Larry; Allison, Chris

2014-01-01

A severe accident assessment was performed for the Atucha 2 Nuclear Power Plant in Argentina. Atucha 2 is a PHWR, cooled and moderated by heavy water, presently in commissioning process. Its 451 fuel assemblies are 6.03m high and each composed of 37 Zircaloy clad fuel rods. Each assembly is placed inside an individual Zircaloy coolant channel. Heavy water coolant flows inside the channels which are all immersed inside the moderator tank. The RPV lower plenum is occupied by a massive steel structure called 'filling body' that was designed to minimize heavy water inventory. Due to some unique design characteristics, severe accident progression in Atucha 2 is expected to be somewhat different from that predicted for regular PWRs. Therefore, a very detailed assessment was performed, focused on the different accident stages and expected phenomena by the use of different input models and nodalizations. When possible, linking to available experimental data was performed. RELAP/SCDAPSIM Mod 3.6 was the computer code selected to perform this task. The modeling of Atucha 2's unique characteristics required several extensions to the code. For the severe accident assessment of Atucha 2, three different input models were developed that were key instruments for the debugging and evaluation process. A Single Channel Model was used to evaluate the first stages of core heatup (including the boiloff of the channels and moderator tank), an RPV standalone model was used to assess the interaction between components in the complete core and for the evaluation of late in-core melting and relocation. Then, a Lower Plenum standalone model was developed to assess the behavior of the melted and slumped core material on top of the filling body and to analyze ex-vessel cooling as a possible severe accident management action. For each of the cases, highlights of key results are shown and general conclusions are drawn. In the case of a severe accident with significant meltdown of

Implementation of the utilization program for the fuel elements of the Atucha I nuclear power plant

International Nuclear Information System (INIS)

Martin, H.R.; Serra, O.H.; Parker, Alejandro

1981-01-01

The programming operation for the use of the fuel elements in the Atucha-1 nuclear power plant was initially under the responsibility of the KWU Company, as part of the services rendered due for the manufacturing of said elements. This job was done with the help of the TRISIC program, developed in the early seventies by CNEA and SIEMENS staff. From april 21, 1979 on, CNEA took over the responsibility and strategy of the interchange of fuel elements. The several stages carried out for the implementation of this service are detailed. (M.E.L.) [es

Reactor building design of nuclear power plant ATUCHA II, Argentina

International Nuclear Information System (INIS)

Rufino, R.E.; Hermann, E.R.; Richter, E.

1984-01-01

It is presented the civil engineering project carried out by the joint venture Hochtief - Techint-Bignoli (HTB) for the reactor building at the Atucha II power plant (PHWR of 745 MWe) in Buenos Aires. All the other civil projects at Atucha II are also being carried out by HTB. This building has the same general characteristics of the PWR plants developed by KWU in Germany, known for the spherical steel containment 56m in diameter. Nevertheless, it differs from those principally in the equipment lay-out and the remarkable foundation depth. From the basic engineering provided by ENACE, the joint venture has had to face the challenge of designing a tridimensional structure of large size. This has necessitated using simplified models which had to be superimposed, since the use of only one spatial mode would be highly inadequate, lacking the flexibility necessary to absorb the numerous modifications that this type of project undergoes during construction. In addition, this procedure has eliminated resorting to numerous and costly computer processings. (Author) [pt

Detection and analysis of thermal energy loss in the Atucha I nuclear power plant residual heat removal system

International Nuclear Information System (INIS)

Berra, Sandra; Guala, Mariana I.; Khon, Hector; Lorenzo, Andrea T.; Raffo Calderon, Maria C.; Urrutia, Guillermo

1999-01-01

It is presented the methodology used to detect and to measure energy losses which are existent in the Atucha I nuclear power plant. They were not directly detected, since the magnitude of those was below of the instrumentation precision which is used to measure the electric and thermal power in the plant. To achieve this work temperature special measurements were made. In this way it was possible to quantify the energy losses after operational long periods. (author)

The application of the PARCS neutronics code to the Atucha-I and Atucha-II NPPs

Energy Technology Data Exchange (ETDEWEB)

Ward, Andrew; Collins, Ben; Xu, Yunlin; Downar, Thomas [Purdue University, West Lafayette, IN (United States); Madariaga, Marcelo [Autoridad Nuclear Regulatoria, Buenos Aires (Argentina)

2008-07-01

In order to analyze Central Nuclear Atucha II (CNA-II) with coupled RELAP5/PARCS, extensive benchmarking of the neutronics codes HELIOS and PARCS was completed. This benchmarking was performed using a range of test problems designed in collaboration with NA-SA. HELIOS has been previously used to model Candu systems, but the results were validated for this case as well. The validation of both HELIOS and PARCS was performed primarily by comparisons to MCNP results for the same problems. Though originally designed to model light water systems, the capability of the PARCS was validated for predicting the performance of a Pressurized Heavy Water Reactor. The other noteworthy issue was the control rods. Because the insertion of the rods is oblique, a special routine was added to PARCS to treat this effect. Lattice level and Core level calculations were compared to the corresponding NA-SA codes WIMS and PUMA. In all cases there was good agreement in the results which provided confidence that the neutronics methods and the core neutronics modelling would not be a significant source of error in coupled RELAP5/PARCS calculations. (authors)

Atucha I nuclear power plant azimuthal ex-vessel flux profile evaluation

International Nuclear Information System (INIS)

Ferraro, Diego

2008-01-01

Irradiation damage in RPV (Reactor Pressure Vessel) in nuclear power plants is a key parameter to be analyzed in order to assess the plant integrity up to end of life and planning for a possible plant life extension. In this work a neutronic model in MCNP that represents a sector of 30 degrees of the Atucha I power plant nucleus has been consolidated with the results of an ex-vessel dosimetry made in the outer surface of the RPV s power plant in order to analyse the irradiation damage through the dpa rate. A strong dependents of the maximum point of damage with the loading of a peripheral channel was found, so a mitigation strategy was proposed, which is basically to empty this channel and its analogs in the rest of the nucleus. Analysing this second case a notable decrease of the damage is found in the zone considerated on the model (shown through the drop of de dpa rate in the zone). [es

Model and simulation of the hydraulic turbine speed regulator of the Atucha I nuclear power plant

International Nuclear Information System (INIS)

Copparoni, G.; Etchepareborda, A.; Urrutia, G.

1992-01-01

The hydraulics turbines of Atucha I Nuclear Power Plant takes advantage of condenser cooling water level difference between the plant and the river to recover about 2,5 MW e. It also supplies emergency power until diesel generators start up. Speed regulation is needed due to the transients that during this process occur. The purpose is to minimize the diesels start up time, and to avoid overshoots on the internal grid frequency. The hydraulic turbine, its speed regulator and the electric system associated with this transient have been modeled. The models and some simulation results are presented in this work. (author)

Improvements related with the safety required by the Argentine Regulatory Authority to the Atucha I Nuclear Central

International Nuclear Information System (INIS)

Calvo, J.; Michelin, C.; Navarro, R.; Waldman, R.

2006-01-01

The Argentinean Nuclear Regulation Authority (ARN) verified the existence of changes in the state of some internal components of the reactor of the Atucha I Nuclear Power station that, of continuing in the time, it could take to an inconvenient degradation for the safety operation of the installation. In consequence, to the effects of preventing that reach this situation, at the end of 1999, the ARN required to the Responsible Entity for the operation of this power station the implementation of an important improvements program in the internal components of the reactor. Additionally, and based on the results of the Probabilistic Safety analysis, it was added the one mentioned improvements program the implementation of an alternative cooling system of the reactor core denominated Second Drain of Heat, due to it was determined that, for some accidental sequences, their performance would reduce considerably the probability of damage to the core. The concretion of the improvements program implied to the Responsible Entity the realization of an important quantity of engineering studies, tests and specific inspections that allowed to carry out changes on the control bars of the reactor and its guide tubes; the coolant channels; the sensors of neutron flow; and diverse components of the primary and moderator systems. On the other hand also it was implemented the system Second Drain of Heat, what represents a considerable effort to make compatible the instrumentation and control of last generation, with the instrumentation and existent control systems in the power station. Also, it was requested to be carried out an integrity of the pressure recipient for to demonstrate the existence of an acceptable margin for the difference among the acceptable limit temperatures and of ductile/fragile transition of the material for all the possible accidental scenarios during the useful life of the reactor. (Author)

Knowledge preservation of Atucha type reactor: Practical approaches and lessons learned

International Nuclear Information System (INIS)

Eppenstein, M.; Vetere, C.

2004-01-01

As Siemens, designer of the Atucha type HWRs, has transferred its nuclear activities to Framatome ANP, Argentina must undertake the knowledge preservation of this type of reactor, both if life extension is decided for the operating Atucha I NPP, and/or if ending the construction of Atucha II is decided. Another reason for undertaking a knowledge preservation program is aging and increasing retirement of personnel in the nuclear field, and the small number of young people in nuclear related disciplines at the universities. This situation motivated CNEA to implement a Knowledge Management system (KM), in order to capture and capitalize the tacit and explicit knowledge, to spread it and share it, making use of the technical and suitable tools through the organization. The strategy was based on recognizing the critical knowledge by means of a methodology incorporating the critical knowledge map technique. This map is a tool that uses the cognitive surfing in order to access to the organization heritage knowledge. Different techniques and methodologies are applied for identifying the critical knowledge domains. The result is a vigorous graphical tool with a certain formalism, able to describe knowledge in a hierarchical way in order to preserve it. It is used to analyze the criticality, and as an access portal to the knowledge patrimony, pointing out, according to each knowledge area, the people skills, publications, related documents and others. Experience obtained through the KM system development shows how training techniques are put into practice, in order not to interfere with normal plant operation, and how to initiate the KM processes in order to improve the criticity. (author)

Blackout sequence modeling for Atucha-I with MARCH3 code

International Nuclear Information System (INIS)

Baron, J.; Bastianelli, B.

1997-01-01

The modeling of a blackout sequence in Atucha I nuclear power plant is presented in this paper, as a preliminary phase for a level II probabilistic safety assessment. Such sequence is analyzed with the code MARCH3 from STCP (Source Term Code Package), based on a specific model developed for Atucha, that takes into accounts it peculiarities. The analysis includes all the severe accident phases, from the initial transient (loss of heat sink), loss of coolant through the safety valves, core uncovered, heatup, metal-water reaction, melting and relocation, heatup and failure of the pressure vessel, core-concrete interaction in the reactor cavity, heatup and failure of the containment building (multi-compartmented) due to quasi-static overpressurization. The results obtained permit to visualize the time sequence of these events, as well as provide the basis for source term studies. (author) [es

Atucha II NPP full scope simulator modelling with the thermal hydraulic code TRAC{sub R}T

Energy Technology Data Exchange (ETDEWEB)

Alonso, Pablo Rey; Ruiz, Jose Antonio; Rivero, Norberto, E-mail: prey@tecnatom.e, E-mail: jaruiz@tecnatom.e, E-mail: nrivero@tecnatom.e [Tecnatom S.A., Madrid (Spain)

2011-07-01

In February 2010 NA-SA (Nucleoelectrica Argentina S.A.) awarded Tecnatom the Atucha II full scope simulator project. NA-SA is a public company owner of the Argentinean nuclear power plants. Atucha II is due to enter in operation shortly. Atucha II NPP is a PHWR type plant cooled by the water of the Parana River and has the same design as the Atucha I unit, doubling its power capacity. Atucha II will produce 745 MWe utilizing heavy water as coolant and moderator, and natural uranium as fuel. A plant singular feature is the permanent core refueling. TRAC{sub R}T is the first real time thermal hydraulic six-equations code used in the training simulation industry for NSSS modeling. It is the result from adapting to real time the best estimate code TRACG. TRAC{sub R}T is based on first principle conservation equations for mass, energy and momentum for liquid and steam phases, with two phase flows under non homogeneous and non equilibrium conditions. At present, it has been successfully implemented in twelve full scope replica simulators in different training centers throughout the world. To ease the modeling task, TRAC{sub R}T includes a graphical pre-processing tool designed to optimize this process and alleviate the burden of entering alpha numerical data in an input file. (author)

Volatile amines treatment: Corrosion rates and Atucha I nuclear power plant experience

International Nuclear Information System (INIS)

Iglesias, Alberto M.; Jimenez Rebagliati, Raul; Raffo Calderon, Maria C.; Manzi, Ricardo

2000-01-01

Steam generators water treatment with volatile amines in place of ammonia is usual today. This option seems an acceptable alternative to the generalize use of ammonia-sodium phosphate and has advantages when copper alloys are present. There are several amines that can work as corrosion inhibitor but the most useful for plant applications are: morpholine, ethanolamine and cyclohexylamine. In this work, are present the obtained results of corrosion rates measurements by electrochemical methods. The hydrothermal conditions of our experiences were similar to that of the Atucha I nuclear power plant (CNA I). pH, conductivity and dissolved oxygen measures were correlated with corrosion rates of the CNA I materials as carbon steel and admiralty brass. The faradaic impedance spectroscopy techniques allows a more detailed interpretation of corrosion rates process. Morpholine and ammonia behavior can be evaluated under power plant operations conditions with the accumulated experience of CNA I. Results are present throughout material release and his effects over heat transfer parameters. (author)

Reliability analysis for Atucha II reactor protection system signals

International Nuclear Information System (INIS)

Roca, Jose Luis

1996-01-01

Atucha II is a 745 MW Argentine Power Nuclear Reactor constructed by ENACE SA, Nuclear Argentine Company for Electrical Power Generation and SIEMENS AG KWU, Erlangen, Germany. A preliminary modular logic analysis of RPS (Reactor Protection System) signals was performed by means of the well known Swedish professional risk and reliability software named Risk-Spectrum taking as a basis a reference signal coded as JR17ER003 which command the two moderator loops valves. From the reliability and behavior knowledge for this reference signal follows an estimation of the reliability for the other 97 RPS signals. Because the preliminary character of this analysis Main Important Measures are not performed at this stage. Reliability is by the statistic value named unavailability predicted. The scope of this analysis is restricted from the measurement elements to the RPS buffer outputs. In the present context only one redundancy is analyzed so in the Instrumentation and Control area there no CCF (Common Cause Failures) present for signals. Finally those unavailability values could be introduced in the failure domain for the posterior complete Atucha II reliability analysis which includes all mechanical and electromechanical features. Also an estimation of the spurious frequency of RPS signals defined as faulty by no trip is performed

Reliability analysis for Atucha II reactor protection system signals

International Nuclear Information System (INIS)

Roca, Jose L.

2000-01-01

Atucha II is a 745 MW Argentine power nuclear reactor constructed by Nuclear Argentine Company for Electric Power Generation S.A. (ENACE S.A.) and SIEMENS AG KWU, Erlangen, Germany. A preliminary modular logic analysis of RPS (Reactor Protection System) signals was performed by means of the well known Swedish professional risk and reliability software named Risk-Spectrum taking as a basis a reference signal coded as JR17ER003 which command the two moderator loops valves. From the reliability and behavior knowledge for this reference signal follows an estimation of the reliability for the other 97 RPS signals. Because the preliminary character of this analysis Main Important Measures are not performed at this stage. Reliability is by the statistic value named unavailability predicted. The scope of this analysis is restricted from the measurement elements to the RPS buffer outputs. In the present context only one redundancy is analyzed so in the Instrumentation and Control area there no CCF (Common Cause Failures) present for signals. Finally those unavailability values could be introduced in the failure domain for the posterior complete Atucha II reliability analysis which includes all mechanical and electromechanical features. Also an estimation of the spurious frequency of RPS signals defined as faulty by no trip is performed. (author)

ND online software development for data acquisition of replacement operations of fuel assemblies of Atucha I Nuclear power plant

International Nuclear Information System (INIS)

Calvo, Maria Dolores; Wentzeis, Luis

2012-01-01

The ND Online software was developed in order to acquire data on a real-time basis of the refueling operations at the Atucha I nuclear power plant. The fuel elements containing slightly enriched uranium dioxide are located in the nuclear reactor core inside the cooling channels. The refueling operations are made periodically while the reactor is operating at full power. The acquired signals during the refueling operations are: pressure, force and position of the fuel element. In order to improve the safety and availability of the installation, monitoring of the refueling operations is important for the early detection of anomalies related to the fuel element itself, the cooling channels or the refueling machine (author)

Development of an acoustic emission equipment for valves of the Nuclear Power Station Atucha 1

International Nuclear Information System (INIS)

Giaccheta, R.; Lopez Pumarega, I.; Straus, A.; Ruzzante, J.; Herzovich, P.

1994-01-01

A four channel Acoustic Emission was developed by the Acoustic Emission Group, INEND Department, of the Atomic Energy Commission of Argentina, for the detection of leaks in valves of the pressurized air system: ''Sistema de desconexion de emergencias por acido deuteroborico''. Basically, the system consists of four piezoelectric transducers with their corresponding preamplifiers coupled to the piping close to the valves. The following stages: amplifiers, threshold levels, channel identifications and visual alarm system are gathered in a box. The system was installed in the controlled zone of the Nuclear Power Stations Atucha I. It was calibrated and works on line. The values shown on the display are registered daily in order to separate the normal values from the leak ones. (author). 4 refs, 9 figs

Experience gathered from the transport of a fuel element prototype of the CNA-II (Atucha-II nuclear power plant) type

International Nuclear Information System (INIS)

Pastorini, A.; Belinco, C.G.; El Bis, E.D.; Sacchi, M.A.; Mayans, C.O.; Martin Ghiselli, A.; Marcora, G.R.

1990-01-01

This work describes the needs to materialize the transport of a fuel element prototype of the CNA-II (Atucha-II nuclear power plant) type, under special conditions, from the Fabrication Pilot Plant sited at the Constituyentes Atomic Center and the Ezeiza Atomic Center, for its subsequent analysis at the High Pressure Experimental Loop. The special conditions under which the transport has been made responded to the fact that the prototype presents a fragile adjustment between rods and separators, necessary to be preserved. (Author) [es

Micrometeorological study of the Atucha Nuclear Power Plant site

International Nuclear Information System (INIS)

Berri, G.J.; Robbio, C.A.

1986-01-01

The evaluation of time meteorological data obtained at the micrometeorological station of the Atucha Power Plant during 1979, is presented. Special attention is given to the transport and atmospheric dispersion characteristics through the evaluation of the mean and hourly wind behaviour and the stability classes. Furthermore, it is obtained an estimation of the dispersion factors both for short-term and long-term releases using Gaussians models. As these factors are representative of mean conditions, they should not be applied to the analysis of isolated situations. Finally it is emphasized that, although the results were obtained by means of 1979 data, significative differences are not expected for other years. (M.E.L.) [es

Assessment of theoretical and experimental results in the calculation of atmospheric dilution factors in the Atucha I nuclear power plant

International Nuclear Information System (INIS)

Quintana, E.E.; Tossi, M.H.; Telleria, D.M.

1990-01-01

Collective doses produced during the normal working of the Atucha I Nuclear Power Plant are calculated using annual atmospheric factors. This work studies the behaviour of the dilution factors in different periods of the year in order to fit the calculated dose model applying factors from seasonal, monthly or weekly periods. The Radiation Protection Group of the C.N.E.A. have carried out continuous environmental monitoring in the surroundings of the Atucha I Nuclear Power Plant. These studies include the measurement of air tritium concentration, radionuclide that is found principally as tritiated water vapour. This isotope, normally released by the nuclear power plant was used as a tracer to assess the atmospheric dilution factors. Factors were calculated by two methods: an experimental one, based on environmental measurements of the tritium concentration in the surroundings of the nuclear power plant and another one by applying a theoretical model based on information from the micrometeorological tower located in the mentioned place. To carry out the environmental monitoring, four monitoring stations in the surroundings of the power plant were chosen. Three of them are approximately one kilometer from the plant and the fourth is 7.5 km away, near the city of Lima. To condense and collect the atmospheric water vapour, an overcooling system was used. The measurement was performed by liquid scintillation counting, previous alkaline electrolytical enrichment of the samples. The theoretical model uses hourly values of direction and wind intensity, as well as the atmospheric dispersive properties. Values obtained during the period 1976 to 1988 allowed, applying statistical tests, to validate the theoretical model and to observe seasonal variation of the dilution factors throughout the same year and between different years. Finally, results and graphics are presented showing that the behaviour of the dilution factors in different periods of the year. It is recommended to

Utilization of noise analysis technique for mechanical vibrations estimation in the ATUCHA{sub 1} and Embalse Argentine NPP; Uso de la tecnica de analisis de ruido para la estimacion de vibraciones mecanicas en las centrales nucleares argentinas Atucha I y Embalse

Energy Technology Data Exchange (ETDEWEB)

Lescano, V.H.; Wentzeis, L.M. [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Centro Atomico Constituyentes; Guevara, M.; Moreno, C. [Nucleoelectrica Argentina S.A., Cordoba (Argentina). Central Nuclear Embalse; Pineyro, J. [Nucleoelectrica Argentina S.A., Buenos Aires (Argentina). Central Nuclear Atucha I

1996-07-01

In Argentine, comprehensive noise measurements have been performed with the reactor instrumentation of the PHWR power plant Atucha I and Embalse. The Embalse reactor is a CANDU-600 (600 Mwe) type pressurized heavy water reactor. It's a heavy water moderator and heavy water cooled natural uranium fueled pressure tube system. Signal of vanadium and platinum type in core-self power neutron detectors of ex-core ion chambers and of a moderator pressure sensor have been recorded and analysed. The vibration of reactor internals as vertical and horizontal in-core neutron flux detectors units and the coolant channels systems, consisting of calandria and pressure tubes with fuel bundles, have been identified and monitored during normal reactor operation. Atucha I, is a PHWR reactor natural uranium fueled, and heavy water moderated and cooled. Neutron noise techniques using of ex-core ionization chambers and in-core Vanadium SPND's were implemented, among others, in order to produce early detection of anomalous vibrations in the reactor internals. Noise analysis was successfully performed to identify normal and peculiar vibrations in particular reactor internals. (author)

Atucha I nuclear power plant: repair works in QK02W01 moderator system heat exchanger

International Nuclear Information System (INIS)

Olivieri, Luis E.; Zanni, Pablo A.

2000-01-01

Atucha I nuclear power plant moderator system operates with highly radioactive heavy water, a pressure of 115 Bar and temperatures of about 200 C degrees. In March 2000, an increasing leakage of heavy water to the conventional thermal circuit was detected, conducting the plant to a shut down. The development of a number of actions and measures were taken, in order to plug this leakage. The leakage was found in a heat exchanger, which is located in a place of difficult access, with a high radiological yield and which, according to design, it was not considered to be mechanically repaired. It is a U bend tubes heat exchanger, weighting about 20 tons, and with a heavy water flow of 800 tons/h on the primary circuit, and 950 tons/h of ordinary water on the secondary side. Foreseeing this event, it had been designed and constructed special equipment and procedures, by means of a contract, with the Company INVAP SA. Repair works were carried out within a period of eighty-six (86) days, from which, forty five days were used to repair the component itself. A considerable amount of time was used to prepare simulators and the training of personnel. Due to the high radiological yield and the strict care of radiological standards, it was necessary the participation of 300 persons, integrating a collective dose of 4,86 Sv-m. It was necessary the construction of platforms and auxiliary stairs so as to make the work place accessible, as well as lifting and movement devices for heavy components, since this area does not have such kind of facilities. Welding and cutting machines remote controlled as well as manipulators which operated in front of the exchanger tube sheet were used. The aim was the reduction of dose values as much as possible. Special shielding were developed and in some cases it was necessary the adoption of drastic measures such as the cutting of bolts or pipes. The failure was detected and the tube was plugged. Also were plugged those tubes with wall thickness

The pressure and leak tests in Atucha II

International Nuclear Information System (INIS)

Anon.

1991-01-01

This work deals with the pressure and leak tests of the containment sphere in the Atucha II Nuclear Power Plant's reactor building. This sphere is a metallic container, made in highly resistant steel plate, that is, built for providing the plant with a biological and structural barrier, which -in turn- provides safety and environmental protection. The applicable rules for these tests establish that the containment erection must be complete and in equivalent conditions to those that will prevail during the NPP operation. Particularly, pressure tests were carried out for assessing the structural condition of the sphere, while the leak test is aimed at the detection of tentative leaks [es

Economical benefits for the use of slightly enriched fuel elements at the Atucha-I nuclear power plant

International Nuclear Information System (INIS)

Sidelnik, J.I.; Sosa, M.A.

1987-01-01

The fuel represents a very important factor in the operative cost of the Atucha I nuclear power plant. This cost is drastically reduced with the use of fuel elements of slightly enriched uranium. The annual saving is analyzed with actual values for fuel elements with an enrichment of 0.85% by weight of U-235. With the reactor core in equilibrium state the annual saving achieved is approximately 7.5-10 u$s. According to the present irradiation plan, the benefit for the transition period is studied. An analysis of the sensitivity to differential increments in factors determining the cost of fuel elements or to changes in manufacturing losses is also performed, calculating its effect on the waste, the storage of irradiated elements and the amount of UO 2 required. (Author)

A Coupled Calculation Suite for Atucha II Operational Transients Analysis

International Nuclear Information System (INIS)

Mazzantini, O.; Schivo, M.; Cesare, J.D.; Garbero, R.; Rivero, M.; Theler, G.

2011-01-01

While more than a decade ago reactor and thermal hydraulic calculations were tedious and often needed a lot of approximations and simplifications that forced the designers to take a very conservative approach, computational resources available nowadays allow engineers to cope with increasingly complex problems in a reasonable time. The use of best-estimate calculations provides tools to justify convenient engineering margins, reduces costs, and maximises economic benefits. In this direction, a suite of coupled best-estimate specific calculation codes was developed to analyse the behaviour of the Atucha II nuclear power plant in Argentina. The developed tool includes three-dimensional spatial neutron kinetics, a channel-level model of the core thermal hydraulics with subcooled boiling correlations, a one-dimensional model of the primary and secondary circuits including pumps, steam generators, heat exchangers, and the turbine with all their associated control loops, and a complete simulation of the reactor control, limitation, and protection system working in closed-loop conditions as a faithful representation of the real power plant. In the present paper, a description of the coupling scheme between the codes involved is given, and some examples of their application to Atucha II are shown

GIS Application in Atucha I Nuclear Power Plant Exercise Argentina, 2007

International Nuclear Information System (INIS)

Sadaniowski, I.V.; Telleria, D.M.; Jordan, O.D.; Boutet, L.I.; Kunst, J.J.; Bruno, H.A.; Hernandez, D.G.; Rodriguez, M.; Cateriano, M.A.; Rey, H.L.

2011-01-01

Geographic Information Systems (GIS) are tools applied to assist in the assessment and solution of many geographical related issues. Recently, their applications have been extended to the areas of disasters and environmental emergencies. GIS not only could be used as a diagnostic tool. Combined with adequate information and other tools capable to predict the transfer of pollutants in the environment and the associated impacts to the public, GIS could be used to support emergency planning and response. The Nuclear Regulatory Authority (NRA) of Argentina has incorporated in 2003 the GIS technology like an innovative resource for its preparation and response activities in emergencies. For this, the NRA acquired the necessary technology (hardware and software) and the technical specialist who were joined to expert's team in the nuclear and radiological emergencies field. The GIS stays operative as support tool in the Emergencies Control Center of NRA. In this paper, the use of GIS as a tool for analysis and advice is presented. The GIS is being used for preparation and development of nuclear emergencies trials and exercises, carried out on-site and off-site at the Nuclear Power Plant Atucha I Buenos Aires, Argentina, in cooperation with civil defense, national and state security and army forces and intensive public involvement. The databases were conformed with information from different sources, including the result of interviews to different actors, as well as other local and national government agencies and forces. Also, educational institutions, local medical centers, etc., were consulted. The information was enriched with outings to field in the surroundings of nuclear power plant. The scope and the detail of the information for this exercise covers 30 kilometers surroundings the nuclear power plant, with a range of significantly different geographical and population conditions. When loading the information in the GIS, a classification scheme is applied and

GIS application in Atucha I nuclear power plant exercise Argentina, 2007

International Nuclear Information System (INIS)

Sadaniowski, Ivana; Jordan, Osvaldo; Boutet, Luis; Kunst, Juan; Bruno, Hector; Hernandez, Daniel; Rodriguez, Monica; Cateriano, Miguel; Rey, Hugo; Telleria, Diego

2008-01-01

Full text: Geographic Information Systems (GIS) are tools applied to assist in the assessment and solution of many geographical related issues. Recently, their applications have been extended to the areas of disasters and environmental emergencies. GIS not only could be used as a diagnostic tool. Combined with adequate information and other tools capable to predict the transfer of pollutants in the environment and the associated impacts to the public, GIS could be used to support emergency planning and response. The Nuclear Regulatory Authority (NRA) of Argentina has incorporated in 2003 the GIS technology like an innovative resource for its preparation and response activities in emergencies. For this, the NRA acquired the necessary technology (hardware and software) and the technical specialist who were joined to expert's team in the nuclear and radiological emergencies field. The GIS stays operative as support tool in the Emergencies Control Center of NRA. In this paper, the use of GIS as a tool for analysis and advice is presented. The GIS is being used for preparation and development of nuclear emergencies trials and exercises, carried out on-site and off-site at the Nuclear Power Plant Atucha I Buenos Aires, Argentina, in cooperation with civil defense, national and state security and army forces and intensive public involvement. The databases were conformed with information from different sources, including the result of interviews to different actors, as well as other local and national government agencies and forces. Also, educational institutions, local medical centers, etc., were consulted. The information was enriched with outings to field in the surroundings of nuclear power plant. The scope and the detail of the information for this exercise covers 30 kilometers surroundings the nuclear power plant, with a range of significantly different geographical and population conditions. When loading the information in the GIS, a classification scheme is applied

Irradiation program of slightly enriched fuel elements at the Atucha I nuclear power plant

International Nuclear Information System (INIS)

Casario, J.A.; Cesario, R.H.; Perez, R.A.; Sidelnik, J.I.

1987-01-01

An irradiation program of fuel elements with slightly enriched uranium is implemented, tending to the homogenization of core at Atucha I nuclear power plant. The main benefits of the enrichment program are: a) to extend the average discharge burnup of fuel elements, reducing the number of elements used to generate the same amount of energy. This implies a smaller annual consumption of elements and consequently the reduction of transport and replacement operations and of the storage pool systems as well as that of radioactive wastes; b) the saving of uranium and structural materials (Zircaloy and others). In the initial stage of program an homogeneous core enrichment of 0.85% by weight of U-235 is anticipated. The average discharge burnup of fuel elements, as estimated by previous studies, is approximately 11.6 MW d/kg U. The annual consumption of fuel elements is reduced from 396 of natural uranium to 205, with a load factor of 0.85. It is intended to reach the next equilibrium steps with an enrichment of 1.00 and 1.20% in U-235. (Author)

Proposal of modification of the Atucha I nuclear power plant's emergency power supply system

International Nuclear Information System (INIS)

Palacio, Pedro; Dabove, Mario

1989-01-01

The emergency power supply system of Atucha I N.P.P. consists of three 50% diesel generators. During the transient from normal power supply to emergency power supply (approximately 15 seconds) an hydraulic generator takes care of the emergency system. By this way, the emergency busbars constitute themselves an interruption free system. The two emergency busbars work normally coupled. This proposal consists of the following modifications: 1) Add a new diesel generator in order to allow the operation with two diesel generators per busbar. 2) To work with the two emergency busbars not coupled as normal operation mode. 3) To eliminate the hydraulic generator from the emergency power supply system, in order to simplify the operation and to reduce the failure possibility. Without the hydraulic turbine generator, the emergency busbars loose the interruption free condition. For this reason, for the loads that are not able for this mode of operation and are connected to the emergency power supply system, two additional low-voltage interruption free busbars are necessary. Finally, this proposal is compared with the Atucha II N.P.P. emergency power supply system. (Author)

C A R A fuel element for Atucha nuclear power plants and development plan

International Nuclear Information System (INIS)

Brasnarof, D. O; Marino, A. C; Bianchi, D; Giorgis M A; Orlando, O; Munoz, C; Taboada, H; Florido, P. C

2006-01-01

This paper presents the current state and the development plan of the C A R A fuel element.Main activities were carried out towards to welding of the end plates of the C A R A fuel element by a new process, and the assembling and hanging of the C A R A fuel element in its Atucha configuration, by using an external basket [es

Cost estimation of interim dry storage for Atucha I NPP

International Nuclear Information System (INIS)

Bergallo, Juan E.; Fuenzalida Troyano, Carlos S.

2007-01-01

A joint effort between NASA and CNEA has been performed in order to evaluate and fix the strategy of interim spent fuel storage for Atucha I nuclear power plant. In this work the cost estimation on the proposed system was performed in order to fix the parameter and design criteria for the next engineering step. The main results achieved show that both alternatives are all in the same range of costs per unit of mass to be stored, the impact on electricity cost is less than 1 US mills/KWh and the scaling factor achieved is 0.85. (author) [es

Design, test and start up of a cleaning system for the moderator tank bottom of Atucha I Nuclear Power Plant

International Nuclear Information System (INIS)

Duca, J.; Gerber, O.; Ibero, M.; Riga, N.

1989-01-01

In order to perform the cleaning of the moderator tank bottom, during the repair of the Atucha I nuclear power plant (CNA I) failure, the Empresa Nuclear Argentina de Centrales Electricas (ENACE S.A.) designed a system with the following requirements (asked by CNA I): a) To aspirate and retain free solid particles, uranium dioxide pellets and coolant channels isolations (foils) of minor size settled at the moderator tank bottom, being the reactor at middle loop state. b) To allow a radially cleaning up to 1.4 m from the extracted channel. c) To design a lay-out attaining the ALARA dose exposure. The designed system basically consists in: a) Flexible intake for suction: allows the movement inside the moderator tank and provides the adequate speed to raise the particles. b) Filter: retains the aspirated particles, pellets and foils. Its capacity is 1.8 dm 3 and the minimum size of retained particles is 200 m. The ALARA dose exposure concept is attained due to that the filter is located inside the moderator tank. c) Filtering column: contains the filter and allows the entrance of the extraction and exchange tool (for the flexible intake and filter). d) Suction hose: connects the filtering column with the pump. Its flexibility allows its use in any channel maintaining the same positions of the discharge pump and the return piping. e) Discharge pump: it is a canned centrifugal pump with low-low net positive suction head. f) Return piping: discharges the filtered water into the moderator tank. The system fulfilled satisfactorily all requirements during its operation. (Author)

Theoretical-experimental assessment of the variables affecting fretting of Atucha I nuclear power plant utility steam generators tubes

International Nuclear Information System (INIS)

Kulichevsky, Raul M.

1995-01-01

Fretting wear of Steam Generator tubes caused by flow induced vibrations generates uncertainty on their integrity. The knowledge of the controlling variables of the wear process may give a criterion to evaluate the tubes residual life. Information on vibratory response and dynamic interaction between tubes and their supports are prerequisites for understanding the relationship between fretting wear and tube vibration. Experimental results of the vibratory response of an Atucha-I nuclear power plant type U-tube, the influence of tube/support clearance on this response and a study of tube/support dynamic interaction, which allow the verification of a finite element model of this type of tubes, are presented in this work. Also wear results for the Incoloy 800/DIN 1.4550 austenitic stainless steel pair of materials and a first evaluation of the wear constant of this pair are presented. (author)

The world's reactors No. 82: Atucha II

International Nuclear Information System (INIS)

Anon.

1982-01-01

Detailed information on Atucha II, a 745 MWe pressure-vessel PHWR, is presented in the form of a wall chart. Plant specifications and full colour cutaway drawings of the power station are included. (U.K.)

Determination of activity by gamma spectrometry of radionuclides present in drums of residues generated in nuclear centrals; Determinacion de actividad por espectrometria gamma de radionucleidos presentes en tambores de residuos generados en centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Aguiar, J.C.; Fernandez, J. [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250, Ciudad Autonoma de Buenos Aires (Argentina)]. e-mail: jaguiar@cae.arn.gov.ar

2006-07-01

The generation of radioactive residuals in nuclear centrals as CNA I (Atucha I Nuclear Central) and CNE (Embalse Nuclear Central) makes that the measurement of those radionuclides has been a previous stage to the waste management. A method used in those nuclear centrals it is the gamma spectrometry with HPGe detectors, previous to the immobilization of the residual in a cemented matrix, with this the contact with the external agents and its possible dispersion to the atmosphere in the short term is avoided. The ARN (Nuclear Regulatory Authority) of Argentina it carries out periodically intercomparisons and evaluations of the measurement and procedures systems used in the nuclear power stations for the correct measurement and determination of activity of radioactive residuals by gamma spectrometry. In this work an independent method of measurement is exposed to the nuclear power stations. To determine the activity of the residuals by gamma spectrometry deposited in drums, it is required of the precise knowledge of the efficiency curve for such geometry and matrix. Due to the RNA doesn't have a pattern of these characteristics, a mathematical model has been used to obtain this efficiency curve. For it, it is necessary to determine previously: 1) the geometric efficiency or solid angle sustained by the source-detector system (drum-detector) applying a mathematical model described in this work. 2) To estimate the auto-attenuation factor that present the photons in the cemented matrix, these calculations are carried out with a simple equation and its are verified with the Micro Shield 6.10 program. The container commonly used by these nuclear power stations its are drums for 220 liters constructed with SAE 1010 steel and with a thickness of 0.127 cm, with an approximate weight 7.73 Kg., internal diameter of 57.1 cm, and height: 87 cm. The results obtained until the moment register a discrepancy from 5 to 10% with relationship to the measurements carried out by the

Simulation program for the dynamic behaviour of the primary system and moderators's circuit of the Atucha I Nuclear Power Plant

International Nuclear Information System (INIS)

Castano, Jorge; Gvirtzman, H.A.

1981-01-01

A model of digital computation is presented to simulate the primary system of heat transportation, moderator system and the associated systems for adjustment, regulation and control in the PHWR reactor at the Atucha-1 nuclear power plant. The model discusses in a concentrated way the different components and allows the study of the dynamical behaviour of the power plant facing disturbances with respect to a state of stationary regime. General considerations and description of the model are made. The method is described showing flow sheets, graphs and developing basic formulas, simulating a primary system, moderator and secondary system of the steam generator and the main system of regulation. Also an analysis of the results is made, for the case of disturbances which reduce or increase the power of the reactor by 10%. (V.B.) [es

Neutronic calculations for the reactor pressure vessel of Atucha I nuclear power plant

International Nuclear Information System (INIS)

Lerner, Ana M.; Madariaga, Marcelo R.

1999-01-01

In 1974 a surveillance program for the Atucha I nuclear power plant pressure vessel was initiated which included the construction of different types of specimens, distributed in 30 irradiation capsules located under the core at the lower part of some of the fuel channels. The capsules containing the irradiated specimens were withdrawn in two stages; the first set (SET 1) of 15 specimens in 1980 and the second one (SET 2) of the remaining 15, in 1987. Both fracture mechanic tests and dosimetry analysis were carried out by the designer (KWU) for SET1 and by the owner National Atomic Energy Commission (CNEA) for SET2. The calculations performed in the case of SET1 showed that there was a significant spectrum difference between the position where the specimens had been and the reactor pressure vessel (RPV) - inner surface (IS). It was established that the ratio of thermal flux (E 1 MeV) varied, approximately, from 1000 to 10 from the irradiation position to the RPV- IS. The purpose of this report is to show the calculations recently performed at the Nuclear Regulatory Authority, with particular emphasis on the difference in the results generated by the modification to sightly enriched fuel. A simplified 1-D calculations show that there is a slight increase (4% approximately) in the flux along the whole energy range. As it has already been mentioned, this is due, more than to the isotopic composition of the new fuel, to the difference in power density spatial distribution, which is a consequence of a different fuel management, necessary to preserve operational limits below their maximum allowed values with the same total thermal power generated. More detailed calculations are nevertheless foreseen in order to verify these first results. (author)

Regulatory actions towards dose reduction at Atucha 1 NPS

International Nuclear Information System (INIS)

Spano, F.; Curti, A.R.; Telleria, D.M.; Rudelli, M.D.

1998-01-01

Atucha 1, a nuclear power plant designed in the late sixties, is in commercial operation since June 1974. In some internal components such as the coolant channels, the station has Stellite-6, a high cobalt content alloy (up to 60%) for hard-facing application. The erosion and corrosion processes on the surfaces of the piping components of the primary coolant and moderator systems generate a varied type of particles oxides called 'crud'. The crud and cobalt 60 produced by neutron activation of cobalt are transferred by the water along the circuit of the coolant and moderator systems, producing deposits on internal surfaces. The cobalt deposits are dominant in radiation fields at working locations. For years, the Authority allowed a considerable number of station workers incurring doses near the limit since that installation had been built previously to introduction of the optimisation concept by ICRP publication 26. The recommendations included in ICRP publication 60 made more than difficult the radiological situation at the Atucha 1. For the facility, to comply with the new limit established by the Authority in January 1995, meant to carry out a substantial modification of the radiological conditions, specially the radiation fields due to cobalt 60. Some options to reduce individual and collective doses were analysed by the Authority. To carry out the evaluation of the deposit mechanisms and the real activity level of cobalt 60, a model of compartments connected by means of constant transfer coefficients was designed. It was concluded that there was a necessity to the change of coolant channels by new ones free of cobalt. It has been shown experimentally that radiation fields and occupational doses were reduced, due to the replacement programme carried out by the utility, in a similar way to the model predictions. At present after more than three years from the beginning of the application of the new limits, and after carrying out partially the tasks for the

Thermoelastic analysis for the fuel claddings of the nuclear power reactor at Atucha in the skid's region

International Nuclear Information System (INIS)

Sanchez Sarmiento, Gustavo; Basombrio, F.G.

1979-01-01

For the fuel elements of the Nuclear Power Reactor at Atucha, a two-dimensional thermoelastic analysis has been made in the region of the skids of the fuel cladding, when the gap between them and the fuel rod separator's support becomes zero. In such a case the latter forces exert on the skids an elastic reaction opposite to the cladding's expansion. The internal pressure reaching the yield stress for the cladding material has been calculated, as a function of the initial gap; for several possible fuel rod locations within the separator; for the actual dimensions and also for reduced thickness of the cladding; with a given external pressure and, with a known temperature spatial distribution. The latter has been calculated by solving the heat conduction equation along the fuel element for a certain power level in the reactor. The calculations are made with two FORTRAN IV computer codes developed at C.A.B., using the finite-element method: the NOLICUARM, to solve the nonlinear quasi-harmonic equation, and the ELASTEF 3, for the solution of thermoelastic problems with plane symmetry. (author) [es

Determination of activity by gamma spectrometry of radionuclides present in drums of residues generated in nuclear centrals

International Nuclear Information System (INIS)

Aguiar, J.C.; Fernandez, J.

2006-01-01

The generation of radioactive residuals in nuclear centrals as CNA I (Atucha I Nuclear Central) and CNE (Embalse Nuclear Central) makes that the measurement of those radionuclides has been a previous stage to the waste management. A method used in those nuclear centrals it is the gamma spectrometry with HPGe detectors, previous to the immobilization of the residual in a cemented matrix, with this the contact with the external agents and its possible dispersion to the atmosphere in the short term is avoided. The ARN (Nuclear Regulatory Authority) of Argentina it carries out periodically intercomparisons and evaluations of the measurement and procedures systems used in the nuclear power stations for the correct measurement and determination of activity of radioactive residuals by gamma spectrometry. In this work an independent method of measurement is exposed to the nuclear power stations. To determine the activity of the residuals by gamma spectrometry deposited in drums, it is required of the precise knowledge of the efficiency curve for such geometry and matrix. Due to the RNA doesn't have a pattern of these characteristics, a mathematical model has been used to obtain this efficiency curve. For it, it is necessary to determine previously: 1) the geometric efficiency or solid angle sustained by the source-detector system (drum-detector) applying a mathematical model described in this work. 2) To estimate the auto-attenuation factor that present the photons in the cemented matrix, these calculations are carried out with a simple equation and its are verified with the Micro Shield 6.10 program. The container commonly used by these nuclear power stations its are drums for 220 liters constructed with SAE 1010 steel and with a thickness of 0.127 cm, with an approximate weight 7.73 Kg., internal diameter of 57.1 cm, and height: 87 cm. The results obtained until the moment register a discrepancy from 5 to 10% with relationship to the measurements carried out by the

Proposal of Ex-Vessel dosimetry for pressure vessel Atucha II

International Nuclear Information System (INIS)

Chiaraviglio, N.; Bazzana, S.

2013-01-01

Nuclear reactor dosimetry has the purpose of guarantee that changes in material mechanical properties of critical materials do not compromise the reactor safety. In PWR in which the top of the reactor vessel is open once a year, is possible to use Charpy specimens to measure the change in mechanical properties. Atucha II nuclear power plant is a reactor with on-line refueling so there is no access to the inside of the pressure vessel. Because of this, ex-vessel dosimetry must be performed and mechanical properties changes must be inferred from radiation damage estimations. This damage can be calculated using displacement per atom cross sections and a transport code such as MCNP. To increase results reliability it is proposed to make a neutron spectrum unfolding using activation dosimeters irradiated during one operation cycle of the power plant. In this work we present a dosimetry proposal for such end, made in base of unfolding procedures and experimental background. (author) [es

Xenon oscillation in a large PHWR core (Atucha II type): TRISIC code applicability

International Nuclear Information System (INIS)

Solanilla, Roberto

2000-01-01

A three dimensional nuclear reactor simulation code (TRISIC) was developed many years ago to design a PHWR (pressurizer heavy water reactors - Atucha type) based in the 'source-sink model' (heterogeneous theory). The limited processor computational performance available at that time was the constraint of the code when a detailed reactor description was necessary. A modern PC (pentium) code version with a full reactor core representation (461 fuel channels) including diagonal control rod banks and flux-reading detectors with theirs tube guide was used in the present paper for simulation of the Xenon transient when a local asymmetric perturbation was produced in a large core (Atucha II type). The results obtained and the computer time required for the 70 hour's simulation with an adequate time step, established the potential of the code to deal with this kind of transients. The paper shows that the method of TRISIC allows to detect and control azimuthal, radial and axial oscillation. This code is a proper way to elaborate a program of control rods movement from the flux reading detectors to damp the oscillation. TRISIC could also be a accurate tool to supervise the full core flux distribution in real time during the operation of the reactor. (author)

Hydrogeological modelling of the eastern region of Areco river locally detailed on Atucha I and II nuclear power plants area

International Nuclear Information System (INIS)

Grattone, Natalia I.; Fuentes, Nestor O.

2009-01-01

Water flow behaviour of Pampeano aquifer was modeled using Visual Mod-flow software Package 2.8.1 with the assumption of a free aquifer, within the region of the Areco river and extending to the rivers of 'Canada Honda' and 'de la Cruz'. Steady state regime was simulated and grid refinement allows obtaining locally detailed calculation in the area of Atucha I and II Nuclear power plants, in order to compute unsteady situations as the consequence of water flow variations from and to the aquifer, enabling the model to study the movement of possible contaminant particles in the hydrogeologic system. In this work the effects of rivers action, the recharge conditions and the flow lines are analyzed, taking always into account the range of reliability of obtained results, considering the incidence of uncertainties introduced by data input system, the estimates and interpolation of parameters used. (author)

Benchmark of Atucha-2 PHWR RELAP5-3D control rod model by Monte Carlo MCNP5 core calculation

Energy Technology Data Exchange (ETDEWEB)

Pecchia, M.; D' Auria, F. [San Piero A Grado Nuclear Research Group GRNSPG, Univ. of Pisa, via Diotisalvi, 2, 56122 - Pisa (Italy); Mazzantini, O. [Nucleo-electrica Argentina Societad Anonima NA-SA, Buenos Aires (Argentina)

2012-07-01

Atucha-2 is a Siemens-designed PHWR reactor under construction in the Republic of Argentina. Its geometrical complexity and peculiarities require the adoption of advanced Monte Carlo codes for performing realistic neutronic simulations. Therefore core models of Atucha-2 PHWR were developed using MCNP5. In this work a methodology was set up to collect the flux in the hexagonal mesh by which the Atucha-2 core is represented. The scope of this activity is to evaluate the effect of obliquely inserted control rod on neutron flux in order to validate the RELAP5-3D{sup C}/NESTLE three dimensional neutron kinetic coupled thermal-hydraulic model, applied by GRNSPG/UNIPI for performing selected transients of Chapter 15 FSAR of Atucha-2. (authors)

LDC nuclear power: Argentina

International Nuclear Information System (INIS)

Tweedale, D.L.

1982-01-01

Argentina's 31-year-old nuclear research and power program makes it a Third World leader and the preeminent Latin American country. Easily accessible uranium fuels the heavy water reactor, Atucha I, which provides 10% of the country's electric power. Atucha II and III are under construction. Several domestic and international factors combined to make Argentina's program succeed, but achieving fuel-cycle independence and the capacity to divert fissionable material to military uses is a cause for some concern. 60 references

Regulatory activities related with the modification of the frequency of the programmed stoppings of the Argentine nuclear centrals; Actividades regulatorias relacionadas con la modficacion de la frecuencia de las paradas programadas de las centrales nucleares argentinas

Energy Technology Data Exchange (ETDEWEB)

Marino, E.; Calvo, J.; Waldman, R.; Navarro, R

2006-07-01

The mandatory character documentation of the Argentinean nuclear power stations in Embalse and Atucha I, required the realization of a programmed stoppings every twelve months to execute that settled down in the maintenance and surveillance programs for each installation. Nucleoelectrica Argentina S.A., in it character of Responsible Entity of the operation of these power stations, requested to the Argentinean Nuclear Regulatory Authority, in 2003 and 2005 respectively, the authorization to change the period of the repetitive tests and of the preventive maintenance of the systems related with the safety, to extend them from twelve to eighteen months. The mentioned applications were founded in economic aspects and in inclining to a decrease in the doses of the workers that perform in the activities that are carried out in the programmed stops. The adopted position by the Nuclear Regulatory Authority to decide on these applications was based on the result of diverse evaluations that included the use of the Probabilistic Analysis of Safety specific of each power station, the operative experience resultant of the execution of the preventive maintenance program, and of the results of the repetitive tests and of the inspections in service. The regulatory decisions were different in each case. Indeed, the Embalse nuclear power station was authorized by the Regulatory Authority to modify from twelve to eighteen months the period among the realization of the repetitive tests and of the preventive maintenance, conditioned to the execution of some specific regulatory requirements. On the other hand, the Atucha I nuclear power station was not authorized to modify this period. In this presentation that is detailed the acted by the Nuclear Regulatory Authority in both cases, the used analysis tools, and the foundation of the adopted decisions. (Author)

37-Active rods fuel element for Atucha 1 nuclear power plant. Effects of this change in design over the neutronic behavior, decay power and radioactive inventory

International Nuclear Information System (INIS)

Villar, Javier E.

1999-01-01

The influence of the use of 37-rods fuel element on the behavior of the Atucha 1 nuclear power plant homogeneous core with slightly enriched fuel to 0.85 w % were studied through representative parameters such as average discharge burnup, channel powers, reactivity coefficients, kinetic parameters, radioactive inventory and decay power. In general, the values of mentioned parameters are similar to those corresponding to a core with the 36-rods fuel element actually in use, although it must be emphasized a decrease both in linear power and, in minor degree, in the efficiency of shut-off and control rods and a slight increase in the discharge burnup. The fuel management strategy developed for a core with 36-rods elements can be maintained. (author)

Reflections on the development of local suppliers for the Argentine nuclear industry

International Nuclear Information System (INIS)

Quilici, Domingo F.

2008-01-01

Argentina has given recently a new start to its nuclear power activities. Looking for background and experiences that can be useful under the new reality, the paper is a survey of the past development of local suppliers for the national nuclear industry. Based on the intention to answer the questions: Why so early it was decided to build a nuclear power plant? Why it was decided to buy it under a turnkey basis rather than developing an indigenous design? and what was the meaning of the 'opening of the technology package' at that time?, the paper describes the actions that led to the purchase of the Atucha I, Embalse and Atucha II nuclear power plants and how these decisions were implemented in order to maximize local participation and the technology transfer. It also analyzes the influence of the Argentine Nuclear Plan of the late seventies on the development of endogenous technology and describes the facts that helped to preserve until now the technological nuclear capabilities of the country in spite of the stopping of the Atucha II construction, and to create positive expectations regarding the revival of the local industry as a supplier of nuclear goods and services. (author) [es

Steam generator materials and secondary side water chemistry in nuclear power stations

International Nuclear Information System (INIS)

Rudelli, M.D.

1979-04-01

The main purpose of this work is to summarize the European and North American experiences regarding the materials used for the construction of the steam generators and their relative corrosion resistance considering the water chemestry control method. Reasons underlying decision for the adoption of Incoloy 800 as the material for the secondary steam generator system for Atucha I Nuclear Power Plant (Atucha Reactor) and Embalse de Rio III Nuclear Power Plant (Cordoba Reactor) are pointed out. Backup information taken into consideration for the decision of utilizing the All Volatil Treatment for the water chemistry control of the Cordoba Reactor is detailed. Also all the reasonswhich justify to continue with the congruent fosfatic method for the Atucha Reactor are analyzed. Some investigation objectives which would eventually permit the revision of the decisions taken on these subjects are proposed. (E.A.C.) [es

Regulatory activities related with the modification of the frequency of the programmed stoppings of the Argentine nuclear centrals

International Nuclear Information System (INIS)

Marino, E.; Calvo, J.; Waldman, R.; Navarro, R.

2006-01-01

The mandatory character documentation of the Argentinean nuclear power stations in Embalse and Atucha I, required the realization of a programmed stoppings every twelve months to execute that settled down in the maintenance and surveillance programs for each installation. Nucleoelectrica Argentina S.A., in it character of Responsible Entity of the operation of these power stations, requested to the Argentinean Nuclear Regulatory Authority, in 2003 and 2005 respectively, the authorization to change the period of the repetitive tests and of the preventive maintenance of the systems related with the safety, to extend them from twelve to eighteen months. The mentioned applications were founded in economic aspects and in inclining to a decrease in the doses of the workers that perform in the activities that are carried out in the programmed stops. The adopted position by the Nuclear Regulatory Authority to decide on these applications was based on the result of diverse evaluations that included the use of the Probabilistic Analysis of Safety specific of each power station, the operative experience resultant of the execution of the preventive maintenance program, and of the results of the repetitive tests and of the inspections in service. The regulatory decisions were different in each case. Indeed, the Embalse nuclear power station was authorized by the Regulatory Authority to modify from twelve to eighteen months the period among the realization of the repetitive tests and of the preventive maintenance, conditioned to the execution of some specific regulatory requirements. On the other hand, the Atucha I nuclear power station was not authorized to modify this period. In this presentation that is detailed the acted by the Nuclear Regulatory Authority in both cases, the used analysis tools, and the foundation of the adopted decisions. (Author)

Application of the weld in maintenance mechanics at the Nuclear Power Station Atucha I; Aplicaciones de soldadura en mantenimiento de la Central Nuclear Atucha I

Energy Technology Data Exchange (ETDEWEB)

Cosentino, R E

1988-12-31

The application of the `weld procedures`, in the field of activity of nuclear power is an special chapter of weld. The so called `Nuclear Installations` are actually under control from their contruction up to their life extension operation to special control programs and quality assurance. This situation obliges the implementation of procedures to assure the fulfilment of the programs for the need to make the reparations or mechanics construction. This paper describes the considerations that has been taken into account to repare some components of the plant. The works carried out constitute applications to the TIG weld procedure. The `lip weld` is a mechanic component required in pressurized systems subject to air pressure. (Author).

The CNA-1 (Nuclear Power Plant Atucha-1) QK-01 repairing project; Proyecto de reparacion del QK-01 de CNA-1 (Central Nuclear Atucha-1)

Energy Technology Data Exchange (ETDEWEB)

Pizzaferri, J C [Nucleoelectrica Argentina S.A. (NASA), Buenos Aires (Argentina); Cabot, P [Comision Nacional de Energia Atomica, San Martin (Argentina). Centro Atomico Constituyentes

1998-12-31

The repair/maintenance of the CNA-1 QK-01 Moderator Cooler will be a leading case of the repair of a class 1 nuclear component in a high radiation environment; utilizing for the work, sophisticated remotely operated equipment. This paper describes the component, the repair-maintenance objective, and the equipment-procedures developed for the intervention. (author) 9 refs., 5 figs. [Espanol] La reparacion/mantenimiento del enfriador del moderador QK-01 de CNA-1 sera un caso sobresaliente de reparacion de un componente nuclear clase 1 en un ambiente de alta radiacion, utilizando equipamiento sofisticado de accion remota. En este trabajo se describen caracteristicas de diseno del componente, objetivos del mantenimiento, y las facilidades y procedimientos desarrollados en el marco del proyecto para realizar la tarea en cuestion. (autor)

The text of the agreement between the Agency and Argentina for the application of safeguards to the Atucha power reactor facility

International Nuclear Information System (INIS)

1995-01-01

The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994. As a result of the coming into force of the aforesaid Agreement for Argentina, the application of safeguards under the Agreement of 3 October 1972 between Argentina and the IAEA for the application of safeguards to the Atucha Power Reactor Facility has been suspended

Chemical and radiochemical control of the primary circuit of Atucha INPP (Nuclear Power Plant) since the start up in January 1990

International Nuclear Information System (INIS)

Ali, S.P; Baungartner, E.C.; Blesa, M.A.

1990-01-01

Since the start up of Atucha I Nuclear Power Plant in January 1990, an exhaustive chemical and radiochemical control of primary media was undertaken. The main objectives were the evaluation of the water condition after the long outage and the determination of activity measurements limitations to detect and localize fuel failures. Chemical and radiochemical techniques were critically proved. At the same time, a complete program of updating and optimization of those procedures was developed, including the revision of the analytical parameters, range of applicability and accuracy. A more adequate processing of data was adopted. They were compared with historical values corresponding to periods with and without fuel elements failures, used as references. The analysis of theoretical models of total gamma activity concentration and some specific radionuclides activity concentration evolution and their rates, and the comparison with experimental data obtained during normal operation including some failure events, generated tables of alarm criteria through a combination of parameters. Additionally, actions are suggested for different combination of parameters. Operative conditions that might interfere in the detection and localization of a failed fuel element are also pointed out. (Author)

Analysis of extreme hydrometric values in the nuclear power plants siting

International Nuclear Information System (INIS)

Gomez, H.R.; Maggio, G.E.; Tripoli, C.R.

1983-01-01

The atucha nuclear power plants are located on the right shore of the Parana de las Palmas river in the entire transition between a fluvial regime and other of tides. Since the disponibility of cooling water is one of the factors to take into account when choosing the nuclear power plant site, it is essential to perform a probabilistic study of extreme hydrometric values. Deterministic and historical analysis should be done to complete the studies already mentioned, in order to establish the values of probable maximum floods. From the application of these methods, it is concluded that the site of the Atucha nuclear power plants constitutes a hydrometric singularity, so that, an optimization has been obtained from that point of view. (Author) [es

Ageing management program of wires for Atucha II Nuclear Power Plant

International Nuclear Information System (INIS)

Zorrilla, J.; Antonaccio, E.; Luraschi, C.; Simionato, E.; Nieto, H.

2012-01-01

Electrical cables constitute one of the most important components of NPP in terms o maintenance, safety and availability of the plant. Due to their large extension (thousands of kilometers) it is impossible to fully replace them and aging management becomes essential for long term operation of NPP. Since Atucha II is under construction there was a good opportunity to establish and implement a holistic cable aging management program from the beginning according to the state of the art in this field. The scope of this program involves safety related cables, including EQ cables and non EQ cables as well. Due to the diversity of the installed cables is impossible to address an aging management program of every single specimen. However it is possible to establish 'cables families' of similar aging behavior based on insulation and jacket material, manufacture, etc Several aging management strategies were set for the different 'cables families'. These strategies include cables deposit in plant, elaboration of procedures of visual and tactile inspection, NDE techniques, etc Currently the aging management program is being implemented covering topic such as: Cable screening and grouping. Review of EQ documentation and conventional qualification information referring to the installed cables. Establishment of base line of condition monitoring techniques. Calibration and set up of test parameters for NDE techniques. Aging mechanism characterization and determination of. Design construction and installation of cable deposit in plant (author)

Main pumps lost incident in the nuclear power plant Atucha I. Modelling with RELAP5/MOD3.2

International Nuclear Information System (INIS)

Ventura, M.A.; Rosso, R.D.

1998-01-01

Time evolution of natural circulation in the nuclear power plant Atucha I (CNA-I), in a main pumps lost incident because of the lost of external power feed, is analyzed. It leads to a strong stop transient, without an important blow down, from a forced nominal flow to a natural circulation one. The results are obtained from RELAP5/MOD3.2 code's modeling. The study is based on the refrigeration conditions analysis, during the first minutes of the reactor out of service. Previously to the transient, work had been done to obtain the plant steady state, with design parameters in operation conditions at 100 % of power. The object is that the actual plant state would be represented. In this way, each plant part (steam generators, reactor, pressurizer, pumps) had been modeled in separated form with the appropriate boundary conditions, to be used in the whole circuit simulation. The developed model, had been validated making use of the comparison between the values obtained to the principal thermodynamic parameters with the plant recorded values, in the same incident. The results are satisfactory in a way. On the other hand, it has suggested some modeling changes. The RELAP5/MOD3.2 capability to model the thermodynamic phenomena in a PHWR plant has been verified when, according to the mentioned incident, the flow pass from a nominal forced flow, to one which is governed by natural circulation, still with the CNA-I untypical design conditions. (author) [es

Criticality and shielding calculations of an interim dry storage system for the spent fuel from Atucha I Nuclear Power Plant

International Nuclear Information System (INIS)

Silva, M

2006-01-01

The Atucha I Nuclear Power Plant (CNA-I) has enough room to store its spent fuel (SF) in damp in its two pool houses until the middle of 2015.Before that date there is the need to have an interim dry storage system for spent fuel that would make possible to empty at least one of the pools, whether to keep the plant operating if its useful life is extended, or to be able to empty the reactor core in case of decommissioning.Nucleolectrica Argentina S.A. (NA-SA) and the Comision Nacional de Energia Atomica (CNEA), due to their joint responsibility in the management of the SF, have proposed interim dry storage systems.These systems have to be evaluated in order to choose one of them by the end of 2006.In this work the Monte Carlo code MCNP was used to make the criticality and shielding calculations corresponding to the model proposed by CNEA.This model suggests the store of sealed containers with 36 or 37 SF in concrete modules.Each one of the containers is filled in the pool houses and transported to the module in a transference cask with lead walls.The results of the criticality calculations indicates that the solutions of SF proposed have widely fulfilled the requirements of subcriticality, even in supposed extreme accidental situations.Regarding the transference cask, the SF dose rate estimations allow us to make a feedback for the design aiming to the geometry and shielding improvements.Regarding the store modules, thicknesses ranges of concrete walls are suggested in order to fulfill the dose requirements stated by the Autoridad Regulatoria Nuclear Argentina [es

Nuclear Activities in Argentina, 2010

International Nuclear Information System (INIS)

Ferreri, J.C.; Ferreri, J.C.; Clausse, A.; Clausse, A.; Clausse, A.; Ordonez, J.P.; Mazzantini, O.A.

2011-01-01

Nuclear activities in Argentina are restarted. After almost two decades of near stagnation, the governments political decision of August 2006 regarding electrical energy production, considered the nuclear option as a valid one to solve the problems of the growing demand of electrical energy. This decision triggered again the activities related to the finalization of the third nuclear power reactor (Atucha-II), now actively progressing, the construction of a prototype of the CAREM integral advanced reactor, the life extension of the Embalse CANDU nuclear power plant (NPP) and the studies for the emplacement of a fourth NPP in an appropriate site. In all those years of near stagnation, there were notable exceptions related to the design and construction of experimental and radioisotope production reactors, led by INVAP, a state-owned industry, which exported its production. The accompanying industries of nuclear fuel elements production also remained active, given the demand of the two active NPPs. Meanwhile, the National Atomic Energy Commission of Argentina continued the efforts on research and development that were at the base of the technological achievements of the nuclear activities in Argentina. Nuclear safety studies associated with Atucha II and Embalse NPPs and radiological safety were also a substantive part of the continued efforts by Nucleo-Electrica de Argentina SA and the Nuclear Regulatory Authority of Argentina

Overview of the SEU project for extended burnup at the Atucha-I NPP. Four years of operating experience

International Nuclear Information System (INIS)

Fink, J.M.; Higa, M.; Perez, R.; Pineyro, J.; Sidelnik, J.; Casario, J.A.; Alvarez, L.

2002-01-01

Atucha I is a 357 MWe nuclear station moderated and cooled with heavy water, of German design located in Argentina. Fuelling is on-power and the plant was originally fuelled with natural uranium. To reduce fuel costs a program was initiated in August 1993 to introduce gradually slightly enriched uranium (SEU) fuel (0.85 w% U-235) with an associated burnup increase from 5900 MWd/tU to 11300 MWd/tU. The introduction of SEU fuel started in January 1995 and the program was divided in three Phases with an upper limit of SEU FA in the core: 12, 60 and 252 (full core) and licensing documentation was prepared for each Phase. This paper describes the most important aspects of the operating and project experience, and some factors limiting the burnup extension from an operation point of view. After four years of the program and with 181 SEU FA (71%) of the core, the operating experience has been good and without unfavourable effects due to the use of SEU fuel with the only exception of a small increase of the time to reach full power in plant startups or power cycling. In particular, the new criteria to prevent PCI failures in power ramps for higher burnup SEU fuel in refueling operations, plant startups or power cycling has been effective. The average discharge burnup of the SEU fuel taken out of the reactor in 1998 was 11263 MWd/tU. The average discharge burnup of the natural fuel in the same year was 6640 MWd/tU, with an increase of about 12% of the original value for a natural fuel core. The average number of fresh fuel assemblies per full power day was being reduced from 1.31 to 0.92 in 1998 and 0.83 in 1999. The fuel costs dropped gradually during the program from 9.38 (with natural uranium fuel) to 6.57 $/MWh in the first four months of 1999 (taking as reference the NU and SEU FA costs for 1999). Because of this the SEU program has been an important contribution to the reduction of Atucha I operating costs and to the competitiveness of nuclear power generation against

New fuel advanced heavy water reactors

International Nuclear Information System (INIS)

Notari, Carla

1999-01-01

A redesign of the PHWR fuel element (FE) to be used in all Argentine nuclear power plants has been proposed elsewhere. This new FE presents several characteristics aimed to an improved in-core performance and economical benefits derived from the unification of most of the fabrication processes that today constitute two different production lines: one for Embalse nuclear power plant CANDU type fuel and another for Atucha I. Atucha I and Embalse, the two operating nuclear power plants in Argentina, are PHWR of different conception. Atucha I (357 M we) is of pressure vessel type and the fuel elements are full-length assemblies (530 cm of active length) with 36 uranium rods in the cluster and a support one in the outer ring. Embalse (648 M we) is a CANDU pressure tube reactor fuelled with the well known 37 rod / 50 cm length fuel bundles, twelve of which are loaded in each channel. The more relevant changes in the proposed design are an increased subdivision of the fuel material in 52 rods and a 100 cm long bundle. The combined features give the adequate channel pressure drop. The proposed CARA design shows a superior neutronic performance than the standard PHWR fuel elements currently used in Atucha I and Embalse nuclear power plants. A variant of the CARA FE consisting in the elimination of the central four rods, leaving 48 rods and a central free space, is strongly recommended because it saves materials (less uranium, less sheaths) with no loss of burnup. The central D 2 O zone allows a better utilization of the inner rods and compensates the diminished uranium loading. In Embalse no differences in core physics are expected except the beneficial decrease in linear power density. In Atucha I besides the lower power density, a higher exit burnup appears as a consequence of the higher uranium inventory. The exit burnup figures have been calculated with cell and reactor models and the result is that similar fuel management schemes as the proposed for Atucha I for the

Atucha-I source terms for sequences initiated by transients

International Nuclear Information System (INIS)

Baron, J.; Bastianelli, B.

1997-01-01

The present work is part of an expected source terms study in the Atucha I nuclear power plant during severe accidents. From the accident sequences with a significant probability to produce core damage, those initiated by operational transients have been identified as the most relevant. These sequences have some common characteristics, in the sense that all of them resume in the opening of the primary system safety valves, and leave this path open for the coolant loss. In the case these sequences continue as severe accidents, the same path will be used for the release of the radionuclides, from the core, through the primary system and to the containment. Later in the severe accident sequence, the failure of the pressure vessel will occur, and the corium will fall inside the reactor cavity, interacting with the concrete. During these processes, more radioactive products will be released inside the containment. In the present work the severe accident simulation initiated by a blackout is performed, from the point of view of the phenomenology of the behavior of the radioactive products, as they are transported in the piping, during the core-concrete interactions, and inside the containment buildings until it failure. The final result is the source term into the atmosphere. (author) [es

Mixed wastes treatment in Atucha I

International Nuclear Information System (INIS)

Varani, J.L.; Comandu, J.F.

1998-01-01

Full text: During decontamination works of the fueling machine of Atucha I nuclear power plant (AINPP), a liquid waste with special characteristics was generated, which needed the development of a treatment method. The waste consisted of an emulsion designed for the cleaning of mechanical components and was formed by an organic solvent dispersed in water with aid of an emulsifier additive. After several cleaning operations, the emulsion contained an important quantity of lubricants and radioactive dirt. The treatment had the objective of recycling a toxic waste such as the organic solvent and reducing the volume of the residual mass. Laboratory tests were made tending to the emulsion separation in their components. Ionic force and ionic mobility were modified for join the emulsion micelles and produce their coalescence. Different salts and working temperatures were tried and it was stated that the combination of 1% of Na 2 SO 4 added and 40 degree C temperature were the optimum taking into account the available equipment in AINPP and cost considerations. The process was carried out in batch mode and 3 residual streams were obtained, an aqueous one which was sent to Residual Water System of AINPP, an organic liquid consisting of decontaminated hydrocarbons, useful for other cleaning tasks and finally a solid one, sited in the in-between interface of the other two liquids, consisting of insoluble soaps used as lubricant thickness, containing the principal proportion of radioactivity. As a result of this process we have achieved a volume reduction higher than 90%, the recycling of the organic solvent and concentration of radioactivity in a solid greasy mass with low water solubility. (author) [es

Operational experience with the first eighteen slightly enriched uranium fuel assemblies in the Atucha-1 nuclear power plant

International Nuclear Information System (INIS)

Higa, M.; Perez, R.; Pineyro, J.; Sidelnik, J.; Fink, J.; Casario, J.A.; Alvarez, L.

1997-01-01

Atucha I is a 357 Mwe nuclear station, moderated and cooled with heavy water, pressure vessel type of German design, located in Argentina. Fuel assemblies (FA) are 36 active natural UO2 rod clusters, 5.3 meters long and fuel is on power. Average FA exit burnup is 6 MWd/kg U. The reactor core contains 252 FA. To reduce the fuel costs about 6 MU$S/yr a program of utilization of SEU (0.85 %w U235) fuel was started at the beginning of 1995 with the introduction of 12 FA in the first step. The exit burnup of FA is approx. 10 MWd/kgU. It is planned to increase gradually the number of them up to having a full core with SEU fuel with an expected FA average exit burnup of 11 MWd/kgU. The SEU program has also the advantage of a strong reduction of spent fuel volume, and a moderate reduction of fuelling machine use. This paper presents the satisfactory operation experience with the introduction of the first 12 SEU fuel assemblies and the planned activities for the future. The fresh SEU fuel assemblies were introduced in six fuel channels located in an intermediate zone located 136 cm from the center of the reactor and selected because they have higher margins to the channel powers limits to accommodate the initial 15 to 20 % relative channel power increase. To verify the design and fuel management calculations, comparisons have been made of the calculated and measured values of the variation of channel ΔT, regulating rods insertion and flux reading in in-core detectors near to the refueled channel. The agreement was good and in most of the cases within the measurement errors. Cell calculations were made with WIMS-D4, and reactor calculations with PUMA. a fuel management 3D diffusion program developed in Argentina. With SEU fuel with a greater burnup in the central high power core region, new operating procedures were developed to prevent PCI failures in fuel power ramps that arise during operation. Some fuel rod and structural assembly design changes were introduced on the

The power control system of the Siemens-KWU nuclear power station of the PWR [pressurized water reactors] type

International Nuclear Information System (INIS)

Huber, Horacio

1989-01-01

Starting with the first nuclear power plant constructed by Siemens AG of the pressurized light water reactor line (PWR), the Obrigheim Nuclear Power Plant (340 MWe net), until the recently constructed plants of 1300 MWe (named 'Konvoi'), the design of the power control system of the plant was continuously improved and optimized using the experience gained in the operation of the earlier generations of plants. The reactor power control system of the Siemens - KWU nuclear power plants is described. The features of this design and of the Siemens designed heavy water power plants (PHWR) Atucha I and Atucha II are mentioned. Curves showing the behaviour of the controlled variables during load changes obtained from plant tests are also shown. (Author) [es

Some conclusions obtained from the thermo-hydraulic behavior analysis of the nuclear power plant Atucha I, in case of loss of coolant accident with second heat sink

International Nuclear Information System (INIS)

Ventura, Mirta A.

2003-01-01

This paper is based on the recompilation, analysis and elaboration of the results of the operator (NA-SA), in the framework of the Atucha I Second Heat Sink project. The results have been compared with those obtained for the same power plant without second heat sink. The conclusions of the work permit the establishment of the operation rules of the plant. (author)

The text of the agreement of 15 July 1981 between Argentina and the Agency for the application of Safeguards in connection with contracts concluded between the Comision Nacional de Energia Atomica Argentina and the Kraftwerk Union AG (Federal Republic of Germany) for the supply of the Atucha II Nuclear Power Plant

International Nuclear Information System (INIS)

1995-01-01

The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994. As a result of the coming into force of the aforesaid Agreement for Argentina, the application of safeguards under the Agreement of 15 July 1981 between Argentina and the IAEA for the application of safeguards in connection with contracts concluded between the Comision Nacional de Energia Atomic Argentina and the Kraftwerk Union AG (Federal Republic of Germany) for the supply of the Atucha II Nuclear Power Plant has been suspended

Hydraulic Design of the CARA Fuel Assembly for Atucha-I

International Nuclear Information System (INIS)

Juanico, Luis; Brasnarof, Daniel

2000-01-01

In this paper a hydraulic model of the CARA fuel assembly within the Atucha I fuel channel is developed. Besides, a experimental test running in the CBP low pressure loop have been designed.This model is used for design purpose of the assembly system such as the whole channel pressure drop remains the same that it is at the present.It is observed that choosing the right thickness and hole surface of the assembly system, it is possible tune up the CARA pressure drop, releases the azimuth alignment condition on the fuel element neighbors

Nuclear fuel supply view in Argentina

International Nuclear Information System (INIS)

Cirimello, R.O.

1997-01-01

The Argentine Atomic Energy Commission promoted and participated in a unique achievement in the R and D system in Argentina: the integration of science technology and production based on a central core of knowledge for the control and management of the nuclear fuel cycle technology. CONUAR SA, as a fuel manufacturer, FAE SA, the manufacturer of Zircaloy tubes, CNEA and now DIOXITEC SA producer of Uranium Dioxide, have been supply, in the last ten years, the amount of products required for about 1300 Tn of equivalent U content in fuels. The most promising changes for the fuel cycle economy is the Slight Enriched Uranium project which begun in Atucha I reactor. In 1997 seventy five fuel assemblies, equivalent to 900 Candu fuel bundles, will complete its irradiation. (author)

Analysis of the main causes of failures in the Atucha I PWR moderator circuit branch piping

International Nuclear Information System (INIS)

Porto, J.; Sarmiento, G.S.

1983-01-01

From 1977 to 1979 four through cracks were detected in the auxiliary connection of the moderator piping with the coolant circuit in the PWR Atucha I Nuclear Plant. The failures were observed to occur systematically in the same place of the pipe, where mechanical stresses were detected experimentally and thermal stresses were calculated based on temperature values measured on the pipe. The temperature field in steady state conditions as well as during thermal shocks was modelled by finite element codes, and the corresponding thermal stresses were than numerically calculated. Considering those thermal and mechanical solicitations, a crack propagation analysis based on the elastoplastic fracture mechanics and the finite element method is now being developed. Among other causes such as fatigue corrosion and vibrations, the results of the analysis show that the most preponderant factors determining the cracking are mechanical stress, thermal stress and thermal fatigue

Construction and cost experience regarding the 2nd pool house for spent fuel storage facility in the Atucha Power Station

International Nuclear Information System (INIS)

Barbosa, C.A.

1980-01-01

The Atucha I second pool house storage for spent fuel is designed as an extension of the Atucha I power station. The two are linked by civil structure, controlling circuits, electrical and compressed air and water supplies, low level wastes disposal, ventilation under pressure maintenance, and, most important, the ability to transfer spent and new fuel in both directions. Because the second pool house is, by location and design, an extension of the existing installation, and since there is no design departure, regarding storage and transfer of fuel from that of the original installation, the rules and regulations applied for its construction were the same as those valid for the Atucha I construction. The requirement not to exceed a four-year period for construction and commissioning was determined by the need to have storage room for the Atucha I fuel. Argentina will meet the 1982 target by having the installation available during the second half of 1981. The second pool house is a wet storage location with a capacity of 1000 tons metallic uranium. It was designed by the Kraftwerk Union of West Germany along the same lines as the 440-ton storage location originally built with the station. The Atomic Energy Commission of Argentina has managed the construction and participated in project and design stages. As in the original pool, the 6 m long assemblies are stacked in double tiers. The cost figures which are mentioned differ from previously released figures and are not the final ones. With civil construction almost finished and mechanical erection started, the present estimates should not differ by more than 10% from the final figures. The installation has an investment cost of 61 million dollars, (1980), and, depending on the amortization time span considered, a total yearly cost per kg of capacity of metallic uranium, ranging between 5.5 and 9.3 dollars per kg

CARA Project: development of the advanced ULE fuel element for heavy water nuclear power plants

International Nuclear Information System (INIS)

Brasnarof, Daniel O.; Marino, Armando C.; Florido, Pablo C.; Munoz, C.; Bianchi, Daniel R.; Giorgis, Miguel A.

2006-01-01

The CARA Project (Spanish acronym of Combustible Avanzado para Reactores Argentinos) is a national fuel element technology development, compatible with our nuclear power plants (Atucha I, Embalse and Atucha II). It takes into account the experience obtained in our nuclear organisations (CNEA-CONUAR-NASA). The goal of the CARA fuel element is the performance improvement for those reactors and the enhancing of their normal operative conditions. The CARA design allows the burnup extension by using 52 rods of the same diameter. Likewise it keeps good thermo-hydraulic behaviour. The fuel bundle can be directly used in nuclear power plants with horizontal channels. By using an additional system it can be installed in the PHWR with vertical channels. The expected profits, by the use of the CARA in our reactors, broadly guaranty the recovery of the fund for its development, due to a reduction of the NPP fuels and back end cost. We estimate a reduction in the generation cost between 20 or 25 % in relation to the present one if we use 0.85 or 0.90% SEU (Slightly Enriched Uranium). The use of the CARA fuel in our reactors will also reduce the amount of spent fuel to be treated. The shortening could be between 17 to 27 % in Atucha I in relation to the present ULE (0.85%), between 38 to 46% for Embalse, and 45 to 53% for Atucha II. The mechanical behaviour and hydraulic compatibility have been verified. Several CARA prototypes were fabricated with a new design of the end plate and with new processes for the welding for the rods. We present in this paper the current status of the CARA fuel element development. (author) [es

Development and Application of MCNP5 and KENO-VI Monte Carlo Models for the Atucha-2 PHWR Analysis

Directory of Open Access Journals (Sweden)

M. Pecchia

2011-01-01

Full Text Available The geometrical complexity and the peculiarities of Atucha-2 PHWR require the adoption of advanced Monte Carlo codes for performing realistic neutronic simulations. Core models of Atucha-2 PHWR were developed using both MCNP5 and KENO-VI codes. The developed models were applied for calculating reactor criticality states at beginning of life, reactor cell constants, and control rods volumes. The last two applications were relevant for performing successive three dimensional neutron kinetic analyses since it was necessary to correctly evaluate the effect of each oblique control rod in each cell discretizing the reactor. These corrective factors were then applied to the cell cross sections calculated by the two-dimensional deterministic lattice physics code HELIOS. These results were implemented in the RELAP-3D model to perform safety analyses for the licensing process.

Nuclear knowledge management at the IAEA

International Nuclear Information System (INIS)

Yanev, Y.

2004-01-01

Nuclear Knowledge Management as a part of the IAEA mission and its aim to help organizations to achieve competitive advantage; costs reduction; accelerated time to market in companies and large private sector organisations; innovation, supports error free decision making are discussed. The most important outputs such as nuclear knowledge management methodology; identifying endangered areas of nuclear science and technology; developing knowledge repositories; knowledge preservation technology; dedicated projects with Member States, (Atucha, Angra, KNK2, ) are presented. A brief review of the currently implemented with Agency's assistance project ANENT (Asian Network for Education in Nuclear Technology) is also given

Modelling of blackout sequence at Atucha-1 using the MARCH3 code

International Nuclear Information System (INIS)

Baron, J.; Bastianelli, B.

1997-01-01

This paper presents the modelling of a complete blackout at the Atucha-1 NPP as preliminary phase for a Level II safety probabilistic analysis. The MARCH3 code of the STCP (Source Term Code Package) is used, based on a plant model made in accordance with particularities of the plant design. The analysis covers all the severe accident phases. The results allow to view the time sequence of the events, and provide the basis for source term studies. (author). 6 refs., 2 figs

Nuclear Energy in Central Europe 98, Proceedings

International Nuclear Information System (INIS)

Ravnik, M.; Jencic, I.; Zagar, T.

1998-01-01

Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 63 articles from Slovenia, sorounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Nuclear Methods, Reactor Physics, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation and Nuclear Waste disposal

Nuclear relevant installations licensing methodology in the Argentine Republic

International Nuclear Information System (INIS)

Paganini, C.E.

1986-01-01

A review of the requeriments of the Nuclear Installations Advisory Committee on Licensing (CALIN) from the nuclear security point of view, is presented. The methodology applied by the CALIN for the licensing in the Argentine Republic is included as well as codes, standards of applications and the interaction between the licensing Authority and the Responsible Entity during the whole process. Finally, the Atucha II nuclear power plant's licensing, in construction at present, is explained and the standard, of the licensing schedule, is presented graphically. (author) [es

Utilization of noise analysis technique for mechanical vibrations estimation in the ATUCHA1 and Embalse Argentine NPP

International Nuclear Information System (INIS)

Lescano, V.H.; Wentzeis, L.M.; Guevara, M.; Moreno, C.; Pineyro, J.

1996-01-01

In Argentine, comprehensive noise measurements have been performed with the reactor instrumentation of the PHWR power plant Atucha I and Embalse. The Embalse reactor is a CANDU-600 (600 Mwe) type pressurized heavy water reactor. It's a heavy water moderator and heavy water cooled natural uranium fueled pressure tube system. Signal of vanadium and platinum type in core-self power neutron detectors of ex-core ion chambers and of a moderator pressure sensor have been recorded and analysed. The vibration of reactor internals as vertical and horizontal in-core neutron flux detectors units and the coolant channels systems, consisting of calandria and pressure tubes with fuel bundles, have been identified and monitored during normal reactor operation. Atucha I, is a PHWR reactor natural uranium fueled, and heavy water moderated and cooled. Neutron noise techniques using of ex-core ionization chambers and in-core Vanadium SPND's were implemented, among others, in order to produce early detection of anomalous vibrations in the reactor internals. Noise analysis was successfully performed to identify normal and peculiar vibrations in particular reactor internals. (author)

The Text of the Agreement between the Agency and Argentina for the Application of Safeguards to the Atucha Power Reactor Facility

Energy Technology Data Exchange (ETDEWEB)

NONE

1973-01-25

The text of the Agreement between the Agency and the Government of the Republic of Argentina for the Application of Safeguards to the Atucha Power Reactor Facility is reproduced in this document for the information of all Members.

Simulation with the MELCOR code of two severe accident sequences, Station Blackout and Small Break LOCA, for the Atucha I nuclear power plant

International Nuclear Information System (INIS)

Valle Cepero, Reinaldo

2004-01-01

The results of the PSA-I applied to the Atucha I nuclear power plant (CNA I) determine the accidental sequences with the most influence related to the probability of the core reactor damage. Among those sequences are include, the Station Blackout and lost of primary coolant, combine with the failure of the emergency injection systems by pipe breaks of diameters between DN100 - DN25 or equivalent areas, Small LOCA. This paper has the objective to model and analyze the behavior of the primary circuit and the pressure vessel during the evolution of those two accidental sequences. It presented a detailed analysis of the main phenomena that occur from the initial moment of the accident to the failure moment of the pressure vessel and the melt material fall to the reactor cavity. Two sequences were taken into account, considering the main phenomena (core uncover, heating, fuel element oxidation, hydrogen generation, degradation and relocation of the melt material, failure of the support structures, etc.) and the time of occurrence, of those events will be different, if it is considered that both sequences will be developed in different scenarios. One case is an accident with the primary circuit to a high pressure (Station Blackout scenario) and the other with a early primary circuit depressurization due to the lost of primary coolant. For this work the MELCOR 1.8.5 code was used and it allows within a unified framework to modeling an extensive spectrum of phenomenology associated with the severe accidents. (author)

Comparison of vibration test results for Atucha II NPP and large scale concrete block models

International Nuclear Information System (INIS)

Iizuka, S.; Konno, T.; Prato, C.A.

2001-01-01

In order to study the soil structure interaction of reactor building that could be constructed on a Quaternary soil, a comparison study of the soil structure interaction springs was performed between full scale vibration test results of Atucha II NPP and vibration test results of large scale concrete block models constructed on Quaternary soil. This comparison study provides a case data of soil structure interaction springs on Quaternary soil with different foundation size and stiffness. (author)

Central depression of nuclear charge density distribution

International Nuclear Information System (INIS)

Chu Yanyun; Ren Zhongzhou; Wang Zaijun; Dong Tiekuang

2010-01-01

The center-depressed nuclear charge distributions are investigated with the parametrized distribution and the relativistic mean-field theory, and their corresponding charge form factors are worked out with the phase shift analysis method. The central depression of nuclear charge distribution of 46 Ar and 44 S is supported by the relativistic mean-field calculation. According to the calculation, the valence protons in 46 Ar and 44 S prefer to occupy the 1d 3/2 state rather than the 2s 1/2 state, which is different from that in the less neutron-rich argon and sulfur isotopes. As a result, the central proton densities of 46 Ar and 44 S are highly depressed, and so are their central charge densities. The charge form factors of some argon and sulfur isotopes are presented, and the minima of the charge form factors shift upward and inward when the central nuclear charge distributions are more depressed. Besides, the effect of the central depression on the charge form factors is studied with a parametrized distribution, when the root-mean-square charge radii remain constant.

Experimental and numerical determination of the dynamic properties of the reactor building of Atucha II NPP

International Nuclear Information System (INIS)

Ceballos, M.A.; Car, E.J.; Prato, T.A.; Prato, C.A.; Alvarez, L.M.; Godoy, A.R.

1995-01-01

Determination of the dynamic properties of the reactor building of Atucha II NPP is carried out in order to: i) Obtain valuable information for seismic qualification of the plant, and ii) Assess some procedures for testing and analysis that are used in the process of seismic evaluation of existing nuclear facilities founded on Quaternary soil deposits. Both steady state and impulsive dynamic tests were performed but attention is centered here in tile techniques used to determine natural frequencies and modal damping ratios with impulsive tests. Numerical analyses were performed by means of a 3-D model model of the superstructure together with foundation stiffness coefficients derived in a separate paper from steady state vibration tests, and also from analysis with a 2-D F.E. model of the soil layers capable of approximating the 3-D features of the problem. The computed foundation stiffness coefficients are compared both with those obtained from the tests and from an axisymmetric F.E. model; results indicate that foundation stiffness coefficients calculated with F.E. models with soil parameters given by laboratory tests performed on cored samples are significantly lower than those given by the steady state vibration tests. (author)

Analysis of occupational doses in radioactive and nuclear facilities

International Nuclear Information System (INIS)

Curti, A.; Gomez P, I.; Pardo, G.; Thomasz, E.

1996-01-01

Occupational doses were analyzed in the most important nuclear and radioactive facilities in Argentina, on the period 1988-1994. The areas associated with uranium mining and milling, and medical uses of radiation facilities were excluded from this analysis. The ICRP publication 60 recommendations, adopted in 1990, and enforced in Argentine in 1994, keep the basic criteria of dose limitation system and recommend a substantial reduction in the dose limits. The reduction of the dose limits will affect the individual dose distributions, principally in those installations with occupational doses close to 50 mSv. It were analyzed Occupational doses, principally in the following facilities: Atucha-I and Embalse Nuclear Power Plants, radioisotope production plants, research reactors and radioactive waste management plants. The highest doses were identified in each facility, as well as the task associated with them. Trends in the individual dose distribution and collective and average doses were analyzed. It is concluded, that no relevant difficulties should appear in accomplishing with the basic standards for radiological safety, except for the Atucha-I Nuclear Power Plant. In this NPP a significant effort for the optimization of radiological safety procedures in order to diminish the occupational doses, and a change of the fuel channels by new ones free of cobalt are being carried out. (authors). 4 refs., 3 figs., 3 tabs

Sampling and characterization of spent exchange resins of Atucha I nuclear power plant

International Nuclear Information System (INIS)

Varani, Jose L.; Cernadas, D.; Iglesias, Alberto M.; Raffo Calderon, Maria del C.

2004-01-01

The present storage facilities for spent resins in Atucha I NPP would be full within the next 5 years, accordingly some tasks are being planned to conditioning these waste and so generate enough storage capacity for the remaining life of the plant. Among this tasks is the characterization of spent resins that has several objectives: to know their chemical and radiochemical composition; the homogeneity of these parameters in the total volume of spent resins; the existence or not of compact zones; the proportion of 'crud'; the breakage degree of the micro-spheres; etc. The first step was to analyse the criterion to follow for sampling resins in the storage deposit of 40 m 3 . In order to take some samples from different points, a special device was required. It had to be introduced closed in the resin bed, opened to take the sample and then closed again to return to the surface. A device used in cereal industry for sampling silos to different depths was modified in its internal capacity for reducing operator dose and increasing the length of rod in order to reaching the bottom of the pit. The device was tested in cold mock up before to taking actual samples. Active resins samples, five in total up to now, were taken from deposit to different depths and kept in lead containers. After analysing the samples, the following average results were extracted: 1.7 x 10 5 Bq/g of Co-60, 9.7 x 10 5 Bq/g of Cs-137 and 774 Bq/g of total alpha, which corresponds to intermediate activity waste. The differences between the values of activity of the different samples are of up to 310 % for Co-60 and of up to 788 % for the Cs-137 what indicates a great inhomogeneity. The direct observation of resin grains, placed in a transparent glass burette, did not demonstrate an important proportion of broken or divided resins. (author)

Study of the Atucha I nuclear power plant's residual heat removal system unavailability through the fault tree analysis and common cause failures

International Nuclear Information System (INIS)

Terrado, C.A.

1991-06-01

The present essay offers a comprehensive research of the Atucha I nuclear power plant's residual heat removal system unavailability, including Fault Tree Analysis and Common Cause Failures (CCF) treatment. The study is developed within the Event Tree perspective that considers the loss of external electrical power of the initiating event. The event was constructed by the Safety Evaluations Division of the Ezeiza Atomic Center in Argentina. According to the Event Tree, the research includes system demand during plant operation with 132 KV and emergency generation (Diesel motor generators). The system unavailability assessment is approached in two different ways: a) Considering independent failures only. b) Taking into account the existence of Common Cause Events, and modeling dependent failures. The Fault Tree quantification is played using the AIEA PSAPACK Code. The assessment data base is compiled from plant specific records and generic data bases like TECDOC 478. After Fault Tree model logic development, some general procedures used in common cause failures treating are applied to pick up another set of solutions. The results of the study are: a) Four Fault Trees have been developed to model the abovementioned system: 132 KV and emergency generation, both including and excluding CCF. b) The following unavailability values were obtained: 132 KV independent failures only: 7 10 -4 . Emergency generation independent failures only: 1.53 10 -2 . 132 KV dependent and independent failures: 3.6 10 -3 . Emergency generation dependent and independent failures: 1.74 10 -2 . The major conclusions obtained from the precedent results are: a) When using 132 KV system configuration, minimal cut sets involving common cause failures represents 81%from total system unavailability. b) The dependent failures treatment is an important task to be considered in safety assessments in order to reach more realistic values. (Author) [es

Central Institute for Nuclear Research (1956 - 1979)

International Nuclear Information System (INIS)

Flach, G.; Bonitz, M.

1979-12-01

The Central Institute for Nuclear Research (ZfK) of the Academy of Sciences of the GDR is presented. This first overall survey covers the development of the ZfK since 1956, the main research activities and results, a description of the departments responsible for the complex implementation of nuclear research, the social services for staff and the activities of different organizations in the largest central institute of the Academy of Sciences of the GDR. (author)

Case study - Argentina

International Nuclear Information System (INIS)

Diaz, E.

1986-01-01

Antecedents and experience of nuclear activities in Argentina; the Atomic Energy Commission (CNEA). First development and research activities. Research reactors and radioisotopes plants. Health physics and safety regulations. - Feasibility studies for the first nuclear power plant. Awarding the first plant CNA I (Atucha I). Relevant data related to the different project stages. Plant performance. - Feasibility study for the second nuclear power plant. Awarding the second plant CNE (Central Nuclear Embalse). Relevant data related to established targets. Differences compared with the first station targets. Local participation. Plant performance. (orig./GL)

Nuclear Activities in Argentina. A short Review. Part 2

International Nuclear Information System (INIS)

Coll, Jorge A.; Radicella, Renato

2002-01-01

The second part of this historical review covers the 'industrial' period of nuclear energy in Argentina. The National Atomic Energy Commission (CNEA), after a feasibility study carried out by argentine experts, in 1968 signed a contract to build a nuclear power plant. This PHWR plant, Atucha 1, of 310 MWe was inaugurated in 1973 and it is still operating. The same year the CNEA signed a new contract to build a CANDU type plant of 600 MWe, Embalse, that was finally inaugurated in 1983. The construction of a third plant, Atucha 2 of 745 MWe also a PHWR, was started in 1980 but was arrested in 1994, when more than 80% was completed, and it is still waiting a political decision to reach completion. Within the development of the nuclear power program, a fuel element production plant for the Argentine power reactors was built by the CNEA and a heavy water production plant of 250 tons/year was inaugurated in 1993 in the southern province of Neuquen. A pilot spent fuel reprocessing plant was designed but its construction was not completed. At the same time, a pilot gaseous diffusion plant was constructed in order to produce enriched uranium for research reactors. The activities in the field of radioisotope and radiation applications were also intensive, mainly in nuclear medicine and food preservation. A facility to fabricate sealed sources was built to process the Co 60 produced by the Embalse power plant. Argentina was active in the export of nuclear facilities: CNEA built a complete nuclear research center in Peru, and the Argentine company INVAP built research reactors in Algeria and Egypt. The same company is now building a research reactor in Australia. (author)

Nuclear power production costs

International Nuclear Information System (INIS)

Erramuspe, H.J.

1988-01-01

The economic competitiveness of nuclear power in different highly developed countries is shown, by reviewing various international studies made on the subject. Generation costs (historical values) of Atucha I and Embalse Nuclear Power Plants, which are of the type used in those countries, are also included. The results of an international study on the economic aspects of the back end of the nuclear fuel cycle are also reviewed. This study shows its relatively low incidence in the generation costs. The conclusion is that if in Argentina the same principles of economic racionality were followed, nuclear energy would be economically competitive in the future, as it is today. This is of great importance in view of its almost unavoidable character of alternative source of energy, and specially since we have to expect an important growth in the consumption of electricity, due to its low share in the total consumption of energy, and the low energy consumption per capita in Argentina. (Author) [es

Fourth Regional Meeting: Nuclear Energy in Central Europe, Proceedings

Energy Technology Data Exchange (ETDEWEB)

Mavko, B; Cizelj, L [eds.; Nuclear Society of Slovenia (Slovenia)

1997-07-01

Fourth Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 89 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accidents, Ageing and Integrity, Thermal Hydraulics, NPP Operation Experiance, Radioactive Waste Management, Environment and Other Aspects, Public and Nuclear Energy, SG Replacement and Plant Uprating.

Nuclear insurance in Central and Eastern Europe

International Nuclear Information System (INIS)

Warren, G.

1998-01-01

In the world outside the former Soviet Union, insurance industries in their respective domestic markets have pooled their resources so as to provide a secure and cost-effective conduit for the transaction of insurance business on behalf of the nuclear industry. These are the so-called nuclear pools. This paper explains the four main principles behind nuclear liability insurance and discusses their application to Central Europe and in particular to the problems facing the nuclear industry in Eastern Europe. (author)

Methodology and Software for Gross Defect Detection of Spent Nuclear Fuel at the Atucha-I Reactor

Energy Technology Data Exchange (ETDEWEB)

Sitaraman, Shivakumar; Ham, Young S.; Gharibyan, Narek [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, CA 94550 (United States); Peixoto, Orpet J.M. [Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, Avenida Rio Branco, 123/Grupo 515- Centro, CEP: 20040-005, Rio de Janeiro (Brazil); Diaz, Gustavo [National Regulatory Authority - Argentina, Av. Del Libertador 8250, (1429) Buenos Aires (Argentina)

2015-07-01

At the Atucha-I pressurized heavy water reactor in Argentina, fuel assemblies in the spent fuel pools are stored by suspending them in two vertically stacked layers. This introduces the unique problem of verifying the presence of fuel in either layer without physically moving the fuel assemblies. Since much of the fuel is very old, Cerenkov viewing devices are often not very useful even for the top layer. Given that the facility uses both natural uranium and slightly enriched uranium at 0.85 w% {sup 235}U, and has been in operation since 1974, a wide range of burnups and cooling times can exist in any given pool. A spent fuel neutron counting tool consisting of a fission chamber, SFNC, has been used at the site to verify the presence of fuel up to burnups of 8000 MWd/t. At higher discharge burnups to levels up 11,000 MWd/t, the existing signal processing software of the tool was found to fail due to non-linearity of the source term with burnup. A new Graphical User Interface software package based on the LabVIEW platform was developed to predict expected neutron signals covering all ranges of burnups and cooling times and establish maps of expected signals at various pool locations. The algorithm employed in the software uses a set of transfer functions in a 47-energy group structure which are coupled with a 47-energy group neutron source spectrum based on various cooling times and burnups for each of the two enrichment levels. The database of the software consists of these transfer functions for the three different inter-assembly pitches that the fuel is stored in at the site. The transfer functions were developed for a 6 by 6 matrix of fuel assemblies with the detector placed at the center surrounded by four near neighbors, eight next nearest neighbors and so on for the 36 assemblies. These calculations were performed using Monte Carlo radiation transport methods. The basic methodology consisted of starting sources in each of the assemblies and tallying the

Nuclear Electric's central dose record service

International Nuclear Information System (INIS)

Goldfinch, E.P.; Mullarkey, D.T.; McWhan, A.W.; Risk, G.; Vaughan, L.

1991-01-01

This paper describes the conception, development and operation of the Nuclear Electric Central Dose Record Service, including the initial philosophy considered necessary for a database for a large multi-site organisation, the setting up of the data and current routine operation. Lessons learned are briefly described. CDRS holds 35,000 records in a high security environment. The database includes records of radiation doses received by contractor's employees working at Nuclear Electric sites as well as dose records and dose histories for classified and non classified Nuclear Electric employees. (Author)

Water chemistry of Atucha II PHWVR. Design concepts and evolution

International Nuclear Information System (INIS)

Chocron, Mauricio; Rodriguez, Ivanna; Duca, Jorge; Fernandez, Ricardo; Rico, Jorge

2007-01-01

Full text: Atucha II is a pressurized heavy water vessel reactor designed by Siemens-KWU, currently part of AREVA NP, of 745 MWe and similar to Atucha I, which has been in operation over 25 years. The primary heat transport system (PHTS) is composed by vertical channels (277-313 C degrees) that allocate the fuel elements while the moderator circuit is composed by a partially separated circuit (142-173 C degrees). The moderation power is transferred to the feedwater through the moderator heat exchangers (HX). These HXs operate as the last, high pressure water-steam cycle heaters as well. Materials (with exception of fuel channels and fuel sheaths which are made of zirconium alloys) are all austenitic steels while cobalt containing alloys have been all replaced at the design stage. Steam generator and moderator HX tubing are Alloy 800 made. The core is operated without boron except with the first fresh nucleus. The secondary circuit or Balance of plant (BOP) is similar in conception to that of a PWR but the moderator HXs. It is entirely built of ferrous alloys, has a feedwater-deaerator tank and moisture separator. The energy sink is the Rio de la Plata River. The Reactors Chemistry Department, Chemistry Division, National Atomic Energy Commission, in its character of R and D institution has been committed by CNA II-N.A.S.A Project to prepare the water chemistry specifications, water chemistry engineering and manuals, considering the type of reactor, design and construction aspects and operation characteristics, taking into account the current state-of-the art and worldwide standards. This includes conceptual aspects and implementation and operative aspects as well. This documentation will be released after a designer's review as it has been stated in the respective agreement. Respecting the confidentiality agreement between CNEA and NASA and the confidentiality regarding handling original documentation provided by the designer, it is considered illustrative to

Manufacturing at industrial level of UO2 pellets for the fuel elements of the Atucha I Nuclear Power Plant

International Nuclear Information System (INIS)

Dyment, I.G.; Noguera Rojas, Francisco

1982-01-01

The interest to produce fuel elements within a policy of self sufficiency arose with the installation of Atucha I. The first steps towards this goal consisted in processing the uranium oxide, transforming it into fuel pellets of high density. The developments towards the fabrication of said pellets, performed by CNEA since 1968, first at a laboratory level and afterwards on an industrial scale, allowed CNEA to obtain its own technological capability to produce 400 kg of UO 2 per day. The fuel pellets manufacturing method developed by CNEA is a powder-metallurgical process, which, besides conventional equipment, involves the use of special equipment that required the performance of systematic testing programmes, as well as special training at operational level. The developed processes respond to a modern and advanced technology. A general scheme of the process, starting with a directly sinterable UO 2 powder, is described, including compacting of the powder into pellets, sintering, control of the temperature in the sintering and reduction zones and of the time of permanence in both zones, and cylindric rectifying of the pellets. During the whole process, specialized personnel controls the operations, after which the material is released by the Quality Control Department. The national contribution to the manufacturing technology of the pellets for fuel elements of power and research reactors was of 100%. (M.E.L.) [es

Third Regional Meeting: Nuclear Energy in Central Europe, Proceedings

International Nuclear Information System (INIS)

Stritar, A.; Jencic, I.

1996-01-01

Third Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 71 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accident management, Thermal Hydraulics, NPP Operation, Radioactive Waste Management, Main Components Integrity, Environment and Other Aspects and Public Information

Third Regional Meeting: Nuclear Energy in Central Europe, Proceedings

Energy Technology Data Exchange (ETDEWEB)

Stritar, A; Jencic, I [Nuclear Society of Slovenia (Slovenia); eds.

1996-07-01

Third Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 71 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accident management, Thermal Hydraulics, NPP Operation, Radioactive Waste Management, Main Components Integrity, Environment and Other Aspects and Public Information.

Argentine activities within the IWGATWR framework

International Nuclear Information System (INIS)

Antunez, H.M.

1991-01-01

The status of power reactors and nuclear activity in Argentina for the period 1988-1990 are described. The reactor shutdown at the Central Nuclear Atucha I and repair works are discussed. Joint venture of the Comision Nacional de Energia Atomica and KWU developments are reported, including the conceptual design of an additional heat sink for pressurized water reactors, a feasibility analysis of the Co-60 production in pressure vessel PHWRs and a study of severe postulated accidents for pressure vessel PHWR. 11 refs, 4 figs

International Conference Nuclear Energy in Central Europe 99, V. 1. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Gortnar, O; Stritar, A [Nuclear Society of Slovenia (Slovenia)

1999-07-01

International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 101 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Reactor Physics, Research Reactors, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation, Nuclear Energy and Public, Radioactive Waste, Radiological Protection and Environmental Issues, Nuclear Methods and Monte Carlo and Deterministic Transport Calculations.

International Conference Nuclear Energy in Central Europe 99, V. 1. Proceedings

International Nuclear Information System (INIS)

Gortnar, O.; Stritar, A.

1999-01-01

International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 101 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Reactor Physics, Research Reactors, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation, Nuclear Energy and Public, Radioactive Waste, Radiological Protection and Environmental Issues, Nuclear Methods and Monte Carlo and Deterministic Transport Calculations

Proceedings of the 2000 International Conference on Nuclear Energy in Central Europe

International Nuclear Information System (INIS)

Mavko, B.; Cizelj, L.; Kovac, M.

2000-01-01

International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 108 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: thermal hydraulics, severe accidents, probabilistic safety assessment (PSA), nuclear waste, safety analyses, nuclear power plant operation, structural integrity and aging, nuclear energy and public, other related topics, research reactors, education and training and Monte Carlo transport calculations

IAEA’s Perspectives on Global Nuclear Power – Opportunities and Challenges

International Nuclear Information System (INIS)

Park, J.K.

2014-01-01

Status of global nuclear power: 437 reactors in operation (374.5 GWe); 2 reactors in long-term shutdown; 149 reactors in permanent shutdown; 70 reactors under construction. [As of Sep. 2014] Latest connections to the grid: - Ningde-2, 1000 MW(e), PWR, China; - Atucha-2, 692 MW(e), PHWR, Argentina; - Fuqing-1, 1000 MW(e), PWR, China). [Website: http://www.iaea.org/pris/]. IAEA projections of nuclear power: • Sep. 2014: 374.5 GWe; • 2030 - low 400.6 GWe: 7.0% increase; - high 699.2 GWe: 86.7% increase; • 2050 - low 412.9 GWe: 10.3% increase; - high 1091.7 GWe: 191.5% increase

Experience in construction and operation of HWR plants in Argentina

International Nuclear Information System (INIS)

Madero, C.C.; Cosentino, J.O.

1982-01-01

''ATUCHA I'', the first nuclear power plant in Argentina, is in commerical operation since 1974 with a high capacity factor. The reactor is based on the MZFR prototype designed by SIEMENS with natural uranium and heavy water and PWR technic. The plant was built by SIEMENS on a turnkey contract and was rated 340 MWe. The offer presented in that opportunity by KWU was based on two reactors (ATUCHA I type) inside one single containment, due to the limitation in power of the reactor. Subsequent changes in the nature of the contract resulted in an active participation of CNEA engineering groups in the erection and commissioning of the reactor. In 1978 the national government approved a nuclear power plan to install four 600 MWe HWR plants until 1995. To start implementing this program, CNEA called for tenders for the supply of components and services for the ATUCHA II plant, in connection with the establishment of a local engineering company and the supply and construction of a heavy water production plant. In 1980 a contract was signed with KWU and the local company ENACE was formed to act as architect engineer and site coordinator. The plant will be located in the ATUCHA I site and the reactor will be similar but double in power to that one. Following the schedule of the nuclear plan, CNEA has just started preliminary studies for the next nuclear plant. ENACE will be responsible for the preparation of an offer for an ATUCHA reactor type. Local engineering and manufacturing firms, upon request and coordination from CNEA, and evaluating the local capacity to participate in the design and construction of a CANDU type nuclear plant. Final decision on this fourth nuclear plant in Argentina will be taken middle 1983. (J.P.N.)

Central eastern Europe approach to the security over nuclear materials

International Nuclear Information System (INIS)

Smagala, G.

2002-01-01

Full text: This paper presents an overview of the national approaches to physical protection of nuclear materials in Central Eastern Europe (CEE), with an emphasis on Poland. Soviet influence in the past led to inadequate safety culture in nuclear activities and insufficient security of nuclear materials and facilities in the region. In the centralized economies all aspects of nuclear activities, including ownership of the nuclear facilities, were the responsibility of the state with no clear separation between regulating and promoting functions. During the last decade a significant progress has been made in the region to clean up the legacy of the past and to improve practices in physical protection of nuclear materials. The countries of Central Eastern Europe have had many similar deficiencies in nuclear field and problems to overcome, but cannot be viewed as a uniform block. There are local variations within the region in a size of nuclear activities, formulated respective regulations and adopted measures to secure nuclear materials and facilities. Nevertheless, all twelve nations, with nuclear reactors and without nuclear facilities, have joined the convention on the physical protection of nuclear material and most of them declare that they have followed the IAEA recommendations INFCIRC/225/Rev.4 to elaborate and implement their physical protection systems of nuclear materials and facilities. The largest request for an international advisory mission (IPPAS) to review states' physical protection systems and to address needs for improvement was received from the countries of Central Eastern Europe. Poland belongs to the beneficiaries where the IPPAS mission and later follow-up consultations resulted in physical protection upgrade of the research reactor under the IAEA/US/UK technical assistance project. A powerful incentive to the progress made in a number of CEE countries was the goal of accession to the European Union. The physical protection of nuclear

Distribution of equilibrium burnup for an homogeneous core with fuel elements of slightly enriched uranium (0.85% U-235) at Atucha I nuclear power plant

International Nuclear Information System (INIS)

Sidelnik, J.I.; Perez, R.A.; Salom, G.F.

1987-01-01

At Atucha I, the present fuel management with natural uranium comprises three burnup areas and one irradiation path, sometimes performing four steps in the reactor core, according to the requirements. The discharge burnup is 6.0 Mw d/kg U for a waste reactivity of 6.5 m k and a heavy water purity of 99.75%. This is a preliminary study to obtain the distribution of equilibrium burnup of an homogeneous core with slightly enriched uranium (0.85% by weight U-235), using the time-averaged method implemented in the code PUMA and a representative model of one third of core and fixed rod position. It was found a strategy of three areas and two paths that agrees with the present limits of channel power and specific power in fuel rod. The discharge burnup obtained is 11.6 Mw d/kg U. This strategy is calculated with the same method and a full core representation model is used to verify the obtained results. (Author)

Central Institute of Nuclear Research Rossendorf 25 years old

International Nuclear Information System (INIS)

Hohmuth, K.; Kaun, K.H.; Schmidt, A.; Hennig, K.; Brinckmann, H.F.; Lehmann, E.; Rossbander, W.; Bitterlich, H.; Weibrecht, R.; Fuelle, R.; Nebel, D.; Reetz, T.; Beyer, G.J.; Muenze, R.

1981-12-01

A colloquium dedicated the 25th anniversary of the foundation of the Central Institute for Nuclear Research of the GDR Academy of Sciences was held on January, 21st, '81. 13 papers were given which dealt with aspects of the institute's history as well as with modern trends in nuclear and solid state physics, nuclear energy and chemistry, radioisotope production, radiation protection and nuclear information. (author)

Proceedings of the International Conference Nuclear Energy in Central Europe 2001

International Nuclear Information System (INIS)

Jencic, I.; Glumac, B.

2001-01-01

International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 98 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: reactor physics, thermal hydraulics, probabilistic safety assessment (PSA) and severe accidents, nuclear materials, NPP and research reactor operation, environmental issues and radiation measurement, fusion, radioactive waste and regulatory issues and public relations

Current situation and future of a nuclear power plan in Argentina

International Nuclear Information System (INIS)

Messi, E.

2006-01-01

After the crisis suffered by Argentina during the first years of the new millennium, the economic variables improved significantly, thus showing the need for an increase in the electric supply. While the growth rate of the electric demand has been of a steady 4%, the electric supply didn't come along as expected; mainly due to the decrease in the gas reserves, among other things. This scenario opens new opportunities for the nuclear area in our country: especially with Atucha II NPP termination that will contribute with 745 MWe gross output, together with Embalse NPP's life extension and refurbishment, and the analysis for the installation of new generation nuclear power plants in the decades to come, therefore strengthening the nuclear industry in Argentina. (author)

Proceedings of the Second Regional Meeting on Nuclear Energy in Central Europe

International Nuclear Information System (INIS)

Stritar, A.; Jencic, I.

1995-01-01

Second Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contains 75 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region

Proceedings of the Second Regional Meeting on Nuclear Energy in Central Europe

Energy Technology Data Exchange (ETDEWEB)

Stritar, A; Jencic, I [eds.; Nuclear Society of Slovenia (Slovenia)

1996-12-31

Second Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contains 75 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region

Fission distribution measurements of Atucha's fuel pellets with solid state track detectors

International Nuclear Information System (INIS)

Ricabarra, M.D. Bovisio de; Waisman, Dina.

1979-08-01

Distribution of fissions in a UO 2 rod has been measured by means of solid state detectors. Mica muscovite and Makrofol-N detectors were used in the experiment. The merits of mica muscovite relative to the Makrofol-N for the detection of fission fragments have been verified. However both fission track detectors closely agree (0,5%) in the final fission distribution of the UO 2 rod. Sensitivity of the detectors shows to be linear in the range between 50.000and 360.000 fission tracks per square centimeter. Due to the high spatial resolution this method is better than any other technique. Determination were made in UO 2 pellets similar to the fuel element of the Atucha reactor. The average fission rate in the rod has been measured within 0,8% error, and provides an accurate determination for the distribution of fissions in the rod wich is needed for the determination of energy liberated per fission in the natural uranium rod.(author) [es

Nuclear and radiation safety of the centralized spent fuel storage facility in Ukraine

International Nuclear Information System (INIS)

Grigorash, O.V.; Dibach, O.M.; Panchenko, A.V.; Shugajlo, Ol-r P.; Kovbasenko, YU.P.; Vishemyirskij, M.P.; Bogorad, V.I.; Belykh, D.O.; Shendrovich, V.Ya.

2017-01-01

The paper presents the analysis of ensuring nuclear and radiation safety in the management of spent nuclear fuel at the Centralized SFSF and activities planned for Centralized SFSF life cycle stages. There are results of comparing requirements of U.S. regulatory documents used by the HOLTEC Company to design Centralized SFSF equipment staff with relevant requirements of Ukrainian regulations, results based on analysis of the most important factors of Centralized SFSF safety (strength and reliability, nuclear safety, thermal regimes and biological protection) and verified expert calculations of the SSTC NRS. The paper includes issues to be considered in further implementation of Centralized SFSF project.

Conceptual evaluation of type B(U) casks for the nuclear power plants of Argentina

International Nuclear Information System (INIS)

Florido, P.C.; Isnardi, E.R.

1993-01-01

In Argentina two different nuclear power plants are in operation, Atucha I (PHWR-Siemens) and Embalse (PHWR-CANDU). Thus two very different fuel elements could be potentially transported. In order to optimize the research and development needed for the design and construction of the cask, the cost-benefit and flexibility of the engineering solutions are studied, for the two fuel elements. Different casks, for both types of existing fuel elements (Atucha I and Embalse), for different burnup-levels (regarding the advanced fuel cycle available), decay times, distances, and transported weight were studied. Three materials for shielding were used: uranium lead and steel. Only transport by road was considered, due to the reduced availability of the train. In this stage (conceptual design) small, easy and fast computer programs should be used. The principal issues that have to be fixed are shielding properties, thermal effects and mechanical behavior. As a result of the evaluation, different options for the casks were founded, as well as the importance of different parameters and the effect of two different designs of fuel elements. (author)

First-order effects of a nuclear moratorium in Central Europe

International Nuclear Information System (INIS)

Messner, S.; Strubegger, M.

1986-12-01

An energy supply model developed at IIASA previously is used to investigate the consequences of a hypothetical nuclear power phaseout in Central Europe. It is assumed that no new nuclear power plants will be built in Central Europe after 1990 but the existing ones will be used for a planned lifetime of 25 years. Energy-specific consequences, import dependence, emissions, energy prices and investments from the energy sector are considered. (G.Q.)

The innovation of nuclear science and technology supporting for the central plains economic zone construction

International Nuclear Information System (INIS)

Yang Xiaowei

2014-01-01

This paper discusses the nuclear agronomy support for the central plains economic zone construction, radiation chemical new material support for the central plains economic zone construction, nuclear medical support for the central plains economic zone construction, nuclear instrument and meter industry support for the central plains economic zone construction and the development trend of related disciplines. (author)

Nuclear Safety in Central and Eastern Europe

International Nuclear Information System (INIS)

2001-04-01

Nuclear safety is one of the critical issues with respect to the enlargement of the European Union towards the countries of Central and Eastern Europe. In the context of the enlargement process, the European Commission overall strategy on nuclear safety matters has been to bring the general standard of nuclear safety in the pre-accession countries up to a level that would be comparable to the safety levels in the countries of the European Union. In this context, the primary objective of the project was to develop a common format and general guidance for the evaluation of the current nuclear safety status in countries that operate commercial nuclear power plants. Therefore, one of the project team first undertakings was to develop an approach that would allow for a consistent and comprehensive overview of the nuclear safety status in the CEEC, enabling an equal treatment of the countries to be evaluated. Such an approach, which did not exist, should also ensure identification of the most important safety issues of the individual nuclear power plants. The efforts resulted in the development of the ''Performance Evaluation Guide'', which focuses on important nuclear safety issues such as plant design and operation, the practice of performing safety assessments, and nuclear legislation and regulation, in particular the role of the national regulatory body. Another important aspect of the project was the validation of the Performance Evaluation Guide (PEG) by performing a preliminary evaluation of nuclear safety in the CEEC, namely in Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, and Slovenia. The nuclear safety evaluation of each country was performed as a desktop exercise, using solely available documents that had been prepared by various Western institutions and the countries themselves. Therefore, the evaluation is only of a preliminary nature. The project did not intend to re-assess nuclear safety, but to focus on a comprehensive summary

Commissioning of the laboratory of Atucha II NPP. Implementation and optimization of analytical techniques, quality aspects

International Nuclear Information System (INIS)

Schoenbrod, Betina; Quispe, Benjamin; Cattaneo, Alberto; Rodriguez, Ivanna; Chocron, Mauricio; Farias, Silvia

2012-09-01

Atucha II NPP is a Pressurized Vessel Heavy Water Reactor (PVHWR) of 740 MWe designed by SIEMENSKWU. After some years of delay, this NPP is in advanced construction state, being the beginning of commercial operation expected for 2013. Nucleoelectrica Argentina (N.A.S.A.) is the company in charge of the finalization of this project and the future operation of the plant. The Comision Nacional de Energia Atomica (C.N.E.A.) is the R and D nuclear institution in the country that, among many other topics, provides technical support to the stations. The Commissioning Chemistry Division of CNAII is in charge of the commissioning of the demineralization water plant and the organization of the chemical laboratory. The water plant started operating successfully in July 2010 and is providing the plant with nuclear grade purity water. Currently, in the conventional ('cold') laboratory several activities are taking place. On one hand, analytical techniques for the future operation of the plant are being tested and optimized. On the other hand, the laboratory is participating in the cleaning and conservation of the different components of the plant, providing technical support and the necessary analysis. To define the analytical techniques for the normal operation of the plant, the parameters to be measured and their range were established in the Chemistry Manual. The necessary equipment and reagents were bought. In this work, a summary of the analytical techniques that are being implemented and optimized is presented. Common anions (chloride, sulfate, fluoride, bromide and nitrate) are analyzed by ion chromatography. Cations, mainly sodium, are determined by absorption spectrometry. A UV-Vis spectrometer is used to determine silicates, iron, ammonia, DQO, total solids, true color and turbidity. TOC measurements are performed with a TOC analyzer. To optimize the methods, several parameters are evaluated: linearity, detection and quantification limits, precision and

Full scale dynamic tests of Atucha II NPP

International Nuclear Information System (INIS)

Konno, T.; Alvarez, L.M.; Ceballos, M.A.; Prato, C.A.; Uchiyama, S.; Godoy, A.R.

1995-01-01

This paper summarizes the main results of a series of dynamic tests of the reactor building of Atucha II NPP performed to determine the dynamic properties of its massive structure deeply embedded in Quaternary soil deposits. Tests were performed under two different types of loading conditions: Steady state harmonic loads imposed by mechanical exciters and impulsive loads induced by dropping a weight on the ground surface in the vicinity. Natural frequencies and mode shapes were identified and the associated modal damping ratios were experimentally determined. Numerical analyses of the reactor building-foundation system by two different F.E. models were performed. One of them, based on an axisymmetric representation of the soil-structure system, was used to simulate the steady state vibration tests and to calculate the dynamic stiffness of the foundation slab and soil layers for comparison with those experimentally obtained. The other, a 3-D F.E. model of the superstructure, was used to assess the natural frequencies and mode shapes obtained from the tests, representing dynamic stiffness of the foundation with stiffness coefficients derived both from the tests and from the axisymmetric F.E. model. Good agreement of the natural frequencies given by two types of tests was generally found, with the largest difference between them in the fundamental frequency of the building. Estimates of modal damping derived from the tests showed significant differences depending on the technique used to calculate them. For the fundamental mode damping was found to be 23-42 %, gradually decreasing with frequency to 2-4 % for around 10 Hz. (author)

Full scale dynamic tests of Atucha II NPP

International Nuclear Information System (INIS)

Prato, C.A.; Ceballos, M.A.; Konno, T.; Uchiyama, S.; Alvarez, L.M.; Godoy, A.R.

1998-01-01

This paper summarizes the main results of a series of dynamic tests of the reactor building of Atucha II NPP performed to determine the dynamic properties of its massive structure deeply embedded in quaternary soil deposits. Tests were performed under two different types of loading conditions: steady state harmonic loads imposed by mechanical exciters and impulsive loads induced by dropping a weight on the ground surface in the vicinity. Natural frequencies and mode shapes were identified and the associated modal damping ratios were experimentally determined. Numerical analyses of the reactor building-foundation system by two different F.E. models were performed. One of them, based on an axisymmetric representation of the soil-structure system, was used to simulate the steady state vibration tests and to calculate the dynamic stiffness of the foundation slab and soil layers for comparison with those experimentally obtained. The other, a 3-D F.E. model of the superstructure, was used to assess the natural frequencies and mode shapes obtained from the tests, representing dynamic stiffness of the foundation with stiffness coefficients derived both from the tests and from the axisymmetric F.E. model. Good agreement of the natural frequencies given by two types of tests were generally found, with the largest difference between them in the fundamental frequency of the building. Estimates of modal damping derived from the tests showed significant differences depending on the technique used to calculate them. For the fundamental mode, damping was found to be 23-42%, gradually decreasing with frequency to 2-4% for ∝10 Hz. (orig.)

A challenging task: cleaning and repairing at nuclear power plant ATUCHA I (CAN-I) the primary's moderators cooling circuits heat exchangers

International Nuclear Information System (INIS)

Amaya, D.; Alaniz, A.; Bernasconi, R.

2005-01-01

A set of automatic and semiautomatic machines and tools were designed for the accomplishment of remotely controlled works in high radiation fields on the ATUCHA-I moderator heat exchangers. The object of this equipment is to carry out works related to the cleaning, inspection and eventual blocking of the heat exchanger's tubes. Due to the special characteristics of the area, such as difficult access, not much space and high dose rates, the remote operation of highly trained and specialized personnel with specially designed tools, is mandatory. The Principal operations consist of: 1. Equipment manually taken to the area by specialized personnel. 2. Remote cutting the bolting and cutting and re-weld seals with custom designed equipment. 3. Remote cutting and re-weld piping connections with equipment on customized tracks, special supports, drives and commands. 4. Remote cleaning, leak testing, machining and plugging of the tube sheets with a custom-made master-slave/Cartesian robotic manipulators. 5. Monitoring with video cameras and lighting systems incorporated into the equipment. 6. Ands others task as piping stabilization, supporting and moving flanges, re-alignment of seals and pipes, etc. This paper describes the entire development of this project, starting from the initial work plan to the completion of the first on-site work carried out at the facility. Including descriptions, drawings and pictures of the custom designed equipment, description of the performed works and comparisons between the actual doses and estimated manual operation doses. (authors)

Prospects for a nuclear-weapon-free zone in Central Asia

International Nuclear Information System (INIS)

Potter, W.C.

1997-01-01

This paper examines the concept of a Nuclear-Weapon-Free Zone (NWFZ) as an approach to nuclear nonproliferation with special reference to Central Asia . 20 More specifically, it describes the evolution of a NWFZ in the region, the potential benefits of a zone, the principal obstacles in the path of its implementation, and the practical steps that need to be taken if a NWFZ in Central Asia is to be realized. The paper concludes that a NWFZ in Central Asia, as with prior NWFZ, would likely lead to advances in the application of an important nonproliferation approach. One innovative aspect of the zone in Central Asia might be its treatment of environmental issues. Although it will not be a simple process to rally support from all of the P-5 states for a new NWFZ, all countries of Central Asia - as well as global community of nations - should profit from creation of a zone which reinforces the international nonproliferation regime improves prospects for political and economic stability in a region of growing importance

Nuclear spin noise in the central spin model

Science.gov (United States)

Fröhling, Nina; Anders, Frithjof B.; Glazov, Mikhail

2018-05-01

We study theoretically the fluctuations of the nuclear spins in quantum dots employing the central spin model which accounts for the hyperfine interaction of the nuclei with the electron spin. These fluctuations are calculated both with an analytical approach using homogeneous hyperfine couplings (box model) and with a numerical simulation using a distribution of hyperfine coupling constants. The approaches are in good agreement. The box model serves as a benchmark with low computational cost that explains the basic features of the nuclear spin noise well. We also demonstrate that the nuclear spin noise spectra comprise a two-peak structure centered at the nuclear Zeeman frequency in high magnetic fields with the shape of the spectrum controlled by the distribution of the hyperfine constants. This allows for direct access to this distribution function through nuclear spin noise spectroscopy.

Radiological impact of the management of radioactive waste arising from the Argentine Nuclear Programme

International Nuclear Information System (INIS)

Migliori de Beninson, A.; Cancio, D.

1984-01-01

The Argentine nuclear programme, as it stands at present, provides for the construction of four nuclear power plants in addition to those of Atucha I and Embalse and for the establishment of such fuel cycle facilities as are required to supply all of these plants. This paper evaluates the radiological impact (collective dose commitment) expected from the management of the radioactive wastes arising in the facilities mentioned above throughout the useful life of the reactors. The maximum individual doses to be expected as a result of the planned high-level-waste repository are also estimated. The evaluations presented are partly specific to the sites under consideration, but they also include estimates of the total collective dose commitments resulting from the management of radioactive waste under the Argentine nuclear programme. (author)

U.S. Central Station Nuclear Power Plants: operating history

International Nuclear Information System (INIS)

1976-01-01

The information assembled in this booklet highlights the operating history of U. S. Central Station nuclear power plants through December 31, 1976. The information presented is based on data furnished by the operating electric utilities. The information is presented in the form of statistical tables and computer printouts of major shutdown periods for each nuclear unit. The capacity factor data for each unit is presented both on the basis of its net design electrical rating and its net maximum dependable capacity, as reported by the operating utility to the Nuclear Regulatory Commission

CAE meteorological database for the PC CREAM program. Atmospheric dilution factor in different points of the CAE (Centro Atomico Ezeiza) and of the argentine nuclear power plants

International Nuclear Information System (INIS)

Amado, Valeria A.

2007-01-01

In the first part of this work, the EZEIZA.MET file, with the meteorological database of the surroundings of the Ezeiza Atomic Center, is prepared and incorporated into the library of the PC CREAM program. This program was developed by the National Radiological Protection Board and the European Union. Information provided by the National Meteorological Service was used, corresponding to the Ezeiza Meteorological Station during the period 1996-2005. In the second part, a methodology to estimate the atmospheric dilution factor at a point using the PLUME module of the PC CREAM, is presented. The developed methodology was used to estimate the dilution factor at points close to the Ezeiza Atomic Center and nuclear power plants Atucha I and Embalse. The developed methodology was used to estimate the dilution factor at points close to the Ezeiza Atomic Center and nuclear power plants Atucha I and Embalse. In the first case the file with the generated meteorological database is used, whereas for the nuclear power plants the already existing ATUCHALO.MET and EMBALSE.MET files are used. The dilution factors obtained are compared with those obtained in previous work. The proposed methodology is a useful tool to estimate the dilution factors in a simple and systematic way, and simultaneously allows the update of the meteorological information used in the estimations. (author) [es

Accounting for and control of nuclear material at the Central Institute of Nuclear Research, Rossendorf

International Nuclear Information System (INIS)

Heidel, S.; Rossbander, W.; Helming, M.

1983-01-01

A survey is given of the system of accounting for and control of nuclear material at the Central Institute for Nuclear Research, Rossendorf. It includes 3 material balance areas. Control is implemented at both the institute and the MBA levels on the basis of concepts which are coordinated with the national control authority of the IAEA. The system applied enables national and international nuclear material control to be carried out effectively and economically at a minimum of interference with operational procedures. (author)

Nuclear Research and Development Institutes in Central and Eastern Europe

International Nuclear Information System (INIS)

2009-06-01

The science and technology (S and T) sector is faced today with complex and diverse challenges. National science budgets are under pressure, and many countries are changing how research and development (R and D) is funded, reducing direct subsidies and introducing competition for both governmental and alternative sources of revenue. On the other hand, the transition toward knowledge-based economies is creating new opportunities in the S and T sector as governments look to it to foster economic growth through innovation. A number of countries in Central and Eastern Europe have recently joined the European Union (EU) which has defined the Lisbon Strategy to create a 'knowledge triangle' of research, education and innovation to underpin the European economic and social model, and economic growth. This strategy seeks to increase investment in science and technology across the EU to a target of 3% of GDP by 2010, with two-thirds of funds coming from the private sector. By comparison, funding for R and D in most Central and Eastern European countries is only around 1% GDP, of which about 90% is provided by the governments. R and D has become more international, reflecting a more interdependent and globalized world. R and D progress is not only of interest to individual countries but also tries to respond to the needs of a broader society. Governments still maintain national networks, but increasingly emphasize international cooperation, both to avoid duplication of expensive infrastructure, and because scientific excellence requires an exchange of ideas and cooperation that crosses borders. These challenges and opportunities directly impact the research and development institutes (RDIs), including the nuclear RDIs. It is important for the nuclear RDIs to take account of these trends in the broader S and T sector in their vision and strategy. Several nuclear RDIs have become very successful, but others are struggling to adapt. The challenges have been particularly severe

Materials qualification for nuclear power plants

International Nuclear Information System (INIS)

Braconi, F.

1987-01-01

The supply of materials to be used in the fabrication of components submitted to pressure destined to Atucha II nuclear power plant must fulfill the quality assurance requirements in accordance with the international standards. With the aim of promoting the national participation in CNA II, ENACE had the need to adapt these requirements to the national industry conditions and to the availability of official entities' qualification and inspection. As a uniform and normalized assessment for the qualification of materials did not exist in the country, ENACE had to develop a materials suppliers qualification system. This paper presents a suppliers qualification procedure, its application limits and the alternative procedures for the acceptance of individual stock and for the stock materials purchase. (Author)

A level III PSA for the inherently safe CAREM-25 nuclear power station

International Nuclear Information System (INIS)

Baron, Jorge H.; Nunez McLeod, J.; Rivera, S.S.

2000-01-01

A Level III PSA has been performed for the inherently safe CAREM-25 nuclear power station, as a requirement for licensing according to argentinian regulations. The CAREM-25 project is still at a detailed design state, therefore only internal events have been considered, and a representative site has been assumed for dose estimations. Several conservative hypothesis have been formulated, but even so an overall core melt frequency of 2.3E -5 per reactor year has been obtained. The risk estimations comply with the regulations. The risk values obtained are compared to the 700MW(e) nuclear power plant Atucha II PSA result, showing an effective risk reduction not only in the severe accident probability but alto in the consequence component of the risk estimation. (author)

Application of the neutron noise analysis technique in nuclear power plants

International Nuclear Information System (INIS)

Lescano, Victor H.; Wentzeis, Luis M.

1999-01-01

Using the neutron noise analysis in nuclear power plants, and without producing any perturbation in the normal operation of the plant, information of the vibration state of the reactor internals and the behavior of the operating conditions of the reactor primary circuit can be obtained. In Argentina, the neutron noise analysis technique is applied in customary way in the nuclear power plants Atucha I and Embalse. A database was constructed and vibration frequencies corresponding to different reactor internals were characterized. Reactor internals with particular mechanical vibrations have been detected and localized. In the framing of a cooperation project between Argentina and Germany, we participated in the measurements, analysis and modelisation, using the neutron noise technique, in the Obrigheim and Gundremmingen nuclear power plants. In the nuclear power plant Obrigheim (PWR, 350 M We), correlations between the signals measured from self-power neutron detectors and accelerometers located inside the reactor core, were made. In the nuclear power plant Gundremmingen (BWR, 1200 M We) we participated in the study of a particular mechanical vibration detected in one of the instrumentation tube. (author)

De "átomos para la paz" a los reactores de potencia: Tecnología y política nuclear en la Argentina (1955-1976)

OpenAIRE

Hurtado de Mendoza, Diego

2005-01-01

Durante el período 1955-76, el programa nuclear argentino se integró a la arena internacional; su Comisión Nacional de Energía Atómica construyó cuatro reactores de investigación, adquirió a una empresa alemana y puso en marcha el primer reactor de potencia Atucha I, y compró a una empresa canadiense un segundo reactor de potencia. En este artículo se examinan estos desarrollos en relación con el contexto político local y con el panorama nuclear internacional. En particular, se analizan la po...

Perspectives for nuclear electricity in central Africa

International Nuclear Information System (INIS)

Wa Kalenga, M.

1977-01-01

The paper analyses the energetic system of Central African countries and evaluate the projected global demand of energy. It compares the economy of the nuclear solution for the satisfaction of future demand versus other forms of energy available in the region. It appreciates finally the role that the countries involved can play in the fuel cycle (supply of raw material, possibilities of fuel enrichment) [fr

Perspectives for nuclear electricity in Central Africa

International Nuclear Information System (INIS)

Wa Kalenga, M.

1977-01-01

The paper analyses the energy system of the Central African countries and evaluates the projected global demand of energy. It compares the economy of the nuclear solution for satisfying future demands in relation to other forms of energy available in the region. Finally, it discusses the role that the countries involved can play in the fuel cycle (supply of raw material, possibilities of fuel enrichment). (author)

Safeguards at the Central Institute for Nuclear Research at Rossendorf/GDR

International Nuclear Information System (INIS)

Helming, M.; Rehak, W.; Schillert, B.

1989-01-01

Experience in the implementation of domestic and international safeguards at the Central Institute for Nuclear Research at Rossendorf is reported covering the following topics: overview of the main nuclear installations belonging to the Institute; structure of its material balance areas; responsibilities for the different aspects of accounting for and control of nuclear material at facility level; the various types of nuclear materials handled and their flow, accessibility and strategic significance; the assessment of IAEA safeguards effectiveness. 2 tabs., 2 figs. (author)

The industrial nuclear fuel cycle in Argentina

International Nuclear Information System (INIS)

Koll, J.H.; Kittl, J.E.; Parera, C.A.; Coppa, R.C.; Aguirre, E.J.

1977-01-01

The nuclear power program of Argentina for the period 1976-85 is described, as a basis to indicate fuel requirements and the consequent implementation of a national fuel cycle industry. Fuel cycle activities in Argentina were initiated as soon as 1951-2 in the prospection and mining activities through the country. Following this step, yellow-cake production was initiated in plants of limited capacity. National production of uranium concentrate has met requirements up to the present time, and will continue to do so until the Sierra Pintada Industrial Complex starts operation in 1979. Presently, there is a gap in local production of uranium dioxide and fuel elements for the Atucha power station, which are produced abroad using Argentine uranium concentrate. With its background, the argentine program for the installation of nuclear fuel cycle industries is described, and the techno-economical implications considered. Individual projects are reviewed, as well as the present and planned infrastructure needed to support the industrial effort [es

30 years of Central Institute for Nuclear Research at Rossendorf

International Nuclear Information System (INIS)

Scheler, W.; Flach, G.; Hennig, K.; Collatz, S.; Muenze, R.; Baldeweg, F.

1986-10-01

A celebration and a scientific colloquium dedicated the 30th anniversary of the foundation of the Central Institute for Nuclear Research (CINR) of the GDR Academy of Sciences were held on January, 23rd and 24th, '86 at Rossendorf. The speaches and lectures given by the president of the GDR Academy of Sciences and by scientists of the CINR dealt with problems of policy of science, history of the CINR, nuclear methods, microelectronics, nuclear energy research, development and production of radioisotopes and scientific instruments. (author)

Experimental and inspection facilities in post-irradiation of spent fuel pools for the analysis of the behaviour of nuclear fuels in power reactors

International Nuclear Information System (INIS)

Ruggirello, G.; Zawerucha, A.

1992-01-01

Since the beginning of the Atomic Nuclear Reactors (PHWR) Atucha I and Embalse in Argentine are employed different techniques for the knowing of the fuel bundles performances. It is detailed the facilities on post-irradiation examination. The techniques described are: online measurements, visual inspections, identifications of defective fuels and rods assemblies in spent fuel pools. This controls have made possible the feed-back to the manufactory process and the changes in the manufactory quality controls. (author)

Spent fuel management of NPPs in Argentina

International Nuclear Information System (INIS)

Alvarez, D.E.; Lee Gonzalez, H.M.

2010-01-01

There are two Nuclear Power Plants in operation in Argentina: 'Atucha I' (unique PHWR design) in operation since 1974, and 'Embalse' (typical Candu reactor) which started operation in 1984. Both NPPs are operated by 'Nucleoelectrica Argentina S.A' which is responsible for the management and interim storage of spent fuel till the end of the operative life of the plants. A third NPP, 'Atucha II' is under construction, with a similar design of Atucha I. The legislative framework establishes that after final shutdown of a NPP the spent fuel will be transferred to the 'National Atomic Energy Commission', which is also responsible for the decommissioning of the Plants. In Atucha I, the spent fuel is stored underwater, until another option is implemented meanwhile in Embalse the spent fuel is stored during six years in pools and then it is moved to a dry storage. A decision about the fuel cycle back-end strategy will be taken before year 2030. (authors)

Communication system and spectral analysis for Ge-Li and GeHp detectors; Sistema de comunicaciones y analisis de espectros para detectores Ge-Li y GeHp

Energy Technology Data Exchange (ETDEWEB)

Fernandez, J; Castano, P; Bonino, A D; Righetti, M A

1991-12-31

An integral communication and spectral analysis system (SICADE) was developed and implemented to satisfy the need to optimize and automate the measurement system used in Atucha I nuclear power plant for the activity in the primary loop`s water extracted by the TV system. The importance of these measurements is based on the fact that from the spectrometric analysis of the samples extracted, the Iodines-GN and Iodines-Iodines relations, which allow to detect the presence of deficient fuel elements, are calculated. The system developed is based on two modules integrated in a unique set commanded by the operators through the screen dialogue. (Author). [Espanol] Dada la necesidad de optimizar y automatizar el sistema de medicion utilizado en la Central Nuclear Atucha I para la actividad en el agua del circuito primario extraida a traves del sistema TV se desarrollo e implemento un sistema integral de Comunicacion y Analisis de espectros (SICADE). La importancia de estas mediciones radica en el hecho que del analisis espectrometrico de las muestras extraidas se calculan las relaciones entre Iodos-GN e Iodos-Iodos que permiten detectar la presencia de elementos combustibles fallados. El sistema desarrollado esta basado en dos modulos integrados en un unico conjunto comandado por el operador a traves del dialogo por pantalla. (Autor).

Study on alternatives of inertisation of nuclear power plant containment

International Nuclear Information System (INIS)

Baron, J.H.; Zarate, S.M.

1998-01-01

In the course of a severe accident in a nuclear power plant, the hydrogen generation and other flammable gases, during the core degradation phase and the interaction corium-concrete, could produce the failure of the containment by overpressure of by combustion. According to the analysis of the potential effects of hydrogen evolution, following accidents inside the containment trough a Defense-in depth principle, which attempts to assure that the containment must not fail catastrophically, two techniques have been evaluated: a: Inertisation pre-accident and b: Inertisation post-accident. The technique of inertisation pre-accident consists in replacing the air of the containment with inert-gas like nitrogen (N 2 ) or carbon dioxide (CO 2 ) during the normal operation. The inertisation post-accident in combination with early venting system consists in replacing the air of the containment with inert-gas like nitrogen (N 2 ) or carbon dioxide (CO 2 ), immediately after the beginning of the accident, while the radioactivity is still negligible inside the containment. A system of inertisation pre-accident with nitrogen is used on BWR Mark I and Mark II. Investigations on the inertisation post-accident of the containment atmosphere during severe accidents have been carried out with different objectives from principles of the decade of 1980. Studies concerning hydrogen problem for the nuclear power plants Atucha I and CAREM-25 have permitted to know that the hydrogen generation during an accidental sequence with core degradation, would result important, being able to arrive to form explosive mixtures. In the present work, the applicability of the techniques of inertisation is analyzed for the containment of the Atucha I and CAREM-25, considering the particular design characteristics of these plants. (author) [es

Federal Republic of Germany: Prospects for nuclear energy from 1972-1992

Energy Technology Data Exchange (ETDEWEB)

Hilger-Haunschild, H [Federal Ministry for Education and Science, Bonn (Germany)

1972-07-01

The number of nuclear power stations, both built and planned, in the Federal Republic of Germany, bears witness to what has been achieved so far. At present, nuclear power stations in operation generate a total of about 2000 MWe, while power stations with a total capacity for a further 10 000 MWe are under construction. The first export orders demonstrate the competitiveness of the German nuclear power industry -power stations are now being built by West German firms at Atucha in Argentina, Borselle in the Netherlands, and Zwentendorf in Austria. Because of parallel technological advances reached by the world's major industrialized nations, and the large funds necessary for further nuclear development, international cooperation is increasingly important. The federal Government therefore follows a policy of joint-development projects, particularly within a European framework. The SNR 300 fast breeder reactor, which is to be constructed with Belgium and the Netherlands, and the development of the gas centrifuge technique being carried out with the Netherlands and the United Kingdom, are excellent examples of this policy.

Central depression in nucleonic densities: Trend analysis in the nuclear density functional theory approach

Science.gov (United States)

Schuetrumpf, B.; Nazarewicz, W.; Reinhard, P.-G.

2017-08-01

Background: The central depression of nucleonic density, i.e., a reduction of density in the nuclear interior, has been attributed to many factors. For instance, bubble structures in superheavy nuclei are believed to be due to the electrostatic repulsion. In light nuclei, the mechanism behind the density reduction in the interior has been discussed in terms of shell effects associated with occupations of s orbits. Purpose: The main objective of this work is to reveal mechanisms behind the formation of central depression in nucleonic densities in light and heavy nuclei. To this end, we introduce several measures of the internal nucleonic density. Through the statistical analysis, we study the information content of these measures with respect to nuclear matter properties. Method: We apply nuclear density functional theory with Skyrme functionals. Using the statistical tools of linear least square regression, we inspect correlations between various measures of central depression and model parameters, including nuclear matter properties. We study bivariate correlations with selected quantities as well as multiple correlations with groups of parameters. Detailed correlation analysis is carried out for 34Si for which a bubble structure has been reported recently, 48Ca, and N =82 , 126, and 184 isotonic chains. Results: We show that the central depression in medium-mass nuclei is very sensitive to shell effects, whereas for superheavy systems it is firmly driven by the electrostatic repulsion. An appreciable semibubble structure in proton density is predicted for 294Og, which is currently the heaviest nucleus known experimentally. Conclusion: Our correlation analysis reveals that the central density indicators in nuclei below 208Pb carry little information on parameters of nuclear matter; they are predominantly driven by shell structure. On the other hand, in the superheavy nuclei there exists a clear relationship between the central nucleonic density and symmetry energy.

Staff Organization in Nuclear Power Stations; Organisation du personnel des centrales nucleaires; Organizatsiya personala na atomnykh ehlektrostantsiyakh; Organizacion del personal de las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Scuricini, G. B. [Comitato Nazionale Energia Nucleare, Roma (Italy)

1963-10-15

This paper deals with the organization of operating and maintenance staff at nuclear power stations in Italy and manpower variations, either because the plants themselves differ or are organized in some special way. Staff doing jobs for which a specific training is required are given special consideration in the paper. (author) [French] Dans le memoire, on examine l'organisation du personnel d'exploitation et d'entretien des centrales nucleaires italiennes et les differences existant dans les effectifs, differences dues soit aux caracteristiques des centrales memes, soit aux particularites d'organisation des entreprises. Le personnel charge de fonctions determinees pour lesquelles un entrainement special est requis, fait l'objet d'une attention particuliere. (author) [Spanish] En la memoria se examina la organizacion del personal de explotacion y conservacion de las centrales nucleares italianas y las diferencias que existen entre sus efectivos, diferencias que se deben a las caracteristicas de las mismas centrales o a las particularidades de organizacion de las empresas. El autor dedica especial atencion al personal encargado de funciones que requieren una formacion profesional especial. (author) [Russian] Issleduyutsya voprosy organizatsii personala, zanimayushchegosya ehkspluatatsiej ital'yanskikh atomnykh ehlektrostantsij i ukhodom za nimi, a takkhe razlichiya v sostave personala, vytekayushchie libo iz kharakternykh osobennostej samikh stantsij, libo iz osobennostej organizatsii predpriyatij. Osoboe vnimanie udelyaetsya personalu, kotoromu porucheny opredelennye funktsii, trebuyushchie spetsial'noj pod go tovki. (author)

JPRS Report Nuclear Developments

Science.gov (United States)

1988-09-02

cracks in Atucha I were detected during the administration of Eng Alberto Constantini. Last year Constantini resigned as CNEA president due to...days, Finance Minister Mailson da Nobrega, Mines and Energy Minis- ter Aureliano Chaves, and Planning Minister Joao Batista de Abreu should be

The CNA-1 (Nuclear Power Plant Atucha-1) QK-01 repairing project

International Nuclear Information System (INIS)

Pizzaferri, J.C.; Cabot, P.

1997-01-01

The repair/maintenance of the CNA-1 QK-01 Moderator Cooler will be a leading case of the repair of a class 1 nuclear component in a high radiation environment; utilizing for the work, sophisticated remotely operated equipment. This paper describes the component, the repair-maintenance objective, and the equipment-procedures developed for the intervention. (author) [es

Dangerous liaisons: Western involvement in the nuclear power industry of central and eastern Europe

International Nuclear Information System (INIS)

1992-12-01

The state of the nuclear industry in central and eastern Europe is an issue of global concern. However, despite all the political talk and corporate hype since the collapse of communist regimes in the region, this study demonstrates that little has so far been done to change the situation. Moreover, the limited level of finance and support which has been offered has tended to support the expansion of nuclear power programmes in central and eastern Europe, rather than address immediately safety concerns relating to existing nuclear reactors and develop more environmentally acceptable and economically efficient energy systems. (author)

Annual progress report on nuclear data 1983 of the Central Bureau for Nuclear Measurements, Geel (Belgium)

International Nuclear Information System (INIS)

1984-05-01

In this progress report of the Central Bureau for Nuclear Measurements at Geel (Belgium) researches related to neutron data and to non-neutron nuclear data are gathered. Neutron data are essentially related to cross-section measurements: for instance, concerning actinides, structural materials as Cr and Fe, fission products. Some studies are classified as concerning standard neutron data. Underlying physics is no forgotten neither than equipment (linear accelerator). Non-neutron nuclear data is concerned essentially with decay studies. Some compilations and evaluations are also given. Improvement of measurement and source preparation techniques is a part of this section

Central Scientific and Research Institute of Nuclear Information as the branch centre of information on nuclear science and engineering

International Nuclear Information System (INIS)

Arkhangel'skij, I.A.; Sokolov, D.D.; Kalinin, V.F.; Nikiforov, V.S.

1982-01-01

The main tasks are considered in the scope of the Central Scientific-Research Institute for Information and Technological and Economic Studies on Nuclear Science and Technology. (TsNIIAtominform). The institute coordinates scientific research and information activity of information agencies of all the USSR organizations engaged in nuclear science and technology, excercises a centralized completion of their libraries, develops and puts into practice the most progressive methods for the information servicing. The institute is a national INIS center of the USSR. Here a system for the automatic information dissemination has been successfully elaborated and employed. Much of the institute activity is given to the estimation and analysis of information and to the determination of tendencies in the nuclear science and technology development. A conclusion is drawn to the effect that TsNIIAtominform, within 15 years of its existence, has formed as a center ensuring functioning of the system of scientific and technical information on nuclear science and technology

Conceptual design of interim storage facility for CNAI

International Nuclear Information System (INIS)

Fuenzalida Troyano, Carlos S.; Bergallo, Juan E.; Nassini, Horacio E.P.; Blanco, Anibal; Delmastro, Dario F.

2007-01-01

The reduced storage capacity available in the two spent fuel pools of argentine PHWR Atucha-1 power plant, the current plans for extending the reactor operation beyond its design lifetime, and the government decision on Atucha-2 NPP construction ending, have motivated the evaluation of a dry storage option for the interim management of spent fuel assemblies. Two different designs are presently being analyzed by an expert working group, from both technical and economical points of views. Authors are proposing a modular system consisting of an arrangement of reinforced concrete structures into which welded metallic canisters loaded with 37 spent fuel assemblies each stored in horizontal position. The reinforced concrete module is designed to provide the necessary physical protection and biological shielding to the loaded canisters during long-term storage, as well as passive means to remove the spent fuel decay heat by a combination of radiation, conduction and natural air convection. In this works are presented advances in the conceptual designs for a spent nuclear fuel system to Atucha I nuclear power plant. (author) [es

Argentina

International Nuclear Information System (INIS)

Tanis, S.; Ramberg, B.

1990-01-01

Argentina has embarked on an ambitious domestic nuclear research and energy program. The venture promises to provide the nation with the infrastructure to play an important role in the nuclear export market in the years ahead. Buenos Aires built its program on a foundation of international support and assistance that overlay an emerging sophisticated industrial and scientific establishment. The foreign contribution sensitized Argentina to opportunities in the global market. This paper reports that Argentina operates two heavy-water/natural uranium reactors, Atucha I and Embalse. Producing, respectively, 320 MW(e) and 600 MW(e), they supply roughly 10 percent of the country's electricity. With a capacity factor of 84 percent, Atucha I is among the best operated plants in the world. Plans call for a third, 745 MW(e) power plant, Atucha II, to go on line in the early 1990s. During this period, construction also may begin on three 300 MW(e) plants, although the country's foreign indebtedness plus cost overruns in earlier construction will place a heavy burden on these plans

Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

Energy Technology Data Exchange (ETDEWEB)

Duran, Felicia Angelica [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.; Waymire, Russell L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.

2013-10-01

Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

International Nuclear Information System (INIS)

Duran, Felicia Angelica; Waymire, Russell L.

2013-01-01

Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

Nuclear Research Center Karlsruhe, Central Safety Department. Annual report 1992

International Nuclear Information System (INIS)

Koelzer, W.

1993-05-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, biophysics of multicellular systems, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1992 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

EFFECT OF CENTRAL MASS CONCENTRATION ON THE FORMATION OF NUCLEAR SPIRALS IN BARRED GALAXIES

International Nuclear Information System (INIS)

Thakur, Parijat; Jiang, I.-G.; Ann, H. B.

2009-01-01

We have performed smoothed particle hydrodynamics simulations to study the response of the central kiloparsec region of a gaseous disk to the imposition of nonaxisymmetric bar potentials. The model galaxies are composed of three axisymmetric components (halo, disk, and bulge) and a nonaxisymmetric bar. These components are assumed to be invariant in time in the frame corotating with the bar. The potential of spherical γ-models of Dehnen is adopted for the bulge component whose density varies as r -γ near the center and r -4 at larger radii and, hence, possesses a central density core for γ = 0 and cusps for γ>0. Since the central mass concentration of the model galaxies increases with the cusp parameter γ, we have examined here the effect of the central mass concentration by varying the cusp parameter γ on the mechanism responsible for the formation of the symmetric two-armed nuclear spirals in barred galaxies. Our simulations show that the symmetric two-armed nuclear spirals are formed by hydrodynamic spiral shocks driven by the gravitational torque of the bar for the models with γ = 0 and 0.5. On the other hand, the symmetric two-armed nuclear spirals in the models with γ = 1 and 1.5 are explained by gas density waves. Thus, we conclude that the mechanism responsible for the formation of symmetric two-armed nuclear spirals in barred galaxies changes from hydrodynamic shocks to gas density waves as the central mass concentration increases from γ = 0 to 1.5.

Instrumentation and control engineering at ENACE (Argentine Nuclear Enterprise of Electric Power Plants S.A.)

International Nuclear Information System (INIS)

Roca, J.L.; Garzon, D.

1987-01-01

This paper describes the techniques used in the project of instrumentation and control for the Atucha II nuclear power plant, from the original flow diagram of the system whose instrumentation and control is requested to the functional binary diagrams and control loops, through measurement sheets and other documentation. An account of the organization and handling of this mass of information is given, using an electronic processing system of data file for the project. A brief description of the task implied in the completing and updating of these files defines the scheme in which all the documentation development associated with a given process is included. (Author)

Fuel operation of EDF nuclear fleet presentation of the centralized organization for operational engineering at the nuclear generation division

International Nuclear Information System (INIS)

Paulin, Ph.

2006-01-01

The main feature of EDF Nuclear Fleet is the standardization, with 'series' of homogeneous plants (same equipment, fuel and operation technical documents). For fuel operation, this standardization is related to the concept of 'fuel management scheme' (typical fuel reloads with fixed number and enrichment of fresh assemblies) for a whole series of plants. The context of the Nuclear Fleet lead to the choice of a centralized organization for fuel engineering at the Nuclear Generation Division (DPN), located at UNIPE (National Department for Fleet Operation Engineering) in Lyon. The main features of this organization are the following: - Centralization of the engineering activities for fuel operation support in the Fuel Branch of UNIPE, - Strong real-time link with the nuclear sites, - Relations with various EDF Departments in charge of design, nuclear fuel supply and electricity production optimization. The purposes of the organization are: - Standardization of operational engineering services and products, - Autonomy with independent methods and computing tools, - Reactivity with a technical assistance for sites (24 hours 'hot line'), - Identification of different levels (on site and off site) to solve core operation problems, - Collection, analysis and valorization of operation feedback, - Contribution to fuel competence global management inside EDF. This paper briefly describes the organization. The main figures of annual engineering production are provided. A selection of examples illustrates the contribution to the Nuclear Fleet performance. (authors)

Development and production of nuclear valves. Forging and welding. Pt. 2

International Nuclear Information System (INIS)

Bernal Castro, J.B.; Perez, J.C.; Labonia, R.N.

1987-01-01

The first part of this work deals with the obtainment of the austenitic stainless steel DIN 1.4541 (AISI 321) stabilized titanium for Atucha II nuclear valves. The second part presented herein, continued with the development process and part of the production of the bodies' forging and valves leads. This development has been also carried out in the country and a detailed set up of the process with its corresponding Inspection and Assay Program was needed. The last part of this stage has been initiated at the welding process, so it was necessary to develop specific welding procedures to qualify them and use the equipment specially applied to this requirement. The set of assays and criteria certification for the qualifications is presented. (Author)

Reduced program of inspection by induced currents for condenser of Embalse nuclear power plant

International Nuclear Information System (INIS)

Obrutsky, L.; Mendonca, H.

1986-01-01

In this work it's presented a reduced inspection in service program by the technique of induced currents to the turbine condenser of Embalse's Power Plant (Cordoba). The authors based its elaboration on the results obtained in the exam of a small number of tubes and on experience obtained through four inspections in the condensers of Atucha I Power Plant, through mathematical models of oxygen and ammoniac distribution in both Power Plants, and its experimental verification in the case of Atucha I. This program improves the quality of inspection thereby reducing time, equipment and personnel employed. (C.M.) [pt

Application of the weld in maintenance mechanics at the Nuclear Power Station Atucha I

International Nuclear Information System (INIS)

Cosentino, R.E.

1988-01-01

The application of the 'weld procedures', in the field of activity of nuclear power is an special chapter of weld. The so called 'Nuclear Installations' are actually under control from their contruction up to their life extension operation to special control programs and quality assurance. This situation obliges the implementation of procedures to assure the fulfilment of the programs for the need to make the reparations or mechanics construction. This paper describes the considerations that has been taken into account to repare some components of the plant. The works carried out constitute applications to the TIG weld procedure. The 'lip weld' is a mechanic component required in pressurized systems subject to air pressure. (Author)

Site of the First Spanish Nuclear Power Stations; Los Emplazamientos de las Primeras Centrales Nucleares Espanolas

Energy Technology Data Exchange (ETDEWEB)

Pascual, F.; Alonso, A.; Norena, S.; Sevilla, A. [Junta de Energia Nuclear, Madrid (Spain)

1967-09-15

The authors analyse and describe the sites of three Spanish nuclear power stations: the Zorita station (153 M W (e )) with a pressurized water reactor and single containment; the Santa Marfa de Garofia station (380 MW (e)), with a boiling water reactor and containment by steam condensation; and the Vandellos station (480 MW(e)), with a graphite-moderated gas-cooled reactor and integrated design of the EDF-4 type. The first two are located in the interior of the country and the third on the Mediterranean coast. The paper discusses the normal criteria and the safety considerations governing the choice of site, and points out the influence of Spanish orography on the transport of heavy equipment and hence its repercussions on the selection of power station sites. Reference is made to the experience acquired in transporting equipment for the Z-orita plant, and an analysis of the practical difficulties encountered in applying particular safety standards to the sites of stations of different types and designs is included. As the type of reactor and its containment system affect the practical value of applying particular standards which, moreover, have to be adapted to the special features of each country, safety standards for assessing power station sites should be applied in an appropriate and flexible manner. The paper describes the geological and meteorological features of the three sites and summarizes the studies carried out in these fields. It refers particularly to the hydrological studies carried out at Zorita and Santa Maria de Garofia and describes the weather stations set up at both sites, the diffusion experiments with neutcal-buoyancy balloons at Santa Maria de Garofia, and the results of these investigations. (author) [Spanish] Se analizan y describen los emplazamientos de tres centrales nucleares espanolas: la central de Zorita, de 153 MW(e), con reactor de agua a presion y sistema de contencion simple; la central de Santa Maria de Garofia, de 380 MW

Moderator behaviour and reactor internals integrity at Atucha I NPP

International Nuclear Information System (INIS)

Berra, S.; Guala, M.; Herzovich, P.; Chocron, M.; Lorenzo, A.; Raffo Calderon, Ma. C. del; Urrutia, G.

1996-01-01

Atucha I is a Pressure Vessel Heavy Water Cooled Heavy Water Moderator Reactor. In this kind of reactor the moderator tank is physically connected to the primary coolant. Since neutron economy requires the moderator to be as cold as possible, it is necessary that even when physically connected, it should have a separated cooling system, which in this case is also used as a feed-water preheater, and also heat mass transfer with primary coolant should be minimized. This condition requires that some reactor internals are designed in principle to last the whole life of the plant. However, in 1988 the failure of one internal produced a 16 month shut down. This incident could have been prevented but the idea that reactor internals would not have failures due to aging was dominant at that time avoiding the early detection of the failure. However, the analysis of the records after the incident showed that some process variables had changed previously to the incident, i.e., power exchanged at the moderator heat exchanger had increased. Since the station restart up some changes in the moderator process variables and a flow rate reduction of about 10% through the primary side of one moderator cooler were observed. In order to understand the flow reduction and the overall behaviour of moderators parameters, two models were developed that predict moderator and moderator cooler behavior under the new conditions. The present paper refers to these models, which together with the improvement of process variables measurements mentioned in another paper presented at this meeting permits to understand current moderator behaviour and helps to early diagnostic of an eventual reactor internal failure. (author). 2 refs, 4 figs, 1 tab

Moderator behaviour and reactor internals integrity at Atucha I NPP

Energy Technology Data Exchange (ETDEWEB)

Berra, S; Guala, M; Herzovich, P [Central Nuclear Atucha I, Nucleoelectrica Argentina, Lima, Buenos Aires (Argentina); Chocron, M; Lorenzo, A; Raffo Calderon, Ma. C. del; Urrutia, G [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Centro Atomico Constituyentes

1997-12-31

Atucha I is a Pressure Vessel Heavy Water Cooled Heavy Water Moderator Reactor. In this kind of reactor the moderator tank is physically connected to the primary coolant. Since neutron economy requires the moderator to be as cold as possible, it is necessary that even when physically connected, it should have a separated cooling system, which in this case is also used as a feed-water preheater, and also heat mass transfer with primary coolant should be minimized. This condition requires that some reactor internals are designed in principle to last the whole life of the plant. However, in 1988 the failure of one internal produced a 16 month shut down. This incident could have been prevented but the idea that reactor internals would not have failures due to aging was dominant at that time avoiding the early detection of the failure. However, the analysis of the records after the incident showed that some process variables had changed previously to the incident, i.e., power exchanged at the moderator heat exchanger had increased. Since the station restart up some changes in the moderator process variables and a flow rate reduction of about 10% through the primary side of one moderator cooler were observed. In order to understand the flow reduction and the overall behaviour of moderators parameters, two models were developed that predict moderator and moderator cooler behavior under the new conditions. The present paper refers to these models, which together with the improvement of process variables measurements mentioned in another paper presented at this meeting permits to understand current moderator behaviour and helps to early diagnostic of an eventual reactor internal failure. (author). 2 refs, 4 figs, 1 tab.

Centralized operation and monitoring system for nuclear power plants

International Nuclear Information System (INIS)

Kudo, Mitsuru; Sato, Hideyuki; Murata, Fumio

1988-01-01

According to the prospect of long term energy demand, in 2000, the nuclear power generation facilities in Japan are expected to take 15.9% of the total energy demand. From this fact, it is an important subject to supply nuclear power more stably, and in the field of instrumentation and control, many researches and developments and the incessant effort of improvement have been continued. In the central operation and monitoring system which is the center of the stable operation of nuclear power plants, the man-machine technology aiding operators by electronic and computer application technologies has been positively developed and applied. It is considered that hereafter, for the purpose of rationally heightening the operation reliability of the plants, the high quality man-machine system freely using the most advanced technologies such as high reliability digital technology, optical information transmission, knowledge engineering and so on is developed and applied. The technical trend of operation and monitoring system, the concept of heightening operation and monitoring capability, the upgrading of operation and monitoring system, and the latest operation, monitoring and control systems for nuclear power plants and waste treatment facilities are described. (K.I.)

Sea transport of used nuclear fuel and radiactive disposals to a Swedish central store

International Nuclear Information System (INIS)

1977-10-01

Sea transport of used nuclear fuel and radioactive disposals to a Swedish central store. A vessel for transporting used nuclear fuel and radioactive disposals from the power stations at Ringhals, Barsebaeck, Simpevarp and Forsmark to a central store has been projected. Safety aspects, technical and economical aspects have been taken into consideration with regard to the actual volume of goods to be transported. Three different types of vessels are presented and a specification is given for the main alternative. A safety study of the main alternative is shown, regarding collision safety, fire risks and fire extinguishing equipment. (author)

Central depression of the nuclear charge distribution

International Nuclear Information System (INIS)

Friedrich, J.; Voegler, N.; Reinhard, P.G.

1986-01-01

As a systematic feature of all measured charge distributions we find a shift in the form-factor zeroes as compared to a simple folding model. To first order, this shift can be interpreted as resulting from the central depression w, caused by the Coulomb repulsion. Accounting for it leads to an increase in the surface width of nuclear charge distributions by 0.105 fm. This interpretation of the experimental findings is compared with the droplet model, which relates w with the compression modulus K and the asymmetry energy J. Accounting for w leads to an increase in the extrapolated nuclear matter density by 7.5%. However, this macroscopic model is not able to describe the experimental results in detail since w is also influenced by shell effects. HF+BCS calculations with effective Skyrme-type interactions reproduce part of the data, revealing the influence of shells on w. Here, too, there remain discrepancies in details. A level of accuracy is reached at which most probably also the skewness of the charge distribution must be taken into account. (orig.)

Intervention of hydrogen analysis laboratory for radioactive materials study

International Nuclear Information System (INIS)

Bruno, N.; Vinces, H.; Figueroa, S.

1996-01-01

The objective of the practice was the measurement of the hydrogen concentration on structural material from the Central Nuclear Atucha I (CNA-I) cooling channels using a LECO gas analyser. Original samples were previously separated into fractions at the Laboratiorio para Ensayos de Post-Irradiacion (LAPEP), Centro Atomico Ezeiza. The practice and the preliminary conditions of the laboratory and equipment to reduce the occupational dose for personnel and the work area contamination are described in this paper. In addition to the training activity for workers, the radiological control performed during the intervention and procedure followed to decontaminate LECO and the laboratory are summarized here. (authors)

Security central processing unit applications in the protection of nuclear facilities

International Nuclear Information System (INIS)

Goetzke, R.E.

1987-01-01

New or upgraded electronic security systems protecting nuclear facilities or complexes will be heavily computer dependent. Proper planning for new systems and the employment of new state-of-the-art 32 bit processors in the processing of subsystem reports are key elements in effective security systems. The processing of subsystem reports represents only a small segment of system overhead. In selecting a security system to meet the current and future needs for nuclear security applications the central processing unit (CPU) applied in the system architecture is the critical element in system performance. New 32 bit technology eliminates the need for program overlays while providing system programmers with well documented program tools to develop effective systems to operate in all phases of nuclear security applications

Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

Energy Technology Data Exchange (ETDEWEB)

Yussup, F., E-mail: nolida@nm.gov.my; Ibrahim, M. M., E-mail: maslina-i@nm.gov.my; Soh, S. C.; Hasim, H. [Instrumentation and Automation Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Haris, M. F. [Information Technology Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Azman, A. [Prototype and Development Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Razalim, F. A. A.; Yapp, R. [Health Physics Group, Radiation Safety and Health Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Ramli, A. A. M. [Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia)

2016-01-22

With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering.

Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

International Nuclear Information System (INIS)

Yussup, F.; Ibrahim, M. M.; Soh, S. C.; Hasim, H.; Haris, M. F.; Azman, A.; Razalim, F. A. A.; Yapp, R.; Ramli, A. A. M.

2016-01-01

With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering

Fifty years contribution to research and technological development of Argentina. Part 7

International Nuclear Information System (INIS)

Aguirre, Fernando; Boselli, Alfredo; Colangelo, Luis J.; Coll, Jorge A.; Espejo, Hector; Mattei, Clara E.; Ornstein, Roberto M.; Palacios, Tulio A.; Radicella, Renato; Rodrigo, Felix

2004-01-01

The paper is the seventh part of a short history of the National Atomic Energy Commission (CNEA). The future of the nuclear activities in the country is outlined, mainly of those related to the energy generation. The completion of the Atucha II nuclear power plant now under construction is supported. (author)

Scope for nuclear weapon-free zone in central and eastern Europe

International Nuclear Information System (INIS)

Pande, Savita

1998-01-01

The idea of a Central Europe free of nuclear weapons has its roots, of course, in the end of the cold war and the break-up of the former Union. These historical developments created the necessary conditions for the Lisbon Protocol, the successful withdrawal of all nuclear weapons from Belarus, Ukraine, and Kazakhstan as well as these countries' accession to the Non-Proliferation Treaty. It is admitted that even before these steps had been achieved, Belarus had put forward the nuclear-free zone initiative at the United Nations General Assembly in 1991. Like all the other nuclear weapon-free zones, existing or potential, a proposal for such a zone entails that it be analysed in the context of its political environment, regional specificity as well as the role, and implications of the relevant outside powers. These include Warsaw Pact dissolution and its impact on control of tactical nuclear weapons as well as the North Atlantic Treaty Organisation (NATO's) expansion eastwards. It is equally important to look at the issue in the context of its history, or, in other words, the past attempts

Mechanical and Radiological Characterization of Different parts of an Irradiation Coolant Channel Tube from Atucha I Nuclear Plant; Caracterizacion Mecanica y Radiologica de Partes de Canales Refrigerantes Irradiados Extraidos del Reactor de la Central Nuclear Atucha I

Energy Technology Data Exchange (ETDEWEB)

Piquin, Ruben [Instituto Balseiro, Universidad Nacional de Cuyo, Centro Atomico Bariloche, Universidad Nacional de Mar del Plata (Argentina)

2001-07-01

The widespread replacement of reactor internals has generated a substantial volume of active material. It is essential to work with these components at least in a partial way before the next planned stop, which will take place during the second semester of the year 2002. Due to the fact that the reactor internals pool and the storage pool for irradiated nuclear fuel have limited capacities, it has been proposed to compact an experimental shift of 50 irradiated coolant channels, that are currently placed in storage pools. Basically the processed waste will be put in baskets at the bottom pools.The alternative choice proposes to divide an irradiation coolant channel tube into different parts: stainless steel section, zircaloy-4 section and stainless steel section with hardened zones with cobalt alloys named Estelite-6. The person in charge has already planned the constructive and operative solutions but the mechanical characterization of the different parts of the channel tube is necessary in order to dimension the compaction tool needed for the semi-industrial installation.In the present special report, two well-differentiated actions will be described. The necessary compacted strength of the irradiation coolant channel tube will be estimated for the stainless steel section and the zircaloy-4 section starting from experiment with unirradiated material and considering effects of radiation damage and hydrides on the ductility.These results will be used to design the necessary compacted tools for the semi-industrial installation. The necessary equipment for the radiological characterization of the different material sections already specified will be described and the most important emitting particles of radiation that could be detected will be mentioned. Also the decontamination process to use including the radiological characterization of every stage of the process will be described in order to establish the decontamination factor. Finally the most important

Behavioral Determinants of Russian Nuclear State-Owned Enterprises in Central and Eastern European Region

OpenAIRE

Vlcek, Tomas; Jirusek, Martin

2015-01-01

Rosatom State Nuclear Corporation play a substantial role in the energy sector of the Central and Eastern European region and the behavioral characteristics of the company forms the basis of this article. Rosatom is positioned as the dominant provider of nuclear technology and fuel supplies to the region, in large part stemming from the Soviet legacy in CEE countries. Compounding this challenge, nuclear energy is one of the major sources of power generation in CEE. Given the long-time, near m...

Karlsruhe Nuclear Research Center, Central Safety Department. Annual report 1993

International Nuclear Information System (INIS)

Koelzer, W.

1994-04-01

The Central Safety Department is responsible for handling all tasks of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: behavior of trace elements in the environment and decontamination of soil, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurements and personnel dosimetry. This report gives details of the different duties, indicates the results of 1993 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

Reassessment and suspension of the nuclear power plant design requirement of the constraint of collective dose per unit of practice. (Requirement 6 (b), Standard AR 3.1.2)

International Nuclear Information System (INIS)

Amado, Valeria A.; Canoba, Analia C.; Curti, Adriana R.; Biaggio, Alfredo L.

2009-01-01

By the middle of 2005, the Nuclear Regulatory Authority (ARN) decided to re-assess the basis of a design requirement applicable to the limitation of nuclear power reactor radioactive discharges. Such requirement, aimed at restricting the discharge of globally dispersed long-lived radionuclides, was in force in Argentina since 1979 and was expressed as a limitation of the collective dose commitment per unit of electrical energy generated. The practical result of such regulatory action was the need to retain C-14 in the Atucha II power reactor under construction as well as in future heavy water reactors to be built in the country, and, later on, to manage it as to assure its isolation from the biosphere during an appropriate period of time. For the above-mentioned reassessment, an ad hoc task group was created and an internal report was presented to the Board of Directors by the middle of 2007. Because of such report the ARN decided to suspend the application of the requirement (i.e. it is not more mandatory, even for Atucha II). The present work presents the main aspects of that report. In particular, it explains the basis of the design requirement and the most important assumptions that triggered it. The differences between the assumptions made at that time and the reality of nuclear power generation at the beginning of the 21st Century, as well as their implications in relation to the requirement are described, including the Suess effect and its impact in the total dose due to C-14. Finally, after explaining in detail the facts that made no longer reasonable to keep in force the above mentioned requirement, the work presents the conclusions that lead the ARN to the suspension of this requirement. (author) [es

Operating practical experience at Argentina

International Nuclear Information System (INIS)

Quihillalt, Oscar

1997-01-01

Operating experiences of Atucha-1 and Embalse Nuclear Power Plants were discussed in this work. The technical and economic aspects, such as reliability, availability, personnel training, operating costs, prices and market, which exercise influence upon Argentina nuclear energy policy, mainly on the power electric generation by nuclear power plants were considered. Finally the current status of the nucleoelectric sector in Argentina and forecasting were analysed

Study of essential safety features of a three-loop 1,000 MWe light water reactor (PWR) and a corresponding heavy water reactor (HWR) on the basis of the IAEA nuclear safety standards

International Nuclear Information System (INIS)

1989-02-01

Based on the IAEA Standards, essential safety aspects of a three-loop pressurized water reactor (1,000 MWe) and a corresponding heavy water reactor were studied by the TUeV Baden e.V. in cooperation with the Gabinete de Proteccao e Seguranca Nuclear, a department of the Ministry which is responsible for Nuclear power plants in Portugal. As the fundamental principles of this study the design data for the light water reactor and the heavy water reactor provided in the safety analysis reports (KWU-SSAR for the 1,000 MWe PWR, KWU-PSAR Nuclear Power Plant ATUCHA II) are used. The assessment of the two different reactor types based on the IAEA Nuclear Safety Standards shows that the reactor plants designed according to the data given in the safety analysis reports of the plant manufacturer meet the design requirements laid down in the pertinent IAEA Standards. (orig.) [de

International Conference Nuclear Energy in Central Europe 99, V. 2. Proceedings. Embedded Meeting Neutron Imaging Methods to Detect Defects in Materials

International Nuclear Information System (INIS)

Gortnar, O.; Stritar, A.

1999-01-01

International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The second book of proceedings contain 14 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics cover Neutron Imaging Methods

A Procedure to Address the Fuel Rod Failures during LB-LOCA Transient in Atucha-2 NPP

Directory of Open Access Journals (Sweden)

Martina Adorni

2011-01-01

Full Text Available Depending on the specific event scenario and on the purpose of the analysis, the availability of calculation methods that are not implemented in the standard system thermal hydraulic codes might be required. This may imply the use of a dedicated fuel rod thermomechanical computer code. This paper provides an outline of the methodology for the analysis of the 2A LB-LOCA accident in Atucha-2 NPP and describes the procedure adopted for the use of the fuel rod thermomechanical code. The methodology implies the application of best estimate thermalhydraulics, neutron physics, and fuel pin performance computer codes, with the objective to verify the compliance with the specific acceptance criteria. The fuel pin performance code is applied with the main objective to evaluate the extent of cladding failures during the transient. The procedure consists of a deterministic calculation by the fuel performance code of each individual fuel rod during its lifetime and in the subsequent LB-LOCA transient calculations. The boundary and initial conditions are provided by core physics and three-dimensional neutron kinetic coupled thermal-hydraulic system codes calculations. The procedure is completed by the sensitivity calculations and the application of the probabilistic method, which are outside the scope of the current paper.

Nuclear policies in Central Europe. Environmental policy and enlargement of the European Union: Austria's policies towards Nuclear Reactors in neighboring countries

International Nuclear Information System (INIS)

Getzner, M.

2003-01-01

Austria's anti-nuclear policies are rooted in the successful anti-nuclear referendum on the Zwentendorf nuclear power plant (Lower Austria) in 1978 and the great impact of the Chernobyl catastrophe on Austria in 1986. Since about 1990, official Austria has pursued anti-nuclear policies not only at home but also abroad. In particular, reactors in Central and Eastern European Countries (CEEC) are the focal points of Austria's foreign anti-nuclear policies. Strategies include increasing nuclear safety, promoting energy efficiency and sustainable energy sources (such as renewable resources), and extending international legal frameworks to account for nuclear safety. Involvement in domestic energy issues in other countries is not an easy task, and while Austrian policy makers have had some success in increasing awareness of nuclear safety in Europe, they have also made a number of strategic mistakes. Notwithstanding real and substantiated concerns regarding nuclear safety, Austrian policies have lost credibility during recent years. This book explores the history and the development of Austrian anti-nuclear policies, and discusses the political economy of such policies. Particular emphasis is laid on the 2002 referendum against the Temelin reactor in the neighboring Czech Republic. (orig.)

Operating practical experience at Argentina; Experiencia practica operativa en la Argentina

Energy Technology Data Exchange (ETDEWEB)

Quihillalt, Oscar [Nucleoelectria Argentina S.A., Buenos Aires (Argentina)

1998-12-31

Operating experiences of Atucha-1 and Embalse Nuclear Power Plants were discussed in this work. The technical and economic aspects, such as reliability, availability, personnel training, operating costs, prices and market, which exercise influence upon Argentina nuclear energy policy, mainly on the power electric generation by nuclear power plants were considered. Finally the current status of the nucleoelectric sector in Argentina and forecasting were analysed. 3 figs., 5 tabs.

CAREM-25: a low-risk nuclear option

International Nuclear Information System (INIS)

Baron, Jorge H.; Nunez Mac Leod, J.E.; Rivera, S.S.

2000-01-01

The future use of nuclear energy for electricity production is assumed as a viable alternative at present, mainly taking into account the high environmental impact of the fossil fuel alternatives (greenhouse effect, acid rain). In the worldwide context, however, it is desirable that the next generation of nuclear power stations to be safer than the present ones. To demonstrate the safety level of a particular nuclear installation, the Risk Analysis (or Probabilistic Safety Assessment) is the most appropriate tool. Quantitative risk estimations can be performed with PSA. The risk can be split as the product of two factors: the first one takes into account the occurrence probability of accidental sequences that involve the release of radioactive material, and the second takes into account the magnitude and consequences of such a release. In the present work, the reduction of both factors is analyzed. The probability is reduced by the use of simpler and more reliable systems to perform the safety functions, and the consequence by the use of small power production units, provided with passive mitigation systems and long response times. The work is illustrated with a risk comparison for electricity production with CAREM-25 units, towards classic production units (Atucha II). The results are based on PSAs performed for both plants. The conclusions show an effective risk reduction (both in probability and in consequence) for the innovative CAREM-25 plant, coming to doses so low as to prevent any acute effect in the nearby population. (author)

Nuclear legislation in central and eastern europe and the NIS

International Nuclear Information System (INIS)

2003-01-01

This study presents the current state of legislation and regulations governing the peaceful uses of nuclear energy in the central and eastern European countries (CEEC) and the New Independent States (NIS). It also contains information on the national bodies responsible for the regulation and control of nuclear energy. The nuclear energy sector has not escaped from the changes that have affected the political, economic and social climates over the past fifteen years. Under the former socialist regime, activities in this field came within the sole remit of the State administration. In the legal area, it had not been deemed necessary in most of these countries to enact laws guaranteeing democratic control of electronuclear programmes and establishing a clear distinction between activities promoting this source of energy and regulatory control, while ensuring that safety imperatives take priority over all other considerations. With the arrival of new political forces came the will to remedy this situation promptly by creating new regulatory structures and drafting legislative texts based on those used in western countries. This evolution was all the more necessary given that, at the same time, the new policy of accountability had revealed safety defects in numerous nuclear installations in these countries, thus rendering international assistance indispensable. From the legal point of view, the outcome of these years of effort is remarkably positive: almost all countries of Eastern Europe pursuing electronuclear programmes have established institutions capable of exercising efficient control over nuclear power plants and other installations. Accession to the international conventions which form the backbone of nuclear law has become widespread. Modern legislation is henceforth in place in almost all of these states. (author)

Creation of zone free nuclear weapon (ZFNW) in the Central Asia

International Nuclear Information System (INIS)

Idrisov, E.A.; Eleukenov, D.Sh.

1997-01-01

Issues on non-proliferation of mass demolition weapons are of special importance for people of Kazakhstan. The whole damage brought to nature and people's health by nuclear tests at the Semipalatinsk test site (STS) is not revealed yet. Kazakhstan contributed much to the matter of nuclear disarmament. More than six years ago for the first time in the world by RK President's resolution an operating nuclear test site closed. Kazakhstan was the first to fulfill obligations in accordance with Lisbon protocol. Kazakhstan liquidated the fourth nuclear potential in the world. It's time to undertake further steps in the field of non-proliferation. One of such steps is the creation of a ZFNW in the central Asia. The idea of ZFNW creation is being acknowledged more and more during last 30 years. All the four present zones include more than 100 countries. If the Antarctic Region is taken into account the zones cover more than 50% of dry land. Regional ZFNWs attract attention as a means of reflecting and rewarding general valuers in the sphere of nuclear disarmament and armament control. Such zones help tj narrow geographical sphere of military nuclear activity and to strengthen non-proliferation regime. The importance of ZFNW in the process of strengthening global and regional peace and safety is confirmed by the documents of Conference for countries joined the agreement on non-proliferation (AN) of 1995 and the first meeting of the Organizing Committee for Conference of 2000

Nuclear legislation in Central and Eastern Europe and the NIS

CERN Document Server

2000-01-01

This publication examines the legislation and regulations governing the peaceful uses of nuclear energy in eastern European countries. It covers 11 countries from Central and Eastern Europe and 11 countries from the New Independent States. The chapters follow a systematic format making it easier for the reader to carry out research and compare information. This study will be updated regularly. Albania Kazakhstan Armenia Latvia Belarus Lithuania Bosnia and Herzegovina Poland Bulgaria Republic of Moldova Croatia Romania Czech Republic Russian Federation Estonia Slovak Republic Former Yugoslav Re

Activities for the life management of nuclear power plant in Argentina

International Nuclear Information System (INIS)

Chocron, M.; Fabbri, S.; Versaci, R.A.

2003-01-01

Since September 1994 the organisation of Argentine nuclear power activities includes the following entities: Argentine Nucleo Electric S.A (NASA) with operates two NPPs (Atucha-1 and Embalse), National Regulatory Board of Nuclear Activities (ARN), National Atomic Energy Commission Commission (CNEA) Within this scheme, one of the main activities undertaken by CNEA is to provide technological assistance to NASA for NPP operation. Works on Life Management of NPPs are included in these activities. In the past, NPP Life Management in Argentina was mainly based on the corrective maintenance concept based on the replacement of damaged part detected during the periodical outages. In recent times, as a consequential of an increasing concern about ageing a Subprogram was created to take care of these subjects. The subprogram, now in the first steps, comprise several tasks: The first task involves the identification of components ageing mechanism and materials likely to age. In the area of mechanical components. a starting point is matrix involving major components such as: Reactor Pressure Vessel, Reactor Internals, Steam Generators, Pressure Tubes, Piping, etc. In this work the apply methodology for the selection of the components will be presented. (Full text)

Status of the initiative to create a nuclear-weapon-free space in Central and Eastern Europe

International Nuclear Information System (INIS)

Sychou, A.

1997-01-01

The aims of Belarus proposal for creating the nuclear-weapon-free zone in Central and Eastern Europe which has already been reflected in official documents of the 51st session of the UN General Assembly are described. This could reaffirm the intention of the European States to move towards the final goal of achieving general and complete nuclear disarmament under efficient international control

Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007; Padrao da mortalidade da populacao circunvizinha a Central Nuclear Almirante Alvaro Alberto / 1986 a 2007

Energy Technology Data Exchange (ETDEWEB)

Leite, Teresa Cristina Sampaio de Barros; Silva, Ilson Peixoto Medeiros da; Jannuzzi, Denise Maria Souza; Higino, Thiago Nunes; Santos, Tatiana Rodrigues dos [Fundacao Eletronuclear de Assistencia Medica (CIRA/FEAM), Angra dos Reis, RJ (Brazil). Centro de Informacoes sobre Radioepidemiologia; Xavier, Diego Ricardo [Fundacao Inst. Oswaldo Cruz (FIOCRUZ), Rio de Janeiro, RJ (Brazil). lnst. de Comunicacao e Informacao Cientifica e Tecnologica; Silva, Roseli Monteiro da [Fundacao Inst. Oswaldo Cruz (FIOCRUZ), Rio de Janeiro, RJ (Brazil)

2011-05-15

This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

Undergraduate teaching of nuclear medicine: a comparison between Central and Eastern Europe and European Union countries

International Nuclear Information System (INIS)

Lass, P.; Scheffler, J.; Bandurski, T.

2003-01-01

This paper overviews the curricula of nuclear medicine (NM) undergraduate training in 34 Central and Eastern European (CEE) and 37 European Union (EU) medical faculties. The data show enormous variation in the number of hours devoted to nuclear medicine, varying between 1-2 to 40 hours and highly differentiated concepts/ideas of nuclear medicine training in particular countries. In most EU countries this teaching is integrated with that of radiology or clinical modules, also with training in clinical physiology. In many CEE countries teaching and testing of NM are independent, although integration with other teaching modules is frequent. The paper discusses the differences in particular approaches to nuclear medicine teaching. (author)

Environmental monitoring in the surroundings of nuclear power plants of Argentina during 1996 and 1997

International Nuclear Information System (INIS)

Canoba, A.C.; Lopez, F.O.; Bruno, H.A.

1998-01-01

During 1996 and 1997, the environmental monitoring program in the surroundings of nuclear power plants Atucha 1 (CNA-1) and Embalse (CNE) was performed. For the selection of the sample points, sample type and frequency, recommendations were taken into account, as well as the major pathways of exposure to man. The results of the measurements were, in general, below the lower limit of detection and the doses for each critical group were, in the case of CNA I, below 4.9 E-3 mSv during 1996 and below 4.5 E-3 mSv during 1997, and for CNE, below 7.7 E-3 mSv during 1996 and below 9.4 mSv during 1997. All of these values are well below the dose limits established by todays norms (1mSv/year). (author) [es

Operative modes of the primary circuit degasser of Atucha II N.P.P

International Nuclear Information System (INIS)

Rodriguez, Ivanna; Contino, Maximiliano; Chocron, Mauricio; Duca, Jorge

2012-09-01

Atucha II (N.A.S.A., Buenos Aires Province, Argentina) is a Pressurized Vessel Heavy Water Reactor designed by Siemens with a capacity of 740 MWe. After a long delay in construction the plant is close to the commissioning and among the many task that are carried out, chemistry and operation of devices related to it are under consideration [1]. As it is known, Hydrogen or Deuterium dosing has the purpose of both: limitation of the water radiolysis and to provide an appropriate reductive media for the structural materials, mainly stainless steel, A800 and Zr-4. Dealing with a heavy water plant, it is critical to determine whether it is necessary to add D 2 or if it is feasible to dose H 2 , by considering heavy water degradation and heavy water upgrading system capability. Those aspects have been previously analyzed and presented [2]. It is also necessary to consider blankets and venting locations that address to losses of the expensive D 2 . In the present work several alternatives of hydrogenation are presented and evaluated, considering the Degasser (D), the Volume Control Tank (TCV) and the special features of the purification and volume control system of a pressurized vessel heavy water plant where the primary circuit and moderator are partially mixed. Also the influence of venting through the pressurizer is analyzed. Conclusions are obtained in connection to (i) the maintenance of a permanent blanket of H 2 /He, 4%, in the TCV dome at a given initial pressure, (ii) The same but constant pressure to reach 0.6 ppm of H 2 in the Primary and Moderator water circuit, (iii) transients while reducing pressure in the Degasser and considering contribution of pressurizer venting, (iv) estimated contribution of the general corrosion of the system and (iv) differences if D 2 is used. (authors)

Decommissioning and deactivation of nuclear facilities; Desmantelamiento y clausura de instalaciones nucleares

Energy Technology Data Exchange (ETDEWEB)

Anasco, Roberto; Harriague, Santiago; Hey, Alfredo M [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Gerencia de Tecnologia y Medio Ambiente; Fabbri, Silvio [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes; Garonis, Omar H [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Gestion de Calidad

2003-07-01

The National Atomic Energy Commission (CNEA) is responsible for the decommissioning and deactivation of all relevant nuclear facilities in Argentina. A D and D Subprogram was created in 2000, within Technology Branch of the CNEA, in order to fulfill this responsibility. The D and D Subprogram has organized its activities in four fields: Planning; Technology development; Human resources development and training; International cooperation. The paper describes the work already done in those 4 areas, as well as the nuclear facilities existing in the country. Planning is being developed for the decommissioning of research reactors, beginning with RA-1, as well as for the Atucha I nuclear power station. An integral Management System has been developed, compatibilizing requirements from ISO 9001, ISO 14001, the national norm for Safety and Occupational Health (equivalent to BS 8800), and IAEA 50-SG Q series. Technology development is for the time being concentrated on mechanical decontamination and concrete demolition. A review has been made of technologies already developed both by CNEA and Nucleoelectrica Argentina S.A. (the nuclear power utility) in areas of chemical and electrochemical decontamination, cutting techniques and robotics. Human resources development has been based on training abroad in the areas of decontamination, cutting techniques, quality assurance and planning, as well as on specific courses, seminars and workshops. An IAEA regional training course on D and D has been given on April 2002 at CNEA's Constituyentes Atomic Center, with the assistance of 22 university graduates from 13 countries in the Latin American and Caribbean Region, and 11 from Argentina. CNEA has also given fellowships for PhD and Master thesis on the subject. International cooperation has been intense, and based on: - IAEA Technical Cooperation Project and experts missions; - Cooperation agreement with the US Department of Energy; - Cooperation agreement with Germany

Assistance in chemistry and chemical processes related to primary, secondary and ancillary systems of nuclear power plants

International Nuclear Information System (INIS)

Chocron, Mauricio A.; Becquart, Elena T.; Iglesias, Alberto M.; La Gamma, Ana M.; Villegas, Marina

2003-01-01

Argentina is currently running two nuclear power plants: Atucha I (CNA I) and Embalse (CNE) operated by Nucleoelectrica Argentina (NASA) whereas the National Atomic Energy Commission (CNEA), among other activities, is responsible for research and development in the nuclear field, operates research reactors and carries out projects related to them. In particular, the Reactor Chemistry Section personnel (currently part of the Chemistry Dept.) has been working on the field of reactor water chemistry for more than 25 years, on research and support to the NPPs chemistry department. Though the most relevant tasks have been connected to primary and secondary circuits chemistry, ancillary systems show along the time unexpected problems or feasible improvements originated in the undergoing operating time as well as in phenomena not foreseen by the constructors. In the present paper are presented the tasks performed in relation to the following systems of Embalse NPP: 1) Heavy water upgrade column preliminary water treatment; 2) Liquid waste system preliminary water treatment; and 3) Primary heat transport system coolant crud composition. (author)

Sharing of responsibilities between central and local authorities with regard to the licensing of nuclear installations

International Nuclear Information System (INIS)

Peltzer, P.

1986-01-01

With regard to sharing of responsibility in the field of nuclear licensing between central and local authorities, the Belgian State has entered into a new phase of regionalisation since the enactment of the law of August 8, 1980. This might entail a conflict of competence in case of the licensing of nuclear power plants. A general survey of foreign legislations seems to indicate that a similar risk also exists in other countries. (CW) [de

The central dose register for the nuclear industry in Sweden

International Nuclear Information System (INIS)

Widell, C.-O.

1978-06-01

The central dose register for the nuclear industry in Sweden has been in operation since 1974. The system contains today about 18 000 persons in the register. The dose information is stored on discs on a CDC Cyber 172 computer and all information to and from the system is handled by terminals at the different nuclear sites. The terminals are connected to the computer by normal telephone lines. Most doses are recorded on TLD. The data from the TLD readers is automatically transferred to the computer via punched tape and the local computer terminal. The dose results are stored under the person's unique social security number. It is also possible to use social security number systems of other countries. The dose register system also supervises the condition of the readers and their calibration by circulation dosimeters which have been given a reference dose. The information from the system can be obtained on many different types of lists, for example, annual, quarterly, monthly, departementally, personal history, job number. (author)

Flow of ideal fluid through a central region of a nuclear reactor wire-spaced fuel subassembly

International Nuclear Information System (INIS)

Schmid, J.

1991-04-01

The results are given of calculations of the flow of an ideal fluid through the central region of a nuclear reactor wire-spaced fuel subassembly. The computer code used is briefly described. (author). 10 figs., 4 refs

Decree N0 73-322 of 15 March 1973 concerning insurance and reinsurance of exceptional and nuclear risks by the Central Reinsurance Fund

International Nuclear Information System (INIS)

1973-01-01

This Decree provides that the Central Reinsurance Fund may cover, with the State guarantee, risks for which operators of nuclear ships and installations are liable and concerning which State intervention is provided for by legislation. These operations relate in particular to goods carried, nuclear installations and property on the site of such installations. The Decree sets up an Advisory Commission for the Central Reinsurance Fund regarding security for exceptional and nuclear risks and repeals a 1967 Decree on insurance of exceptional risks. (NEA) [fr

Center for Nuclear Safety in Central and Eastern Europe: a platform for co-operation

International Nuclear Information System (INIS)

Tomik, L.; Kichev, E.

2003-01-01

The paper presents a summary of the current status and the activities of the Centre of Nuclear Safety in Central and Eastern Europe (CENS). The CENS is a non-profit and independent association supported by the Swiss and Slovak Governments. The main mission of the CENS is to provide an independent platform for technical co-operation between the regulatory authorities of the Western and Eastern countries. The key partners of the CENS are the Swiss Federal Nuclear Safety Inspectorate (HSK), the International Atomic Energy Agency (IAEA), the US Department of Energy (US DOE), the Nuclear Regulatory Authority of the Slovak Republic (UJD), the Gesellschaft fuer Anlagen-und Reaktorsicherheit mbH (GRS), Germany and the Institute of Radiation Protection and Nuclear Safety (IRSN), France. The CENS programs for 2003-2004 are presented. It can be considered as a complement to the IAEA activities in the area of short-term and event urgent planning. CENS projects as an example are presented. CENS proposals for co-operation with the Bulgarian institutions are made in connection with the topics of the forum round table discussions

Transfer of nuclides from the water phase to the sediments during normal and extraordinary hydrological cycles

International Nuclear Information System (INIS)

1985-07-01

Atucha I and Atucha II nuclear power plants are located on the right margin of the Parana de las Palmas river. This river belongs to the Cuenca del Plata, whose 1982-1983 hydrologic cycle registered the greatest freshets of the century. Works and studies previously fixed had to be altered and investigations were adapted to the possibilities and the particular hydric conditions verified. Considerations on the transfer of nuclides between water and sediments are presented. The floods reduce the water-sediments contact time on the bed of the river. In outer areas, the waters labelled by the nuclear power plant effluent discharge favor the infiltration in alluvial soils, as well as the exchange with the sediments. The investigations carried out for the phase near to the discharge of liquid effluents (related to the critical group) made possible to prove the characteristics of the path of the liquid wastes released, the distribution coefficient and the fixation or penetrability of some nuclides in soils of the floody valley. In this manner, a balance of radioactive nuclides incorporated to soils and sediments from the neighbourhood of Atucha and the water-course of Parana de las Palmas river is obtained. The presence of 60 Co and 137 Cs in the floody soils on the right margin of this river was detected and measured during the greatest flood of the century. On the other hand, 144 Ce, 51 Cr, 106 Ru and 90 Sr have not been detected. The detection of artificial radioisotopes turns out to be impossible in normal hydrological years, even in the sorroundings of the nuclear power plant or the critical group (from the point of view of the surface waters, The Fishing Club, 3 km down stream). (M.E.L.) [es

Decree no 77-623 of 6 June 1977 amending Decree no 73-278 of 13 March 1973 setting up a Superior Council for Nuclear Safety and a Central Service for the Safety of Nuclear Installations

International Nuclear Information System (INIS)

1977-01-01

Under this Decree, the Central Service for the Safety of Nuclear Installations is placed from now onwards within the Directorate of Mines which comes under the Ministry of Industry, Trade and Crafts. The Head of the Central Service for the Safety of Nuclear Installations and his deputy are appointed by Order of the Minister of Industry, Trade and Crafts, on the proposal of the Director of Mines. (NEA) [fr

Separation of tritium from heavy water by vacuum distillation; Separacion de tritio de agua pesada por destilacion al vacio

Energy Technology Data Exchange (ETDEWEB)

Vidal, M I; Cabrera, C A [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

1997-12-31

In this report the feasibility of using vacuum distillation to detriate the moderator of a HWR nuclear power plant is studied. It is intended to use, for this purpose, the Atucha I nuclear power plant present facilities. The physical-chemistry of the system is described and the most appropriate range of operating conditions is examined. The availability of data to make use of the present equipment is also analyzed. (author). 20 refs., 3 figs., 1 tab.

Separation of tritium from heavy water by vacuum distillation

International Nuclear Information System (INIS)

Vidal, M.I.; Cabrera, C.A.

1996-01-01

In this report the feasibility of using vacuum distillation to detriate the moderator of a HWR nuclear power plant is studied. It is intended to use, for this purpose, the Atucha I nuclear power plant present facilities. The physical-chemistry of the system is described and the most appropriate range of operating conditions is examined. The availability of data to make use of the present equipment is also analyzed. (author). 20 refs., 3 figs., 1 tab

Rapid prototyping of the Central Safety System for Nuclear Risk in ITER

Energy Technology Data Exchange (ETDEWEB)

Scibile, L. [ITER Organization, CS 90 046, St. Paul-lez-Durance, Cedex (France); Ambrosino, G. [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy); De Tommasi, G., E-mail: detommas@unina.i [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy); Pironti, A. [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy)

2010-07-15

The Central Safety System for Nuclear Risk (CSS-N) coordinates the safety control systems to ensure nuclear safety for the ITER complex. Since the CSS-N is a safety critical system, its validation and commissioning play a very important role; in particular the required level of reliability must be demonstrated. In such a scenario, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the control system requirements. Furthermore the models can than be used for the rapid prototyping of the safety system. Hardware-in-the-loop simulations can also be performed in order to assess the performance of the control hardware against a plant simulator. The proposed approach relies on the availability of a plant simulator to develop the prototype of the control system. This paper introduces the methodology used to design and develop both the CSS-N Oriented Plant Simulator and the CSS-N Prototype.

Rapid prototyping of the Central Safety System for Nuclear Risk in ITER

International Nuclear Information System (INIS)

Scibile, L.; Ambrosino, G.; De Tommasi, G.; Pironti, A.

2010-01-01

The Central Safety System for Nuclear Risk (CSS-N) coordinates the safety control systems to ensure nuclear safety for the ITER complex. Since the CSS-N is a safety critical system, its validation and commissioning play a very important role; in particular the required level of reliability must be demonstrated. In such a scenario, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the control system requirements. Furthermore the models can than be used for the rapid prototyping of the safety system. Hardware-in-the-loop simulations can also be performed in order to assess the performance of the control hardware against a plant simulator. The proposed approach relies on the availability of a plant simulator to develop the prototype of the control system. This paper introduces the methodology used to design and develop both the CSS-N Oriented Plant Simulator and the CSS-N Prototype.

Defence in Depth and Ageing Management

Energy Technology Data Exchange (ETDEWEB)

Fabbri, S.; Vega, G.; Diluch, A.; Versaci, R., E-mail: versaci@cnea.gov.ar [Comisión Nacional de Energía Atómica, Buenos Aires (Argentina)

2014-10-15

Accident prevention is the first safety priority of both designers and operators. It is achieved through the use of reliable structures, components, systems and procedures in a plant operated by personnel who are committed to a strong safety culture. For future nuclear power plants, consideration of multiple failures and severe accidents will be achieved in a more systematic and complete way from the design stage. Defence in depth (DID) consists of a hierarchical deployment of different levels of equipment and procedures in order to maintain the effectiveness of physical barriers placed between radioactive materials and workers, the public or the environment, in normal operation, anticipated operational occurrences and, for some barriers, in accidents at the plant. The primary way of preventing accidents is to achieve a high quality in design, construction and operation of the plant, and thereby to ensure that deviations from normal operation are infrequent. The best way to meet these premises of effectiveness of the barriers and the Systems, Structures and Components (SSCs) is to develop an ageing management programme to prevent potential failures and accidents. In this work we will refer to the ageing management programme for Atucha I and Atucha II power plants and to the Atucha I spent fuel storage. (author)

A Study to Promote a Collaboration of R and D for Nuclear Energy Technology Development between Korea and Central Asia

Energy Technology Data Exchange (ETDEWEB)

Rho, Si Pyo; Kim, Cheol Jung; Yoo, Bung Duk; Kim, Jae Woo; Lee, Myung Ho; Kim, Kyung Pyo

2006-02-15

The goal of this research work is to promote the cooperation in the field of nuclear related works with Kazakhstan and Uzbekistan which are main countries in the central Asia. To make a basis on exchanging researchers, a staff in KAERI had visited INP NNC RK, touring research reactors, and make a discussion with the staffs in INP. With this, there is a efforts to make an arrangement between KAERI and NNC RK, signing will be made in near futures. To understand the level of nuclear technology in Uzbekistan, Dr. Rho had made a trip to INP. He visited the Gamma-radiation facility, a research reactor. In Nov. 2005, the chairman of Science Academy visited Korea to discuss the future cooperation in the field of peaceful use of the nuclear energy. By doing so, Korea will make an effort to cooperate with countries in the Central Asia.

A Study to Promote a Collaboration of R and D for Nuclear Energy Technology Development between Korea and Central Asia

International Nuclear Information System (INIS)

Rho, Si Pyo; Kim, Cheol Jung; Yoo, Bung Duk; Kim, Jae Woo; Lee, Myung Ho; Kim, Kyung Pyo

2006-02-01

The goal of this research work is to promote the cooperation in the field of nuclear related works with Kazakhstan and Uzbekistan which are main countries in the central Asia. To make a basis on exchanging researchers, a staff in KAERI had visited INP NNC RK, touring research reactors, and make a discussion with the staffs in INP. With this, there is a efforts to make an arrangement between KAERI and NNC RK, signing will be made in near futures. To understand the level of nuclear technology in Uzbekistan, Dr. Rho had made a trip to INP. He visited the Gamma-radiation facility, a research reactor. In Nov. 2005, the chairman of Science Academy visited Korea to discuss the future cooperation in the field of peaceful use of the nuclear energy. By doing so, Korea will make an effort to cooperate with countries in the Central Asia

Decommissioning and deactivation of nuclear facilities

International Nuclear Information System (INIS)

Anasco, Roberto; Harriague, Santiago; Hey, Alfredo M.; Fabbri, Silvio; Garonis, Omar H.

2003-01-01

The National Atomic Energy Commission (CNEA) is responsible for the decommissioning and deactivation of all relevant nuclear facilities in Argentina. A D and D Subprogram was created in 2000, within Technology Branch of the CNEA, in order to fulfill this responsibility. The D and D Subprogram has organized its activities in four fields: Planning; Technology development; Human resources development and training; International cooperation. The paper describes the work already done in those 4 areas, as well as the nuclear facilities existing in the country. Planning is being developed for the decommissioning of research reactors, beginning with RA-1, as well as for the Atucha I nuclear power station. An integral Management System has been developed, compatibilizing requirements from ISO 9001, ISO 14001, the national norm for Safety and Occupational Health (equivalent to BS 8800), and IAEA 50-SG Q series. Technology development is for the time being concentrated on mechanical decontamination and concrete demolition. A review has been made of technologies already developed both by CNEA and Nucleoelectrica Argentina S.A. (the nuclear power utility) in areas of chemical and electrochemical decontamination, cutting techniques and robotics. Human resources development has been based on training abroad in the areas of decontamination, cutting techniques, quality assurance and planning, as well as on specific courses, seminars and workshops. An IAEA regional training course on D and D has been given on April 2002 at CNEA's Constituyentes Atomic Center, with the assistance of 22 university graduates from 13 countries in the Latin American and Caribbean Region, and 11 from Argentina. CNEA has also given fellowships for PhD and Master thesis on the subject. International cooperation has been intense, and based on: - IAEA Technical Cooperation Project and experts missions; - Cooperation agreement with the US Department of Energy; - Cooperation agreement with Germany

Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007

International Nuclear Information System (INIS)

Leite, Teresa Cristina Sampaio de Barros; Silva, Ilson Peixoto Medeiros da; Jannuzzi, Denise Maria Souza; Higino, Thiago Nunes; Santos, Tatiana Rodrigues dos

2011-05-01

This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

National Atomic Energy Commission. Decree No. 1540, August 30 1994

International Nuclear Information System (INIS)

1994-01-01

One of the objectives of the reorganization process of Argentina's public sector was to transfer to the private sector some of the Nation's productive activities, including those concerning the nuclear field. As a consequence, by Decree No. 1540 of August 30, 1994, (B.O. 2-Dec-94), CNEA's functions were partially reorganized. According to Decree No. 1540, the National Atomic Energy Commission (CNEA) maintained the missions and functions established by Decree-Law No. 22.498/56, with the exception of the regulation and surveillance of nuclear activities and the nuclear power generation activities. For the fulfillment of these activities, both the National Board of Nuclear Regulation (Ente Nacional Regulador Nuclear - ENREN) and Nucleoelectrica Argentina S.A. (NASA), were created. The National Board of Nuclear Regulation (ENREN), as an autarchical entity reporting to the Presidency of the Nation, shall be administered by a Board of Directors and shall be responsible for surveying and controlling all nuclear activities, shall suggest regulations and standards to ensure radiological and nuclear safety, personal protection, a controlled use of nuclear materials, licensing and surveillance of nuclear installations, and compliance with international safeguards. Nucleoelectrica Argentina S.A. (NASA) shall be organised as a corporation, reporting to the Ministry of Economy and Public Works and Services (Ministerio de Economia y Obras y Servicios Publicos) who will approve its statures. NASA shall take care of nuclear power generation at the Atucha I and Embalse nuclear power plants, as well as the construction, start-up and operation of the Atucha II nuclear power plant. As far as royalties are concerned, the Decree obliges Nucleoelectrica Argentina S.A. to pay CNEA for the performance of research and development activities, and to the ENREN an yearly regulatory tax per megawatt of installed nuclear power generation capacity. Also, Nucleoelectrica Argentina S.A. is declared

Nuclear power in eastern and central Europe. Background paper

International Nuclear Information System (INIS)

Myers, L.C.

1993-11-01

The breakup of the former Soviet Union and other political changes in eastern and central Europe have opened up the area to closer scrutiny than was previously possible. Because of the accident at Chernobyl, nuclear power is one of the subjects that western nations have had a great deal of interest in exploring. The former Soviet Union designed and/or helped build more than 60 civilian reactors in the region. Most of these reactors follow one of two distinctly different designs: the VVER, or pressurized water reactor series; and the RBMK, which is a graphite-moderated, multi-channel reactor (the so-called Chernobyl type). In addition, there are two fast-breeder reactors and four graphite-moderated boiling water reactors for combined heat and power in operation in Russia. These last two designs are not widely distributed and so are not discussed in detail in this report. As noted above, the safety of Soviet-designed reactors has been of great concern around the world since the catastrophic events at Chernobyl in 1986. This paper will briefly describe the technology involved. It will also examine the main safety concerns, both technical and organizational, associated with each reactor type. In addition, the paper will review the nuclear power programs in the new countries emerging from the former Soviet Union and its satellites and discuss the international efforts underway to address the most pressing problems. (author). 1 tab

Nuclear power in eastern and central Europe. Background paper

Energy Technology Data Exchange (ETDEWEB)

Myers, L C [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

1993-11-01

The breakup of the former Soviet Union and other political changes in eastern and central Europe have opened up the area to closer scrutiny than was previously possible. Because of the accident at Chernobyl, nuclear power is one of the subjects that western nations have had a great deal of interest in exploring. The former Soviet Union designed and/or helped build more than 60 civilian reactors in the region. Most of these reactors follow one of two distinctly different designs: the VVER, or pressurized water reactor series; and the RBMK, which is a graphite-moderated, multi-channel reactor (the so-called Chernobyl type). In addition, there are two fast-breeder reactors and four graphite-moderated boiling water reactors for combined heat and power in operation in Russia. These last two designs are not widely distributed and so are not discussed in detail in this report. As noted above, the safety of Soviet-designed reactors has been of great concern around the world since the catastrophic events at Chernobyl in 1986. This paper will briefly describe the technology involved. It will also examine the main safety concerns, both technical and organizational, associated with each reactor type. In addition, the paper will review the nuclear power programs in the new countries emerging from the former Soviet Union and its satellites and discuss the international efforts underway to address the most pressing problems. (author). 1 tab.

Piping information centralized management system for nuclear plant, PIMAS

International Nuclear Information System (INIS)

Matsumoto, Masaru

1977-01-01

Piping works frequently cause many troubles in the progress of construction works, because piping is the final procedure in design and construction and is forced to suffer the problems in earlier stages. The enormous amount of data on quality control and management leads to the employment of many unskilled designers of low technical ability, and it causes confusion in installation and inspection works. In order to improve the situation, the ''piping information management system for nuclear plants (PIMAS)'' has been introduced attempting labor-saving and speed-up. Its main purposes are the mechanization of drafting works, the centralization of piping informations, labor-saving and speed-up in preparing production control data and material management. The features of the system are as follows: anyone can use the same informations whenever he requires them because the informations handled in design works are contained in a large computer; the system can be operated on-line, and the terminals are provided in the sections which require informations; and the sub-systems are completed for preparing a variety of drawings and data. Through the system, material control has become possible by using the material data in each plant, stock material data and the information on the revision of drawings in the design department. Efficiency improvement and information centralization in the manufacturing department have also been achieved because the computer has prepared many kinds of slips based on unified drawings and accurate informations. (Wakatsuki, Y.)

The ATC, the centralized temporary storage facility for the spanish nuclear spend fuel; El ATC, la instalación de Almacenamiento Temporal Centralizado de Combustible Nuclear Gastado Español

Energy Technology Data Exchange (ETDEWEB)

González Fernández-Conde, A.; Gónzalez Gandal, R.; Larrosa Peruga, O.; Medinilla Téllez, G.; Navarro Santos, M.

2016-07-01

The ATC, strategic project contained in the Sixth Radioactive Waste General Plan approved by the Government in 2006, is the temporary storage facility of centralized nature intended to store the spent nuclear fuel generated by Spanish NPP during their operation life, for other so-called special waste arising either from the ATC operation itself or from NPP dismantling, and for vitrified waste generated as a result of fuel reprocessing from Vandellós 1 NPP. The main functions of the ATC are the reception of transport casks, encapsulation of spent fuel, and storage of such canister in dry vaults with passive cooling by natural convection; and additionally, the temporary storage of storage casks with spent fuel, of other special waste in canisters, and finally of secondary waste generated during the operation of the facility. The facility estimated operation lifetime is 60 years, and its safety structures, systems and components are designed considering the requirements according to the Spanish nuclear regulations and using best international practices. In the detailed design, major Spanish and some foreign nuclear sector engineering companies are taking part. [Spanish] El ATC, proyecto estratégico recogido en el Sexto Plan General de Residuos Radiactivos aprobado por el Gobierno en 2006, es la instalación de almacenamiento temporal de carácter centralizado destinada para el combustible nuclear gastado generado por las centrales nucleares españolas durante su proceso de operación, así como de otros residuos denominados especiales originados por la propia operación o durante el desmantelamiento de las citadas centrales nucleares, así como los residuos vitrificados originados como consecuencia del reproceso del combustible de la central nuclear de Vandellós I. Las principales funciones del ATC son la recepción de los contenedores de transporte, encapsulado del combustible y almacenamiento de dichas cápsulas en bóvedas en seco con refrigeración pasiva por

THERMOS, district central heating nuclear reactors

International Nuclear Information System (INIS)

Patarin, L.

1981-02-01

In order to expand the penetration of uranium in the national energy balance sheet, the C.E.A. has been studying nuclear reactors for several years now, that are capable of providing heat at favourable economic conditions. In this paper the THERMOS model is introduced. After showing the attraction of direct town heating by nuclear energy, the author describes the THERMOS project, defines the potential market, notably in France, and applies the lay-out study to the Grenoble Nuclear Study Centre site with district communal heating in mind. The economic aspects of the scheme are briefly mentioned [fr

Reinforcement of planning and response to emergencies inside nuclear power plants; Refuerzo de la planificación y respuesta ante emergencias en el interior de las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Cortés, M.A.; Garcés, J.M.; Bolaños, J.; Fernández, J.; Gutiérrez, C.; Pontejo, A.; Rosell, B.

2015-07-01

Fukushima Daichi nuclear accident (11th march of 2011) required a rapid and effective response of nuclear industry, in order to guarantee that current safety margins were enough to cope with events like this or even worse. In Europe, stress tests were carried out to comply with that objective, evaluating if every nuclear plant was able to succeed managing design basis accidents or even beyond. Stress-test results were satisfactory, although several areas for improvement where identified. Improvements in emergency response and management have been developed in several phases. First, increasing emergency response capacity by implementing modifications in existing equipment. Later, installing new equipment (generally portable) which would be used in even more degraded conditions. This must be held by the revision of emergency response personnel and their training. Finally, external support has been reinforced to help in longstanding emergencies, with the establishment of CAE (Regional Center), and collaboration protocols with the Army. These actions, supervised and approved by the Regulator Body (CSN) will lead to increase plants safety margins and their emergency response capacities in order to reduce probability and consequences of a nuclear accident to the minimum. [Spanish] El accidente nuclear ocurrido el 11 de marzo de 2011 en Fukushima Daichi requirió de una pronta y efectiva respuesta de la industria nuclear, que garantizase que los márgenes de seguridad eran los adecuados para hacer frente a sucesos de estas características o incluso peores. Con ese objetivo se planteó, a nivel europeo, la realización de unas pruebas de resistencia que valorasen si las centrales podían hacer frente con garantías a una serie de accidentes dentro y más allá de las bases de diseño. Los resultados fueron satisfactorios, si bien se identificaron varios aspectos de mejora. La mejora en la respuesta y gestión de emergencias de las centrales nucleares se ha planteado en

An overlook of the new global nuclear scenario and the emergent challenges

International Nuclear Information System (INIS)

Solanilla, Roberto B.A.

2007-01-01

The aim of this paper is to make a short overlook of the world nuclear renaissance and point out some emergent challenges. The presentation covers different subjects in which the nuclear energy shows great advantage to face concerns about climate change, energy demand growth, and relative cost of competing technologies in a global scenario. Additionally nuclear technology can deploy in a middle term an important potential development oriented to improve even more that nuclear design, safety, environment protection, economic and sustainability of the present nuclear reactors generation. The world nuclear energy scenario reveals a renaissance after a long period of lethargy. Now is the focus of considerable attention and debate about the risks and benefits of its expansion. Many countries are again planning ambitious nuclear programs. In the case of Argentina, a decision was taken to end the construction of Atucha 750 MWe power plant (NPP) and to begin the construction of another two NPP in the next decade. In the middle term and expansion of 60 % of the present world nuclear capabilities is foreseen. For the long term there could be much more if today's performance data is maintained or improved. It would require the nuclear industry to return immediately to the most rapid period of growth experienced in the past. The training of the young people is also an important challenge. But some countries are still reluctant due to the adverse local public opinion. In spite of the great accessibility and availability of the NPP confirmed by the global experience of the 350 operating nuclear power plants, the public acceptability is not confirmed. Some sectors of the society -with the support in some case of the media- are against the use of the nuclear energy. In this paper some reasons of the public concerns is explained and actions are mentioned to change its perceptions. At the end, the global society in front of the real means available to fulfill the growing energy

Development of 3D models of buildings for containment of the nuclear power plant of Almaraz and of the Trillo Nuclear with the GOTHIC 8.0 code; Desarrollo de modelos 3D de los edificios de conten cion de la Central Nuclear de Almaraz y de la Central Nuclear de Trillo con el codigo GOTHIC 8.0

Energy Technology Data Exchange (ETDEWEB)

Jimenez, G.; Bocanegra Melian, R.; Fernandez Cosils, K.; Barreira Pereira, P.; Rey Peinado, L.; Posada Barral, J. M.

2014-07-01

The objective of the first phase of the research of CNAT and the UPM project is the construction of several three-dimensional models detailed GOTHIC 8.0 code of containment of a buildings plant type PWR-W and KWU, corresponding to the Central Nuclear de Almaraz (CNA) and Trillo (CNT) respectively. (Author)

Between research and energy production

International Nuclear Information System (INIS)

Kirbus, F.B.

1977-01-01

When on March 20th, 1974, the nuclear power plant in Atucha, 100 km to the north-west of Argentine's capital Buenos Aires, built by Siemens, was taken into operation, it seemed as if South America had resolutely stepped into the atomic age. In the meantime, Brazil makes preparations for fortified construction of nuclear power plants and its own nuclear industry, and Mexico is accelerating its investigations in order to replace its dwindlung hydroelectric reserves as soon as possible with nuclear energy. The effect of the oil crisis was that Latin American countries, too, take a different look at the peaceful uses of atomic energy. (orig.) [de

A report on recent progress of Central Analytical Laboratory (NRI Rez plc.) for upgrading capabilities for identification of illicit nuclear materials

International Nuclear Information System (INIS)

Malek, Z.; Sus, F.

2002-01-01

Full text: In the first half of the 90's, the State Office for Nuclear Safety (SONS) -- in close co-operation with other state organizations and following the IAEA's extended safeguards system - strengthened its attention to the development of procedures for the characterization of unknown nuclear materials. This problem become important in the context of increasing danger of illicit trafficking of nuclear material which emerged with the political changes in former 'Comecon' countries during late 80's and 90's. Particular attention has been drawn to the upgrade of the counter-potential in possible transit countries situated in Central Europe. The Central Analytical Laboratory as the main Czech institution working in the field of nuclear material analytical chemistry participated in the development and upgrading of analytical procedures for detailed identification and characterization of nuclear material samples. The special methods for the determination of uranium content, isotopic composition, swipe sample analysis, determination of age and long-lived radioisotopes were developed. In second half of the 90's within the IAEA Project entitled 'Special Analytical Methods for Determination of Traces Radioactivity and Detection of Undeclared Nuclear Activities' basic procedures were prepared for the determination of: - selected isotopes of the natural disintegration series in the samples of water, sediments and technological waste solutions after termination of the uranium ores mining, - age of uranium and plutonium materials based on the 230 Th/ 234 Th, 226 Ra/ 234 U and 241 Am/ 241 Pu pairs, studies on the application of the 231 Pa/ 235 U pair were started. In 1998 PHARE PH5.01/95 project, 'Assistance in setting up special analytical services including a data bank for analysis of radioactive substances and nuclear materials of unknown origin' was started. The project was funded from the European Commission's PHARE Programme. The activities were performed at the

CENTRAL NUCLEAR ELECTRIC, A FUTURE OF ROMANIAN ENERGY

Directory of Open Access Journals (Sweden)

Gabriel I. NĂSTASE

2010-05-01

Full Text Available Official statistics show the year increasing the share of electricity produced in nuclear power plants. The most developed nuclear energy programs are: the United States, France, Japan, Germany and Canada. Although Romania was among the first countries in Eastern Europe that had a nuclear research program, switching to nuclear power reactors has been extremely difficult and slow. The implications of this decisionmaking process were the first political and then economic. There were a series of oscillations between Wer system offered by the USSR and the CANDU-PHWR supplied by Canada. Considering nuclear reactors Wer insufficiently protected against a nuclear accident, and the total requested by the former Soviet Union on the nuclear fuel cycle, the decision of us have opted for CANDU reactor, fueled with natural uranium, moderated and cooled with heavy water.

Root cause analysis of relevant events

International Nuclear Information System (INIS)

Perez, Silvia S.; Vidal, Patricia G.

2000-01-01

During 1998 the research work followed more specific guidelines, which entailed focusing exclusively on the two selected methods (ASSET and HPIP) and incorporating some additional human behaviour elements based on the documents of reference. Once resident inspectors were incorporated in the project (and trained accordingly), events occurring in Argentine nuclear power plants were analysed. Some events were analysed (all of them from Atucha I and Embalse nuclear power plant), concluding that the systematic methodology used allows us to investigate also minor events that were precursors of the events selected. (author)

IAEA activities to improve occupational radiation protection in nuclear power plants in Central and Eastern Europe

International Nuclear Information System (INIS)

Gustafsson, M.; Webb, G.A.M.; )

1998-01-01

The following aspects are highlighted: developing standards, ISOE (Information System on Occupational Exposure), providing assistance, and intercomparisons. By means of these coordinated efforts, the IAEA aims at improving occupational radiation protection in nuclear power plants in Central and Eastern Europe. The objective is not only transfer of knowledge and technology but also encouraging cooperation between health physicists in those countries as well as with health physicists in Western countries. (P.A.)

Whole study of nuclear matter collective motion in central collisions of heavy ions of the FOPI detector

International Nuclear Information System (INIS)

Bendarag, A.

1999-01-01

In this work we study the collective phenomena in the central collisions of heavy ions for the Au + Au, Xe + CsI and Ni + Ni systems at incident energies from 150 to 400 MeV/nucleon with the data of the FOPI detector. In order to describe completely the flow of the nuclear matter, we fit the double differential momentum distributions with two-dimensional Gaussian. We study the characteristic parameters of the collective flow (flow range, aspect ratios, flow parameter) versus the charge and the mass of the fragments as well as the incident energy and the centrality of the collisions. The transverse energy is used for selecting the central collisions. The method of the Gaussian fits requires also to reconstruct the reaction plane of the event. Then we correct the parameters for the finite number of particles effects and account for the influence of the acceptance of the detector. We confirm the importance of the thermal motion for the light charge or mass fragments and, conversely, the predominance of the collective motion for the heavy fragments. A common flow angle for all the types of particles is highlighted for the first time, demonstrating the power of the method of the Gaussian fits; The evolution of the other parameters confirms the observations done with other methods of flow analysis. These results should contribute to put constraints on the collision models and to enlarge our knowledge of the properties of the nuclear matter. (author)

Quantification of aquifer properties with surface nuclear magnetic resonance in the Platte River valley, central Nebraska, using a novel inversion method

Science.gov (United States)

Irons, Trevor P.; Hobza, Christopher M.; Steele, Gregory V.; Abraham, Jared D.; Cannia, James C.; Woodward, Duane D.

2012-01-01

Surface nuclear magnetic resonance, a noninvasive geophysical method, measures a signal directly related to the amount of water in the subsurface. This allows for low-cost quantitative estimates of hydraulic parameters. In practice, however, additional factors influence the signal, complicating interpretation. The U.S. Geological Survey, in cooperation with the Central Platte Natural Resources District, evaluated whether hydraulic parameters derived from surface nuclear magnetic resonance data could provide valuable input into groundwater models used for evaluating water-management practices. Two calibration sites in Dawson County, Nebraska, were chosen based on previous detailed hydrogeologic and geophysical investigations. At both sites, surface nuclear magnetic resonance data were collected, and derived parameters were compared with results from four constant-discharge aquifer tests previously conducted at those same sites. Additionally, borehole electromagnetic-induction flowmeter data were analyzed as a less-expensive surrogate for traditional aquifer tests. Building on recent work, a novel surface nuclear magnetic resonance modeling and inversion method was developed that incorporates electrical conductivity and effects due to magnetic-field inhomogeneities, both of which can have a substantial impact on the data. After comparing surface nuclear magnetic resonance inversions at the two calibration sites, the nuclear magnetic-resonance-derived parameters were compared with previously performed aquifer tests in the Central Platte Natural Resources District. This comparison served as a blind test for the developed method. The nuclear magnetic-resonance-derived aquifer parameters were in agreement with results of aquifer tests where the environmental noise allowed data collection and the aquifer test zones overlapped with the surface nuclear magnetic resonance testing. In some cases, the previously performed aquifer tests were not designed fully to characterize

Cooperation in peaceful uses of nuclear energy among Turkey, Caucasian and Central Asian countries

International Nuclear Information System (INIS)

Zafer, A.

2006-01-01

Full text: On the first call for expanding peaceful uses of nuclear energy, Turkey was one of the first countries to start activities in the nuclear field. Turkish Atomic Energy Authority (TAEK) was established in 1956 and became the member of the International Atomic Energy Agency (IAEA) established in 1957 by the United Nations for spreading the use of nuclear energy to contribute peace, health and prosperity throughout the world, in the same year. TAEK was established to support, co-ordinate and perform the activities in peaceful uses of nuclear energy and act as a regulatory body and establish cooperation with other countries and international organizations. In the late 1990's, TAEK, besides building cooperation with various countries, has involved in cooperating with related institutes of Azerbaijan, Kazakhstan, Kyrgyzstan and Uzbekistan for establishment of bilateral and multilateral scientific and technical cooperation in peaceful use of nuclear energy and signed protocols with Academy of Science of Azerbaijan, Nuclear Physics Institute of Kazakhstan, National Academy of Science of Kyrgyzstan and Institute of Nuclear Physics of Uzbekistan Academy of Science. Turkey is a candidate state to join the European Union and has already signed Custom Union Agreement, also part of the Eurasia Region. So, there are significant developments in the cultural, social, technical, economical and trade relations owing to our common historical and cultural values with the countries in the region and Central Asia. These protocols enable parties to organize joint projects, conferences, seminars, training programs, establish laboratories for the joint studies and make joint efforts to seek support from their governments and international organizations for these activities. The joint activities carried out mainly are given as follows: Eurasia Conference on Nuclear Science and Its Application - First Conference organized in the year 2000 in Turkey, Second Conference at Almaty? in

A position paper for a central procurement organization for the nuclear power industry

International Nuclear Information System (INIS)

Hendricks, J.R.

1996-01-01

This paper integrates the results of numerous nuclear utility industry meetings with commercial business practices. The Central Procurement Organization (CPO) is designed to achieve an immediate 30%--50% reduction in total procurement, engineering qualification, warehousing, and distribution cost. Three (3) areas define a CPO success criteria: (1) Lean, credible, and cost-effective issues discussed include facility cost, operational cost, staff expertise, product priorities, warehousing, and distribution, (2) Common technical, commercial, and quality requirement issues discussed include current industry practices and proposed future methodologies, and (3) Financial survivability issues which are the most critical since the CPO must exist during changing internal and external utility environments

Relation between the punctual defects dynamics and irradiation growth in Zr and its alloys

International Nuclear Information System (INIS)

Sarce, A.; Monti, A.M.; Smetniansky-De Grande, N.

1990-01-01

The knowledge of the static properties punctual defects and their interaction with the drains present in the material, such as dislocations and grain borders, is of fundamental importance for the correct prediction of the reactor's components behaviour under irradiation. This work calculates the Zr alloys growth under irradiation and results are compared with the stretching values of the cooling channels measured at the Atucha I nuclear power plant. (Author) [es

Central Bureau for Nuclear Measurements

International Nuclear Information System (INIS)

1991-01-01

The main task of CBNM is defined as the specific programme Nuclear Measurements and Reference Materials. In the field of neutron data for standards, for fission and for fusion application, the nuclear charge distribution and odd-even effects for mass, charge and neutron number in the cold spontaneous fission of 252 Cf were determined. X- and γ-ray emission probabilities were evaluated in the frame of an IAEA coordinated Research Project. The subthermal fission cross section measurements of 235 U, 233 U and 239 Pu, were finalised. The dependence of the experimental weighting function of C 6 D 6 detectors on thickness of several 56 Fe samples was determined. Fusion data studies involved the development of a light-ion telescope with improved time - and energy resolution. Double differential cross-sections of 9 Be were analysed. Radionuclide metrology dealt with the response of silicon detectors, as well as with the standardization of 192 Ir sources. Project Reference Materials reports the EC Certification of nuclear reference materials 210 (PuO 2 ), 523 (Al), 525 (Nb) and 526 (Nb). Progress was achieved in the preparation of dried solid spikes of uranium and plutonium for undiluted reprocessing input solution analysis. 10 B and 6 Li deposits were prepared for a redetermination of the neutron lifetime. Preliminary studies on speciation of trace metals in biological fluids were successful. Radioactive waste barrels were analysed by γ-scanning and blood samples were irradiated with 0.6 MeV neutrons. Exploratory research resulted in first measurements of transition radiation properties

Development of the process of energy transfer from a nuclear Power Plant to an intermediate temperature electrolyse; Desarrollo del proceso de transferencia de energia desde una central nuclear a un electrolizador de temperatura intermedia

Energy Technology Data Exchange (ETDEWEB)

Munoz Cervantes, A.; Cuadrado Garcia, P.; Soraino Garcia, J.

2013-07-01

Fifty million tons of hydrogen are consumed annually in the world in various industrial processes. Among them, the ammonia production, oil refining and the production of methanol. One of the methods to produce it is the electrolysis of water, oxygen and hydrogen. This process needs electricity and steam which a central nuclear It can be your source; Hence the importance of developing the transfer process energy between the two. The objective of the study is to characterize the process of thermal energy transfer from a nuclear power plant to an electrolyzer of intermediate temperature (ITSE) already defined. The study is limited to the intermediate engineering process, from the central to the cell.

Management of Spent Nuclear Fuel from Nuclear Power Plant Reactor

International Nuclear Information System (INIS)

Wati, Nurokhim

2008-01-01

Management of spent nuclear fuel from Nuclear Power Plant (NPP) reactor had been studied to anticipate program of NPP operation in Indonesia. In this paper the quantity of generated spent nuclear fuel (SNF) is predicted based on the national electrical demand, power grade and type of reactor. Data was estimated using Pressurized Water Reactor (PWR) NPP type 1.000 MWe and the SNF management overview base on the experiences of some countries that have NPP. There are four strategy nuclear fuel cycle which can be developed i.e: direct disposal, reprocessing, DUPlC (Direct Use of Spent PWR Fuel In Candu) and wait and see. There are four alternative for SNF management i.e : storage at the reactor building (AR), away from reactor (AFR) using wet centralized storage, dry centralized storage AFR and prepare for reprocessing facility. For the Indonesian case, centralized facility of the wet type is recommended for PWR or BWR spent fuel. (author)

Centralized digital computer control of a research nuclear reactor

International Nuclear Information System (INIS)

Crawford, K.C.

1987-01-01

A hardware and software design for the centralized control of a research nuclear reactor by a digital computer are presented, as well as an investigation of automatic-feedback control. Current reactor-control philosophies including redundancy, inherent safety in failure, and conservative-yet-operational scram initiation were used as the bases of the design. The control philosophies were applied to the power-monitoring system, the fuel-temperature monitoring system, the area-radiation monitoring system, and the overall system interaction. Unlike the single-function analog computers currently used to control research and commercial reactors, this system will be driven by a multifunction digital computer. Specifically, the system will perform control-rod movements to conform with operator requests, automatically log the required physical parameters during reactor operation, perform the required system tests, and monitor facility safety and security. Reactor power control is based on signals received from ion chambers located near the reactor core. Absorber-rod movements are made to control the rate of power increase or decrease during power changes and to control the power level during steady-state operation. Additionally, the system incorporates a rudimentary level of artificial intelligence

Commercial nuclear power 1989

International Nuclear Information System (INIS)

1989-01-01

This report presents historical data on commercial nuclear power in the United States, with projections of domestic nuclear capacity and generation through the year 2020. The report also gives country-specific projections of nuclear capacity and generation through the year 2010 for other countries in the world outside centrally planned economic areas (WOCA). Information is also presented regarding operable reactors and those under construction in countries with centrally planned economies. 39 tabs

Structural integrity analysis of a steam turbine

International Nuclear Information System (INIS)

Villagarcia, Maria P.

1997-01-01

One of the most critical components of a power utility is the rotor of the steam turbine. Catastrophic failures of the last decades have promoted the development of life assessment procedures for rotors. The present study requires the knowledge of operating conditions, component geometry, the properties of materials, history of the component, size, location and nature of the existing flaws. The aim of the present work is the obtention of a structural integrity analysis procedure for a steam turbine rotor, taking into account the above-mentioned parameters. In this procedure, a stress thermal analysis by finite elements is performed initially, in order to obtain the temperature and stress distribution for a subsequent analysis by fracture mechanics. The risk of a fast fracture due to flaws in the central zone of the rotor is analyzed. The procedure is applied to an operating turbine: the main steam turbine of the Atucha I nuclear power utility. (author)

Effectiveness of a large mimic panel in an existing nuclear power plant central control board

International Nuclear Information System (INIS)

Kubota, Ryuji; Satoh, Hiroyuki; Sasajima, Katsuhiro; Kawano, Ryutaro; Shibuya Shinya

1999-01-01

We conducted the analysis of the nuclear power plant (NPP) operators' behaviors under emergency conditions by using training simulators as a joint research project by Japanese BWR groups for twelve years. In the phase-IV of this project we executed two kinds of experiments to evaluate the effectiveness of the interfaces. One was for evaluations of the interfaces such as CRTs with touch screen, a large mimic panel, and a hierarchical annunciator system introduced in the newly developed ABWR type central control board. The other was that we analyzed the operators' behaviors in emergency conditions by using the first generation BWR type central control board which was added new interfaces such as a large display screen and demarcation on the board to help operators to understand the plant. The demarcation is one of the visual interface improvements and its technique is that a line enclosing several components causes them to be perceived as a group.The result showed that both the large display panel Introduced in ABWR central control board and the large display screen in the existing BWR type central control board improved the performance of the NPP operators in the experiments. It was expected that introduction of the large mimic panel into the existing BWR type central control boards would improve operators' performance. However, in the case of actual installation of the large display board into the existing central control boards, there are spatial and hardware constraints. Therefore the size of lamps, lines connecting from symbols of the pumps or valves to the others' will have to be modified under these constraints. It is important to evaluate the displayed information on the large display board before actual installation. We made experiments to solve these problems by using TEPCO's research simulator which is added a large mimic panel. (author)

Thermal phenomenae in nuclear fuel rods

International Nuclear Information System (INIS)

Baigorria, Carlos.

1983-12-01

Thermal phenomenae occurring in a nuclear fuel rod under irradiation are studied. The most important parameters of either steady or transient thermal states are determined. The validity of applying the Fourier's approximation equations to these problems is also studied. A computer program TRANS is developed in order to study the transient cases. This program solves a system of coupled, non-linear partial differential equations, of parabolic type, in cylindrical coordinates with various boundary conditions. The benchmarking of the TRANS program is done by comparing its predictions with the analytical solution of some simplified transient cases. Complex transient cases such as those corresponding to characteristic reactor accidents are studied, in particular for typical pressurized heavy water reactor (PHWR) fuel rods, such as those of Atucha I. The Stefan problem emerging in the case of melting of the fuel element is solved. Qualitative differences between the classical Stefan problem, without inner sources, and that one, which includes sources are discussed. The MSA program, for solving the Stefan problem with inner sources is presented; and furthermore, it serves to predict thermal evolution, when the fuel element melts. Finally a model for fuel phase change under irradiation is developed. The model is based on the dimensional invariants of the percolation theory when applied to the connectivity of liquid spires nucleated around each fission fragment track. Suggestions for future research into the subject are also presented. (autor) [es

Evaluation of Argentinian industrial capacity and of suppliers for nuclear installations

International Nuclear Information System (INIS)

Volman de Tanis, S.

1986-04-01

This work describes and analyses the Argentinian system of purchasing, the laws and decrees which must be observed by the State enterprises and dependent bodies such as the National Atomic Energy Commission (C.N.E.A.). Within the system there are regulations which must be observed by the State suppliers, and to which the purchasing bodies must conform. Furthermore, there is a thorough analysis of the methods implemented before beginning the construction of the third nuclear plant in Argentina, the Atucha II Nuclear Plant. For this, all the existing antecedents were taken into account, insofar as they were related to the prior projects, and an exhaustive questionnaire was elaborated, in which the examined enterprises described in detail their installed capacity, their antecedents, their human resources, etc. The data thus obtained were evaluated and the task was concluded by drawing up lists of the possible enterprises to supply the most diverse components, services or equipment required both by the electrical plant and for any other large scale work. The evaluation obtained would allow an analysis of the foreign offers concerning the entire project and of the possible participation with each bidder of Argentinian industry and engineering. A description is given of the advanced method used to assess bidders with respect to such participation, to assess the replies to the questionnaire, which were analysed in detail, and the weighting factors applied to each item. Also described are some major contracts concluded with enterprises in the country. These contracts relate to the external acquisition of technology for nuclear plants and the essential points are outlined. Also analysed are the results obtained during the execution of the programmes of technology transfer and training, both for parts of different enterprises selected to produce the components, and for the State, through C.N.E.A. and ENACE S.A. 6 refs, 5 tabs

Comparative analysis of C A R A fuel element in argentinean PHWR Argentinas

International Nuclear Information System (INIS)

Brasnarof D; Marino, A. C; Florido, P. C; Daverio, H

2006-01-01

This paper presents an analysis of the thermal mechanical behaviour, fuel consumption and economical estimations of the CARA fuel element in the Atucha and Embalse nuclear power plants, compared with the present fuel performance.The present results show that the expect profit by the use of the CARA fuel element in our reactor guaranties the recovery of fund for its development. Likewise it reduces the number of spent fuel to be storage and treated [es

Current experience with central-station nuclear cogeneration plants

International Nuclear Information System (INIS)

1981-10-01

In considering the potential of the HTGR for nuclear cogeneration, a logical element for investigation is the recent history of nuclear cogeneration experience. Little is found in recent literature; however, the twin nuclear cogeneration plant at Midland is nearing completion and this milestone will no doubt be the basis for a number of reports on the unique cogeneration facility and operating experiences with it. Less well known in the US is the Bruce Nuclear Power Development in Ontario, Canada. Originally designed to cogenerate steam for heavy water production, the Bruce facility is the focus of a major initiative to create an energy park on the shores of Lake Huron. To obtain an improved understanding of the status and implications of current nuclear cogeneration experience, GCRA representatives visited the Ontario Hydro offices in Toronto and subsequently toured the Midland site near Midland, Michigan. The primary purpose of this report is to summarize the results of those visits and to develop a series of conclusions regarding the implications for HTGR cogeneration concepts

Chinese nuclear insurance and Chinese nuclear insurance pool

International Nuclear Information System (INIS)

Gong Zhiqi

2000-01-01

Chinese Nuclear Insurance Started with Daya Bay Nuclear Power Station, PICC issued the insurance policy. Nuclear insurance cooperation between Chinese and international pool's organizations was set up in 1989. In 1996, the Chinese Nuclear Insurance Pool was prepared. The Chinese Nuclear Insurance Pool was approved by The Chinese Insurance Regulatory Committee in May of 1999. The principal aim is to centralize maximum the insurance capacity for nuclear insurance from local individual insurers and to strengthen the reinsurance relations with international insurance pools so as to provide the high quality insurance service for Chinese nuclear industry. The Member Company of Chinese Nuclear Pool and its roles are introduced in this article

Nuclear shell theory

CERN Document Server

de-Shalit, Amos; Massey, H S W

1963-01-01

Nuclear Shell Theory is a comprehensive textbook dealing with modern methods of the nuclear shell model. This book deals with the mathematical theory of a system of Fermions in a central field. It is divided into three parts. Part I discusses the single particle shell model. The second part focuses on the tensor algebra, two-particle systems. The last part covers three or more particle systems. Chapters on wave functions in a central field, tensor fields, and the m-Scheme are also presented. Physicists, graduate students, and teachers of nuclear physics will find the book invaluable.

Professional practices: a short introduction of national nuclear activities to university students; Practicas profesionales: breve incursion laboral de alumnos universitarios en las actividades nucleares

Energy Technology Data Exchange (ETDEWEB)

Martin, Hugo R [Comision Nacional de Energia Atomica, Cordoba(Argentina). Regional Centro

2005-07-01

tiene a cargo la produccion del Oxido de Uranio para el combustible de las centrales nucleares en Atucha 1 y Embalse; las cuestiones relacionadas con la opinion publica han sido una constante preocupacion para la institucion. Por tal motivo, a partir de junio de 2003 se comenzo a desarrollar un Programa de Apertura Institucional (PAI), con la intencion de poner al alcance de la sociedad cordobesa un conocimiento mas profundo sobre las actividades que se desarrollan en el lugar. Entre las multiples acciones implementadas se encuentra el desarrollo de relaciones institucionales con las universidades locales, con el objeto de permitir a alumnos, docentes e investigadores, segun los intereses de cada uno, un acercamiento a la realidad del sector nuclear nacional. A partir de entonces la CNEA ha comenzado a participar activamente de las actividades de la comunidad universitaria local, tanto como miembro permanente en comisiones evaluadoras para el otorgamiento de becas y subsidios del sistema cientifico local, como en consejos asesores del gobierno provincial y otras instancias similares. De las actividades desarrolladas, la que ha mostrado ser muy efectiva para los objetivos propuestos y que motiva estas lineas, ha sido la realizacion de Practicas Profesionales de alumnos del ultimo anio de distintas carreras universitarias en instalaciones de la institucion. (autor)

Multiplicity Fluctuations in Central Nuclear Reaction of Pb + AgBr Events at 158A GeV

Directory of Open Access Journals (Sweden)

Mohammad Ayaz Ahmad

2017-12-01

Full Text Available In the present articles an attempt has been made for the study of multiplicity fluctuations of the secondary charged particles produced in central relativistic nuclear collisions of (Pb+AgBr at an energy 158A GeV, to find the first-order phase transition (QGP to hadron phase state. This study has been carried out for the experimental data along with the theoretical prediction of FRITIOF simulation program and Monte-Carlo (RanMC simulation. The theoretical model predictions were found in good agreements.

Rapid Prototyping of the Central Safety System for Nuclear Risk in ITER

Energy Technology Data Exchange (ETDEWEB)

Scibile, L. [ITER Organization, 13 - St. Paul lez Durance (France); Ambrosino, G.; De Tommasi, G.; Pironti, A. [Euratom-ENEA-CREATE, Universita di Napoli Federico II, Napoli (Italy)

2009-07-01

Full text of publication follows: In the current ITER Baseline design, the Central Safety System for Nuclear Risk (CSS-N) is the safety control system in charge to assure nuclear safety for the plant, personnel and environment. In particular it is envisaged that the CSS shall interface to the plant safety systems for nuclear risk and shall coordinate the individual protection provided by the intervention of these systems by the activation, where required, of additional protections. The design of such a system, together with its implementation, strongly depends on the requirements, particularly in terms of reliability. The CSS-N is a safety critical system, thus its validation and commissioning play a very important role, since the required level of reliability must be demonstrated. In such a scenario, where a new and non-conventional system has to be deployed, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the system requirements, and they will be used to test and validate the control logic. Furthermore these tools can be used to rapid design the safety system and to carry out hardware-in-the-loop (HIL) simulations, which permit to assess the performance of the control hardware against a plant simulator. Both a control system prototype and a safety system oriented plant simulator have been developed to assess first the requirements and then the performance of the CSS-N. In particular the presented SW/HW framework permits to design and verify the CSS protection logics and to test and validate these logics by means of HIL simulations. This work introduces both the prototype and plant simulator architectures, together with the methodology adopted to design and implement these validation tools. (authors)

AP1000, a nuclear central of advanced design; AP1000, una central nuclear de diseno avanzado

Energy Technology Data Exchange (ETDEWEB)

Hernandez M, N.; Viais J, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: nhm@nuclear.inin.mx

2005-07-01

The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

L’ambientalista nucleare Alternative al cambiamento climatico

CERN Document Server

Gómez Cadenas, Juan José

2012-01-01

Che cosa emette più radioattività nell'atmosfera: una centrale nucleare o una centrale termica? Una centrale termica. Che cosa comporta maggior rischio: vivere nei pressi di una centrale nucleare o fumare una sigaretta? Fumare una sola sigaretta equivale al rischio di vivere due anni vicino a una centrale nucleare. Che cosa si fa in un'ora di punta di richiesta energetica se non soffia il vento? Si ricorre a impianti di pompaggio o centrali a gas di riserva. L'energia elettrica non può essere immagazzinata. Quanti aerogeneratori servono per sostituire una centrale nucleare? Circa duemila, dell'ultima generazione. Separati tra di loro dei cinquecento metri necessari perché siano efficienti, la fila dei mulini si estenderebbe da Barcellona a Ginevra, attraversando l'intera Francia. È un errore contrapporre tra loro le energie alternative, sarebbe molto più sensato considerarle alleate nella grande battaglia contro un Signore Oscuro ogni giorno più potente: il cambiamento climatico, che potrebbe benissimo...

Diseño y evaluación de un procedimiento on-line para la biorremediación de aguas radiactivas en centrales nucleares

OpenAIRE

Belinchón Vergara, Julio Angel

2016-01-01

Recientemente se ha demostrado la existencia de microorganismos en las piscinas de almacenamiento de combustible nuclear gastado en las centrales nucleares utilizando técnicas convencionales de cultivo en el laboratorio. Estudios posteriores han puesto de manifiesto que los microorganismos presentes eran capaces de colonizar las paredes de acero inoxidable de las piscinas formando biopelículas. Adicionalmente se ha observado la capacidad de estas biopelículas de retener radionúclidos, lo que ...

Safety performance indicators program

International Nuclear Information System (INIS)

Vidal, Patricia G.

2004-01-01

In 1997 the Nuclear Regulatory Authority (ARN) initiated a program to define and implement a Safety Performance Indicators System for the two operating nuclear power plants, Atucha I and Embalse. The objective of the program was to incorporate a set of safety performance indicators to be used as a new regulatory tool providing an additional view of the operational performance of the nuclear power plants, improving the ability to detect degradation on safety related areas. A set of twenty-four safety performance indicators was developed and improved throughout pilot implementation initiated in July 1998. This paper summarises the program development, the main criteria applied in each stage and the results obtained. (author)

Adequacy features of Nucleoelectrica Argentina Safety Management

Energy Technology Data Exchange (ETDEWEB)

Rapoport, H [Nucleoelectrica Argentina S.A., Buenso Aires (Argentina)

1997-12-01

The Argentine Nuclear Power Plants (NPP) ATUCHA I (357 Mw, SIEMENS) and EMBALSE (648 Mw, CANDU), both of PHWR type, were owned and operated until August 94 by the Comision Nacional de Energia Atomica (CNEA). Until that date, CNEA, the national agency for nuclear R and D, concentrated three activities or roles: Research, Nuclear Regulations and NPP Operation. Since August 1994 NPP`s are owned and operated by a state electrical company (Nucleoelectrica Argentina S.A.) the nuclear utility supplying 15% of the national electrical generation demand. NASA is going to be privatized according to a recent national law regulating nuclear activities. The transition from a research agency to a commercial company requires the introduction of changes in the management of activities. Mention of these changes is limited to those relating to Safety.

Adequacy features of Nucleoelectrica Argentina Safety Management

International Nuclear Information System (INIS)

Rapoport, H.

1997-01-01

The Argentine Nuclear Power Plants (NPP) ATUCHA I (357 Mw, SIEMENS) and EMBALSE (648 Mw, CANDU), both of PHWR type, were owned and operated until August 94 by the Comision Nacional de Energia Atomica (CNEA). Until that date, CNEA, the national agency for nuclear R and D, concentrated three activities or roles: Research, Nuclear Regulations and NPP Operation. Since August 1994 NPP's are owned and operated by a state electrical company (Nucleoelectrica Argentina S.A.) the nuclear utility supplying 15% of the national electrical generation demand. NASA is going to be privatized according to a recent national law regulating nuclear activities. The transition from a research agency to a commercial company requires the introduction of changes in the management of activities. Mention of these changes is limited to those relating to Safety

Nuclear energy in central and eastern Europe

International Nuclear Information System (INIS)

Cognet, G.; Billaud, E.; Battista, L.; Pascal, J.

2010-01-01

Bulgaria, Hungary, Czech Republic, Romania, Slovakia and Slovenia have all nuclear power plants on their soil, their entry to the European Union has counter-balanced the number of member states that are not in favour of nuclear energy. All these countries committed themselves to upgrade their installations to European safety standards. This work is going on and new programs for service life extension and for construction of new units have been launched. All these countries have a strong culture and know-how in nuclear engineering inherited from soviet era. They stay very active in this field, for instance the ALLEGRO project that is carried out by a collaboration between Hungarian, Slovak, Czech research institutes and western partners aims at building the first demonstration plant of the future fourth generation reactor: a fast reactor cooled by gas. The situation of each country plus Croatia (that is a candidate to full E.U. membership) is reviewed. (A.C.)

The Centralized Reliability Data Organization (CREDO); an advanced nuclear reactor reliability, availability, and maintainability data bank and data analysis center

International Nuclear Information System (INIS)

Knee, H.E.

1991-01-01

The Centralized Reliability Data Organization (CREDO) is a data bank and data analysis center, which since 1985 has been jointly sponsored by the US Department of Energy's (US DOE's) Office of Technology Support Programs and Japan's Power Reactor and Nuclear Fuel Development Corporation (PNC). It focuses on reliability, availability and maintainability (RAM) data for components (e.g. valves, pumps, etc.) operating in advanced nuclear reactor facilities. As originally intended, the purpose of the CREDO system was to provide a centralized source of accurate, up-to-date data and information for use in RAM analyses necessary for meeting DOE's data needs in the areas of advanced reactor safety assessments, design and licensing. In particular, creation of the CREDO system was considered an essential element needed to fulfill the DOE Breeder Reactor Safety Program's commitment of 'identifying and exploiting areas in which probabilistic methods can be developed and used in making reactor safety Research and Development choices and optimizing designs of safety systems'. CREDO and its operation are explained. (author)

Energy situation in Latin America and nuclear power

International Nuclear Information System (INIS)

Jinchuk, D.; Deluchi, F.

2006-01-01

Greenhouse Gas emission levels. As an example, C02 emission levels in South America were dominated by a 38% increase in Brazil in the period of 1990-2003. Regarding Nuclear Power generation, at present, only Mexico (1.300 MWe), Brazil (1.900 MWe) and Argentina (950 MWe) have NPP's in operation, representing 5%, 3% and 8% of total electricity generation share respectively. Argentina has 1 reactor (750 MWe) under construction, while Brazil has 1 (1.200 MWe) planned. In the near future Argentina is planning to finish its Third Nuclear Power Plant Atucha 2 for 2010, to extend the life of the CANDU type Embalse NPP for another 20 years and start studies for a future fourth plant in 2015

Nuclear regulation in transition

International Nuclear Information System (INIS)

Tomain, J.P.

1986-01-01

The current state of nuclear regulations in the USA is examined. Since Three Mile Island the regulation of the nuclear power industry has been undergoing a noticeable transition. It will be argued here that the transition is characterized by two indicia. First, the primary focus of state and federal regulators has been on the financial aspects of the industry: this is best seen in the context of decisions allocating the costs of nuclear plant cancellations. Second, decisionmaking power has been decentralized: although the regulatory history of nuclear power demonstrates the tradition of centralized decisionmaking power (i.e., formerly the primary decisionmaking body was the Atomic Energy Commission), now States share decisionmaking power with the Nuclear Regulatory Commission. In Section 1 a brief legislative history of nuclear regulation is presented to establish the assertion that nuclear regulation, both de jure and de facto, was centralized. Next, Section 2 canvasses recent United States Supreme Court opinions regarding nuclear regulation. The Court frequently acts as policymaker through the consequences of its opinions, if not by its intent. In the area of nuclear policymaking, the Court has paid allegiance recently both to the tradition of centralization and to the movement toward decentralization. This dualism is reflected in other federal court decisions as well which will be briefly mentioned. Continuing the analysis of Federal regulation, Section 3 examines the current reform efforts of the NRC. Section 4 presents an examination of State responses to nuclear plant cancellations. In this section, State administrative agency and court decisions will be examined and recent State legislation will be discussed. (author)

Nuclear regulation in transition

Energy Technology Data Exchange (ETDEWEB)

Tomain, J.P. (Cincinnati Univ., OH, US. Coll. of Law)

1986-01-01

The current state of nuclear regulations in the USA is examined. Since Three Mile Island the regulation of the nuclear power industry has been undergoing a noticeable transition. It will be argued here that the transition is characterized by two indicia. First, the primary focus of state and federal regulators has been on the financial aspects of the industry: this is best seen in the context of decisions allocating the costs of nuclear plant cancellations. Second, decisionmaking power has been decentralized: although the regulatory history of nuclear power demonstrates the tradition of centralized decisionmaking power (i.e., formerly the primary decisionmaking body was the Atomic Energy Commission), now States share decisionmaking power with the Nuclear Regulatory Commission. In Section 1 a brief legislative history of nuclear regulation is presented to establish the assertion that nuclear regulation, both de jure and de facto, was centralized. Next, Section 2 canvasses recent United States Supreme Court opinions regarding nuclear regulation. The Court frequently acts as policymaker through the consequences of its opinions, if not by its intent. In the area of nuclear policymaking, the Court has paid allegiance recently both to the tradition of centralization and to the movement toward decentralization. This dualism is reflected in other federal court decisions as well which will be briefly mentioned. Continuing the analysis of Federal regulation, Section 3 examines the current reform efforts of the NRC. Section 4 presents an examination of State responses to nuclear plant cancellations. In this section, State administrative agency and court decisions will be examined and recent State legislation will be discussed.

Outlook for a new design application for the joint union geometry of zircaloy-4 pipe-plug welds

International Nuclear Information System (INIS)

Martinez, R.L; Corso, H.L; Ausas, J; Fernandez, L

2008-01-01

The potential advantages are described and the test results shown for a new joint design for the Zircaloy-4 sheath-plug welding, used in the production of fuel elements for nuclear reactor power generators. Samples taken from sheaths and plugs similar to those used in the Atucha I Reactor were welded using the orbital GTAW process (Gas Tungsten Arc Welding), using a new joint design and equipment that is now applied to the production of high quality welding, with very low levels of contamination. The test results from the experiments with hydrogen content, corrosion, metallographic and traction on samples of these welds are compared with those obtained in simples taken from the conventionally processed fuel elements for Atucha I. The results are also presented for the characterization of samples obtained with the same orbital welding method, but with a smaller protective chamber. This work aimed to verify the influence of the welding chamber size on the contamination with hydrogen. The utility of applying the new design together with the orbital GTAW method to the fabrication process for fuel elements is discussed

Temperature and density of nuclear matter in central CC interactions at P=4.2 GeV/c per nucleon

International Nuclear Information System (INIS)

Didenko, L.A.; Grishin, V.G.; Kowalski, M.; Kuznetsov, A.A.

1984-01-01

An estimation of the temperature and density of nuclear matter in central carbon-carbon interactions at P/A=4.2 GeV/c is presented. It is shown that at energies of about 4 GeV per nucleon it is possible to reach the transitional region between hadronic matter and quark-gluon plasma. The results could be however more convincing if one uses heavier ions than carbon

I and C upgrades resulting from the systematic evaluation program carried out at the Central Nuclear Jose Cabrera

International Nuclear Information System (INIS)

Humphrey, J.C.

1985-01-01

Central Nuclear Jose Cabrera, also known as Zorita, is a 160 MWe nuclear power plant owned and operated by UNION ELECTRICA-FENOSA, S.A. The plant was supplied by Westinghouse Electric Corporation and commissioned in 1968. It features a unique one loop Pressurized Water Reactor design. The Spanish Licensing Authorities requested C.N. Jose Cabrera to carry out a review of their plant. The main objectives were to reassess the safety adequacy of the operating systems, provide a documented comparison of the plant design versus present day criteria and establish a rationale for departures. Another important objective was to provide prompt identification of any significant deficiency. The review known as phase 1 of the C.N. Jose Cabrera Systematic Evaluation Program, was completed and documented by April 1980

International assistance to upgrade the safety of Soviet-designed nuclear power plants. Selected activities in Eastern and Central Europe and the countries of the former Soviet Union

International Nuclear Information System (INIS)

Gillen, V.

1993-12-01

The overview is merely a snapshot of nuclear safety activities to assist the countries of Eastern and Central Europe and the former Soviet Union. While many other activities are planned or ongoing, this publication is meant to provide a general overview of the world community's commitment to improving the safety of Soviet-designed nuclear reactors

Nuclear safety organisation in France

International Nuclear Information System (INIS)

1979-12-01

This report outlines the public authorities responsible for the safety of nuclear installations in France. The composition and responsibilities of the Central Safety Service of Nuclear Installations within the Ministry of Industry, the Institute of Nuclear Protection and Safety within the CEA, the Central Service of Protection Against Ionising Radiation and the Interministerial Committee of Nuclear Safety are given. Other areas covered include the technical safety examination of large nuclear installations, the occurrence of accidents, treatment and control of release of radioactive wastes and decommissioning. The section on regulations covers the authorisation procedure, plant commissioning, release of radioactive effluents, surveillance and protection of workers exposed to ionising radiation. The situation is compared with the USA and the Federal Republic of Germany. A list of commercial nuclear installations in France is given

Final results of the cadmium and spectral ratios obtained inside of the fuel rod positioned in the central position of the IPEN/MB-01 nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Bitelli, Ulysses d' Utra; Mura, Luiz Ernesto C.; Santos, Diogo Feliciano dos, E-mail: ubitelli@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Lambiasi, Beatriz G.N. [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)

2015-07-01

The spectral ratios are very important to determine some nuclear reactors parameters such as reaction rates, fuel lifetime, etc and some safety operational conditions. This study aims to determine the spectral ratios in 2 (two) spatial positions located inside the core of the Nuclear Reactor IPEN/MB-01. These places are at the central position of the nuclear reactor core in an asymptotic neutron flux region. The experiment consists in inserting different activation foil detectors inside an experimental fuel rod. The experimental rod is assembled at the central position of the reactor core. Activation neutron foil detectors of different elements such as {sup 197}Au, {sup 238}U, {sup 45}Sc, {sup 58}Ni, {sup 24}Mg, {sup 47}Ti and {sup 115m}In were used to cover a large range of neutron spectrum. Saturation activity per target nucleus was obtained by gamma spectrometry using a HPGe system. The experimental cadmium ratios compared with values computed by MCNP-4C code show good agreement. (author)

Role of the chemistry in the occupational dose control in nuclear power plants

International Nuclear Information System (INIS)

Blesa, M.A.

1988-01-01

The safety and radioprotection problem in nuclear power plants does not only concern the plants in operation, but it also includes the design, building and decommissioning stages. The factors that determine the radiation field development and the possibility of diminishing them when they reach critical values are presented. Here are considered pressure vessel-heavy water reactors and particularly the radionucleides coming from the products of structural material corrosion. These products are removed by decontaminating compounds and primary circuit systems in general. In accordance with ALARA criterium, the factors that make the decontamination process advisable are analyzed. Firstly, the number of collective doses is discused. In case of heavily contaminated components there is another limitation to the ALARA criterion: the limits of individual dose in a fixed period of time (year, trimester, etc). Among the various decontamination processes-physical or chemical - the stages to follow just in chemical procedures are stated. As Atucha I and II Power Plants are uniques it is necessary to be ready to solve problems. The research and development programs of National Atomic Energy Commission have produced very valuable results such as the 'in situ' activation model and the HERO (high efficient electrochemical removal of oxides) decontamination procedure. (M.E.L.) [es

Development of a simulator for personnel training on nuclear power plants. The authors` experience in the Federal Republic of Germany; Desarrollo de un simulador para entrenamiento de personal de centrales nucleares. Experiencia de los autores en la Republica Federal de Alemania

Energy Technology Data Exchange (ETDEWEB)

Hacker, P; Kogan, A; Garzon, D

1991-12-31

This work describes the stages necessary to carry out the development of a full scope simulator for personnel training on nuclear power plants operation. (Author). [Espanol] Este trabajo describe los pasos o etapas necesarios para llevar adelante el desarrollo de un simulador de amplio alcance (full scope simulator) para entrenamiento de personal de operacion de centrales nucleares. (Autor).

Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

1999-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

2000-08-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-08-15

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

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

Energy Technology Data Exchange (ETDEWEB)

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

2008-12-15

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

Communication dated 11 September 2006 from the Permanent Mission of the Republic of Kazakhstan regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia signed on 8 September 2006

International Nuclear Information System (INIS)

2007-01-01

The Secretariat has received a Note Verbale, dated 11 September 2006, from the Permanent Mission of the Republic of Kazakhstan to the IAEA regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia signed on 8 September 2006 in Semipalatinsk by the leaders of Kazakhstan, Kyrgyzstan, Tajikistan, Turkmenistan and Uzbekistan. The Note Verbale and, as requested therein, the enclosed information regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia, is reproduced herewith for the information of Member States

Instruction of 27 March 1973 concerning implementation of Decree No 73-278 of 13 March 1973 setting up a Higher Council for Nuclear Safety and a Central Service for the Safety of Nuclear Installations

International Nuclear Information System (INIS)

1973-01-01

This Instruction specifies, on the basis of the 1973 Decree, the duties, in particular regarding licensing, of the Central Service for the Safety of Nuclear Installations. The Service is assisted in its work by the Atomic Energy Commission (CEA) and advisory groups.(NEA) [fr

Atucha II: building a 745 MWe pressure-vessel PHWR in the Argentine

International Nuclear Information System (INIS)

Madero, C.C.

1982-01-01

The history of the development of nuclear power in Argentina is outlined. Future policy is described. The aim is to close the fuel cycle and secure a domestic capability to design and construct nuclear power plants. (U.K.)

A cosmic-ray nuclear event with an anomalously strong concentration of energy and particles in the central region

International Nuclear Information System (INIS)

Amato, N.M.; Arata, N.; Maldonado, R.H.C.

1987-01-01

A cosmic-ray-induced nuclear event detected in an emulsion chamber is described. The event consist of 217 shower cores with ΣEγ=1.275 TeV. In a logarithmic scale, energy and particles are emitted most densely at the small lateral distance corresponding to 0.5 mm; 77% of the total energy and 61% of the total multiplicity are inside a radius of 0.65 cm. The shower cores in the central region show exponential-type energy distribution and nonisotropic azimuthal distribution

Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs.

Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

1997-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs

Diffusion tensor analysis with nuclear magnetic resonance in human central nervous system

International Nuclear Information System (INIS)

Nakayama, Naoki

1998-01-01

Nuclear magnetic resonance has been used to measure the diffusivity of water molecules. In central nervous system, anisotropic diffusion, which is characterized by apparent diffusion tensor D app ξ , is thought to be related to neuronal fiber tract orientation. For precise observation of anisotropic diffusion, it is needed to determine the diagonal and off-diagonal elements of D app ξ . Once D app ξ is estimated from a series of diffusion weighted images, a tissue's orthotropic principal axes and diffusivity of each direction are determined from eigenvalues and eigenvectors of D app ξ . There are several methods to represent anisotropic diffusion with D app ξ . Examples are diffusion ellipsoids constructed in each voxel depicting both these principal axes and the mean diffusion length in these directions, trace invariant values and its mapping image, largest eigenvalue, and ratio of largest eigenvalue to the other eigenvalue. In this study, the author investigated practical procedure to analyze diffusion tensor D app ξ using both of spin-echo end echo-planer diffusion weighted imagings with 3-tesla magnetic resonance machine in human brain. The ellipsoid representation provided particularly useful information about microanatomy including neuronal fiber tract orientation and molecular mobility reflective of microstructure. Furthermore, in the lesion of Wallerian degeneration, the loss of anisotropy of local apparent diffusion was observed. It is suggested that the function of axons can be observed via degree of anisotropy of apparent diffusion. Consequently, diffusion tensor analysis is expected to be a powerful, noninvasive method capable of quantitative and functional evaluation of the central nervous system. (author)

A prototype system dynamic model of nuclear and radiological export controls in Central Asia and the Caucasus; enhancing the effectiveness of preventing illicit nuclear material trafficking

International Nuclear Information System (INIS)

Ferguston, C.D.; Ouagrham, S.B.

2002-01-01

An urgent need calls out for improved border security and export control systems in the Central Asian and Caucasus regions to prevent illicit nuclear and radioactive materials trafficking. Effective nuclear and radiological exports controls are essential because these regions contain numerous nuclear facilities and radioactive materials as well as lie at the crossroads between seekers and suppliers of technologies that could be employed in nuclear and radiological weapons. Porous and unprotected borders compound these concerns. Moreover, the states within these regions are struggling with forming new regulations and laws, obtaining sufficient portal monitoring equipment, training customs and border security personnel, and coordinating these activities with neighboring states. Building this infrastructure all at once can severely task any government. Thus, unsurprisingly, most of these states have inadequate export control and border security systems. To enable each state in these regions determine how to better prevent illicit nuclear and radiological materials trafficking, the authors have developed a prototype system dynamics model focused on evaluating and improving of effectiveness of export controls. System dynamics modeling, a management tool that grew out of the field of system engineering and nonlinear dynamics, uses two structures: causal loop diagrams and stock and flow diagrams. The former shows how endogenous systematic factors interact with each other to produce feedback mechanisms that results in either balancing or reinforcing loops. A classic example is a arms race, modeled as a vicious cycle or reinforcing loop. In addition to interacting with each other, causal loops influence the flow of stock, which is material concern. In the export control system dynamics model, the stock represents nuclear and radioactive materials. System dynamics modelling is an iterative process that is continually modified by user input. Therefore, export control

Experience with a mobile data storage device for transfer of studies from the critical care unit to a central nuclear medicine computer

International Nuclear Information System (INIS)

Cradduck, T.D.; Driedger, A.A.

1981-01-01

The introduction of mobile scintillation cameras has enabled the more immediate provision of nuclear medicine services in areas remote from the central nuclear medicine laboratory. Since a large number of such studies involve the use of a computer for data analysis, the concurrent problem of how to transmit those data to the computer becomes critical. A device is described using hard magnetic discs as the recording media and which can be wheeled from the patient's bedside to the central computer for playback. Some initial design problems, primarily associated with the critical timing which is necessary for the collection of gated studies, were overcome and the unit has been in service for the past two years. The major limitations are the relatively small capacity of the discs and the fact that the data are recorded in list mode. These constraints result in studies having poor statistical validity. The slow turn-around time, which results from the necessity to transport the system to the department and replay the study into the computer before analysis can begin, is also of particular concern. The use of this unit has clearly demonstrated the very important role that nuclear medicine can play in the care of the critically ill patient. The introduction of a complete acquisition and analysis unit is planned so that prompt diagnostic decisions can be made available within the intensive care unit. (author)

Swedish support programme on nuclear non-proliferation in Central and Eastern Europe and Central Asia

Energy Technology Data Exchange (ETDEWEB)

Ek, P.; Andersson, Sarmite [Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Wredberg, L. [ILG Consultant Ltd., Vienna (Austria)

2000-06-15

At the request of the Swedish Government, the Swedish Nuclear Power Inspectorate has established a support and co-operation programme in the area of nuclear non-proliferation with Russia and several of the republics of the former Soviet Union. The Programme was initiated in 1991 and an overall goal is to accomplish national means and measures for control and protection of nuclear material and facilities, in order to minimise the risk of proliferation of nuclear weapons and illicit trafficking of nuclear material and equipment. The objective of the Swedish Support Programme is to help each, so called, recipient State to be able to, independently and without help from outside, take the full responsibility for operating a national non-proliferation system and thereby fulfil the requirements imposed through the international legal instruments. This would include both the development and implementation of a modern nuclear legislation system, and the establishment of the components making up a national system for combating illicit trafficking. The support and co-operation projects are organised in five Project Groups (i.e. nuclear legislation, nuclear material control, physical protection, export/import control, and combating of illicit trafficking), which together cover the entire non-proliferation area. Up till June 2000, support and co-operation projects, completed and on-going, have been carried out in ten States, namely Armenia, Azerbaijan, Belarus, Georgia, Kazakstan, Latvia, Lithuania, Moldova, Russia and Ukraine. Furthermore, programmes have been initiated during the first part of 2000 with Estonia, Uzbekistan, Kyrgyzstan and Tajikistan. In addition, assistance has been given to Poland on a specific nuclear material accountancy topic. All projects are done on request by and in co-operation with these States. The total number of projects initiated during the period 1991 to June 2000 is 109, thereof 77 have been completed and 32 are currently on-going. It is the

Swedish support programme on nuclear non-proliferation in Central and Eastern Europe and Central Asia

International Nuclear Information System (INIS)

Ek, P.; Andersson, Sarmite; Wredberg, L.

2000-06-01

At the request of the Swedish Government, the Swedish Nuclear Power Inspectorate has established a support and co-operation programme in the area of nuclear non-proliferation with Russia and several of the republics of the former Soviet Union. The Programme was initiated in 1991 and an overall goal is to accomplish national means and measures for control and protection of nuclear material and facilities, in order to minimise the risk of proliferation of nuclear weapons and illicit trafficking of nuclear material and equipment. The objective of the Swedish Support Programme is to help each, so called, recipient State to be able to, independently and without help from outside, take the full responsibility for operating a national non-proliferation system and thereby fulfil the requirements imposed through the international legal instruments. This would include both the development and implementation of a modern nuclear legislation system, and the establishment of the components making up a national system for combating illicit trafficking. The support and co-operation projects are organised in five Project Groups (i.e. nuclear legislation, nuclear material control, physical protection, export/import control, and combating of illicit trafficking), which together cover the entire non-proliferation area. Up till June 2000, support and co-operation projects, completed and on-going, have been carried out in ten States, namely Armenia, Azerbaijan, Belarus, Georgia, Kazakstan, Latvia, Lithuania, Moldova, Russia and Ukraine. Furthermore, programmes have been initiated during the first part of 2000 with Estonia, Uzbekistan, Kyrgyzstan and Tajikistan. In addition, assistance has been given to Poland on a specific nuclear material accountancy topic. All projects are done on request by and in co-operation with these States. The total number of projects initiated during the period 1991 to June 2000 is 109, thereof 77 have been completed and 32 are currently on-going. It is the

A study on the role adjustment between central and local government II

International Nuclear Information System (INIS)

Yuk, D. I.; Ahn, S. K.

2004-01-01

The goal of this research is to construct new system and feasible action plans by seeking solutions for more effective redistribution of the nuclear regulatory roles between central and local governments. From 1995 on, since local autonomy system has been reimplemented in Korea, it is imperative to develop reformative alternatives for the decentralization of powers between central and local governments. The core devolution is to redistribute administrative roles and functions which have been centralized, toward both self-governing bodies and communities including NGO. The level of devolution in nuclear regulatory system depends on how to redistribute nuclear related roles and functions among central/local government with KINS. Therefore, it is very important to examine general principles criteria and type of domestic/foreign role adjustment for effective/rational/democratic nuclear regulation. Based on previous model and system proposed, role adjustment action plans are reviewed taking account of the nuclear environmental changes in the localization era. In the long run, the result of this research will be expected to utilize the optimal and democratic regulatory system in Korea

A study on the role adjustment between central and local government II

Energy Technology Data Exchange (ETDEWEB)

Yuk, D. I. [Chungnam National University, Taejon (Korea, Republic of); Ahn, S. K. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

2004-07-01

The goal of this research is to construct new system and feasible action plans by seeking solutions for more effective redistribution of the nuclear regulatory roles between central and local governments. From 1995 on, since local autonomy system has been reimplemented in Korea, it is imperative to develop reformative alternatives for the decentralization of powers between central and local governments. The core devolution is to redistribute administrative roles and functions which have been centralized, toward both self-governing bodies and communities including NGO. The level of devolution in nuclear regulatory system depends on how to redistribute nuclear related roles and functions among central/local government with KINS. Therefore, it is very important to examine general principles criteria and type of domestic/foreign role adjustment for effective/rational/democratic nuclear regulation. Based on previous model and system proposed, role adjustment action plans are reviewed taking account of the nuclear environmental changes in the localization era. In the long run, the result of this research will be expected to utilize the optimal and democratic regulatory system in Korea.

National independence and nonproliferation in the new states of Central Asia

Energy Technology Data Exchange (ETDEWEB)

Gleason, G.

1993-12-01

Five independent states emerged in Central Asia from the breakup of the USSR. One of these states, Kazakhstan, possesses nuclear weapons. The other four of these states, Kyrgyzstan, Tajikistan, Turkmenistan, and Uzbekistan, are not known to possess nuclear weapons, however they occupy a geostrategic position which makes them important to non-proliferation efforts. The present report profiles the capabilities and intentions of these four Central Asian states. The analysis of capabilities suggests that none of these states has the capability to develop a usable nuclear weapon. However, all of these countries-- especially Uzbekistan--have components of the old Soviet nuclear weapons complex which are now orphans. They have no use for these facilities and must either re-profile them, destroy them, or transfer them. The analysis of intentions suggests that the dynamics of national independence have created a situation in which Uzbekistan has hegemonic designs in the region. Implications for retarding nuclear proliferation in the Central Asian region are examined. Opportunities for outside influence are assessed.

Pulsed nuclear power plant

International Nuclear Information System (INIS)

David, C.V.

1986-01-01

This patent describes a nuclear power plant. This power plant consists of: 1.) a cavity; 2.) a detonatable nuclear device in a central region of the cavity; 3.) a working fluid inside of the cavity; 4.) a method to denote a nuclear device inside of the cavity; 5.) a mechanical projection from an interior wall of the cavity for recoiling to absorb a shock wave produced by the detonation of the nuclear device and thereby protecting the cavity from damage. A plurality of segments defines a shell within the cavity and a plurality of shock absorbers, each connecting a corresponding segment to a corresponding location on the wall of the cavity. Each of these shock absorbers regulate the recoil action of the segments; and 6.) means for permitting controlled extraction of a quantity of hot gases from the cavity produced by the vaporization of the working fluid upon detonation of the nuclear device. A method of generating power is also described. This method consists of: 1.) introducing a quantity of water in an underground cavity; 2.) heating the water in the cavity to form saturated steam; 3.) detonating a nuclear device at a central location inside the cavity; 4.) recoiling plate-like elements inside the cavity away from the central location in a mechanically regulated and controlled manner to absorb a shock wave produced by the nuclear device detonation and thereby protect the underground cavity against damage; 5.) extracting a quantity of superheated steam produced by the detonation of the nuclear device; and 6.) Converting the energy in the extracted superheated steam into electrical power

Molecular species identification of Central European ground beetles (Coleoptera: Carabidae using nuclear rDNA expansion segments and DNA barcodes

Directory of Open Access Journals (Sweden)

Raupach Michael J

2010-09-01

Full Text Available Abstract Background The identification of vast numbers of unknown organisms using DNA sequences becomes more and more important in ecological and biodiversity studies. In this context, a fragment of the mitochondrial cytochrome c oxidase I (COI gene has been proposed as standard DNA barcoding marker for the identification of organisms. Limitations of the COI barcoding approach can arise from its single-locus identification system, the effect of introgression events, incomplete lineage sorting, numts, heteroplasmy and maternal inheritance of intracellular endosymbionts. Consequently, the analysis of a supplementary nuclear marker system could be advantageous. Results We tested the effectiveness of the COI barcoding region and of three nuclear ribosomal expansion segments in discriminating ground beetles of Central Europe, a diverse and well-studied invertebrate taxon. As nuclear markers we determined the 18S rDNA: V4, 18S rDNA: V7 and 28S rDNA: D3 expansion segments for 344 specimens of 75 species. Seventy-three species (97% of the analysed species could be accurately identified using COI, while the combined approach of all three nuclear markers provided resolution among 71 (95% of the studied Carabidae. Conclusion Our results confirm that the analysed nuclear ribosomal expansion segments in combination constitute a valuable and efficient supplement for classical DNA barcoding to avoid potential pitfalls when only mitochondrial data are being used. We also demonstrate the high potential of COI barcodes for the identification of even closely related carabid species.

Molecular species identification of Central European ground beetles (Coleoptera: Carabidae) using nuclear rDNA expansion segments and DNA barcodes.

Science.gov (United States)

Raupach, Michael J; Astrin, Jonas J; Hannig, Karsten; Peters, Marcell K; Stoeckle, Mark Y; Wägele, Johann-Wolfgang

2010-09-13

The identification of vast numbers of unknown organisms using DNA sequences becomes more and more important in ecological and biodiversity studies. In this context, a fragment of the mitochondrial cytochrome c oxidase I (COI) gene has been proposed as standard DNA barcoding marker for the identification of organisms. Limitations of the COI barcoding approach can arise from its single-locus identification system, the effect of introgression events, incomplete lineage sorting, numts, heteroplasmy and maternal inheritance of intracellular endosymbionts. Consequently, the analysis of a supplementary nuclear marker system could be advantageous. We tested the effectiveness of the COI barcoding region and of three nuclear ribosomal expansion segments in discriminating ground beetles of Central Europe, a diverse and well-studied invertebrate taxon. As nuclear markers we determined the 18S rDNA: V4, 18S rDNA: V7 and 28S rDNA: D3 expansion segments for 344 specimens of 75 species. Seventy-three species (97%) of the analysed species could be accurately identified using COI, while the combined approach of all three nuclear markers provided resolution among 71 (95%) of the studied Carabidae. Our results confirm that the analysed nuclear ribosomal expansion segments in combination constitute a valuable and efficient supplement for classical DNA barcoding to avoid potential pitfalls when only mitochondrial data are being used. We also demonstrate the high potential of COI barcodes for the identification of even closely related carabid species.

Collective phenomena in non-central nuclear collisions

International Nuclear Information System (INIS)

Voloshin, Sergei A.; Poskanzer, Arthur M.; Snellings, Raimond

2008-01-01

Recent developments in the field of anisotropic flow in nuclear collision are reviewed. The results from the top AGS energy to the top RHIC energy are discussed with emphasis on techniques, interpretation, and uncertainties in the measurements

Collective phenomena in non-central nuclear collisions

Energy Technology Data Exchange (ETDEWEB)

Voloshin, Sergei A.; Poskanzer, Arthur M.; Snellings, Raimond

2008-10-20

Recent developments in the field of anisotropic flow in nuclear collision are reviewed. The results from the top AGS energy to the top RHIC energy are discussed with emphasis on techniques, interpretation, and uncertainties in the measurements.

The nuclear contribution

International Nuclear Information System (INIS)

Jones, P.M.S.

1984-01-01

The subject is discussed under the headings: background; nuclear reactors (reactor types; reactor choices; the present position; the future); reprocessing and waste management; uranium resources and the potential for thermal fission reactors; the fast reactor; thorium; other applications (than the central generation of electricity) of nuclear power; fusion; conclusion. (U.K.)

Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

Energy Technology Data Exchange (ETDEWEB)

Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

1966-02-15

matieres nucleaires ne se limite pas S de simples travaux d'inventaire mais sert de base a beaucoup d'autres activites qui font partie integrante du programme d'operations de tout reacteur, par exemple les expeditions de combustible irradie, le traitement chimique du combustible epuise et la comptabilite du combustible recupere et des matieres produites au cours du fonctionnement du reacteur, et l'institution et l'application d'un regime d'assurance satisfaisant. (author) [Spanish] Combustible relativamente nuevo y sumamente valioso para la produccion de energia electrica, el uranio requiere un control muy minucioso desde el momento en que la direccion de una central asume la responsabilidad financiera inherente a su posesion hasta que como combustible parcialmente agotado se transfiere a otra instalacion en la que se recupera la parte que no se ha consumido. Antes de que se descubriera la posibilidad de emplear la energia nuclear para producir electricidad, la mayor parte de las empresas que actualmente explotan centrales nucleares explotaban centrales alimentadas con combustibles fosiles y hablan establecido sistemas de control relativamente completos y adecuados para los combustibles de ese tipo. Los responsables de las centrales nucleoelectricas deben disponer de sistemas no menos adecuados para controlar los materiales nucleares especiales que utilizan. La explotacion de los reactores de potencia no es una ciencia antigua, pero durante el tiempo relativamente corto que ha transcurrido desde que se inicio su empleo los ingenieros y hombres de ciencia han mejorado continuamente el diseflo del equipo y los metodos de trabajo con objeto de disminuir los costos de produccion y de lograr que las centrales nucleares puedan competir en el plano economico con las centrales clasicas. La administracion de los materiales nucleares debe efectuarse con metodos modernos y eficientes a fin de que los adelantos tecnologicos que han permitido reducir los costos no resulten inutiles

Starting Point, Keys and Milestones of a Computer Code for the Simulation of the Behaviour of a Nuclear Fuel Rod

Directory of Open Access Journals (Sweden)

Armando C. Marino

2011-01-01

Full Text Available The BaCo code (“Barra Combustible” was developed at the Atomic Energy National Commission of Argentina (CNEA for the simulation of nuclear fuel rod behaviour under irradiation conditions. We present in this paper a brief description of the code and the strategy used for the development, improvement, enhancement, and validation of a BaCo during the last 30 years. “Extreme case analysis”, parametric (or sensitivity, probabilistic (or statistic analysis plus the analysis of the fuel performance (full core analysis are the tools developed in the structure of BaCo in order to improve the understanding of the burnup extension in the Atucha I NPP, and the design of advanced fuel elements as CARA and CAREM. The 3D additional tools of BaCo can enhance the understanding of the fuel rod behaviour, the fuel design, and the safety margins. The modular structure of the BaCo code and its detailed coupling of thermo-mechanical and irradiation-induced phenomena make it a powerful tool for the prediction of the influence of material properties on the fuel rod performance and integrity.

Accelerating the global nuclear renaissance: the central challenge of sustainable development

International Nuclear Information System (INIS)

Ritch, J.

2006-01-01

The rebirth of nuclear energy has become an unmistakable reality that is gathering speed and momentum on the full world stage. All around the world, old-school anti-nuclear environmentalism is being eclipsed by a new realism that recognises nuclear energy's essential virtue: its capacity to deliver cleanly generated power safely, reliably, and on a massive scale. For serious environmentalists, the real challenge is that nuclear energy is not yet growing fast enough to play its needed role in the clean-energy revolution our world so desperately needs. A fair assessment shows that not one of the commonly cited ''public concerns'' poses a reasonable obstacle to a global expansion of nuclear power: Proliferation, Operational Safety, Cost Reduction, Waste Management. In three areas, governments must take decisive action to grow the nuclear industry: (1) Construct a comprehensive global regime to curtail greenhouse emissions; (2) Elevate nuclear investment to a national and international policy priority; and (3) Support educational development of the nuclear profession for an expanded global role. The global nuclear industry will be indispensable if humanity is to preserve the environment that enabled civilisation to evolve. Governments must emerge from postures of timidity and equivocation to act decisively in support of that industry. Our world is in dire peril, and we have no time to lose

San Rafael mining and fabrication complex today

International Nuclear Information System (INIS)

Navarra, Pablo; Aldebert, Sergio R.

2005-01-01

In Mendoza province, 35 km West San Rafael city, is located a CNEA installation for uranium ore extraction and concentration: the San Rafael Mining and Fabrication Complex. By the middle of the nineties, as a consequence of the very low prices of uranium concentrate in the international market and of the high internal production costs, uranium extraction was stopped. To day, the international price of the concentrate had a very important increase and the Government has decided the completion of the Atucha II Nuclear Power Station construction. Moreover, studies have been started for new nuclear power plants. In such circumstances the reactivation of the Complex will make sure the uranium supply for our nuclear power stations, contributing to the improvement of the energy generation mix in our country. (author) [es

Central nuclear almirante Alvaro Alberto: study on the phytoplanktonic variation in the region of unity 1 - Angra dos Reis - RJ

International Nuclear Information System (INIS)

Souza, C.A.F. de; Pessoa, M.A.R.; Utchitel, S.

1988-01-01

By according of ''staff'' which has elaborated the first works in phitoplankton, in initial phasis (before operation) of Central Nuclear Almirante Alvaro Alberto - CNAAA Unidade 1, Angra dos Reis, Rio de Janeiro, Brazil we carry out a search about physic - chemicals parameters at same area, during the times of 11 months, too. The efluent region presents a phytoplanktonic comunity of reasonable environmental conditions. The evaluation of biological parameters, or in the words, a natural environment in equilibrium. (author) [pt

Activities of nuclear human resource development in nuclear industry

International Nuclear Information System (INIS)

Tsujikura, Yonezo

2010-01-01

Since 2007, the JAIF (Japan Atomic Industrial Forum) had established the nuclear energy human resource development council to make analysis of the issue on nuclear human resource development. The author mainly contributed to develop its road map as a chairman of working group. Questionnaire survey to relevant parties on issues of nuclear human resource development had been conducted and the council identified the six relevant issues and ten recommendations. Both aspects for career design and skill-up program are necessary to develop nuclear human resource at each developing step and four respective central coordinating hubs should be linked to each sector participating in human resource development. (T. Tanaka)

Elecnuc. Nuclear power plants worldwide; Elecnuc. Les centrales nucleaires dans le monde

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

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

Central Safety Department. Annual report 1986

International Nuclear Information System (INIS)

Kiefer, H.; Koenig, L.A.

1987-03-01

The Safety Officer and the Security Officer are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the safeguards of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH (KfK). To fulfill these functions they rely on the assistance of the Central Safety Department. The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of HT in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. The report gives details of the different duties, indicates the results of 1986 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

Validation of finite element code DELFIN by means of the zero power experiences at the nuclear power plant of Atucha I; Convalidacion del codigo DELFIN por medio de las experiencias a potencia cero de la central nuclear Atucha I

Energy Technology Data Exchange (ETDEWEB)

Grant, C R [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

1997-12-31

Code DELFIN, developed in CNEA, treats the spatial discretization using heterogeneous finite elements, allowing a correct treatment of the continuity of fluxes and currents among elements and a more realistic representation of the hexagonal lattice of the reactor. It can be used for fuel management calculation, Xenon oscillation and spatial kinetics. Using the HUEMUL code for cell calculation (which uses a generalized two dimensional collision probability theory and has the WIMS library incorporated in a data base), the zero power experiences performed in 1974 were calculated. (author). 8 refs., 9 figs., 3 tabs.

Spectrophotometric determination of uranium traces in zircaloy-4 and zirconium sponge

International Nuclear Information System (INIS)

Correia, R.J.; Weber de D'Alessio, Ana; Zucal, R.H.

1980-01-01

The uranium contents of the zircaloy-4 which is used for the fabrication of the fuel cans for the PHWR Atucha and Embalse nuclear power stations must not exceed 3.ppM. A method was developed for performing that control, involving the separation of the uranium from its matrix by partition chromatography and its determination by spectrophotometry with Arsenazo (III). This method is applied within the range of 0.2 to 10 ppM, obtaining a relative standard deviation of 6% for U contents of 3 ppm. (M.E.L.) [es

Vibration monitoring of pressure vessel in Atucha-1 power plant

International Nuclear Information System (INIS)

Belinco, C.; Pastorini, A.; Martin Ghiselli, A.; Sacchi, M.

1994-01-01

The Vibration Monitoring Systems are described to obtain information about the mechanical state of different components in the main coolant system of nuclear power plants to ensure that changes in the mechanical integrity of this components are detected at an early point in time, even during operation. 9 figs

Safety Regulations in organizations and enterprises under supervision of Federal environmental, industrial and nuclear supervision service of Russia (Rostechnadzor), Central Region. Short overview of sites which potentially are dangerous for terrorist threat

International Nuclear Information System (INIS)

Gasselblat, A.D.

2010-01-01

Full text: Federal environmental, industrial and nuclear supervision service of Russia carries out inspections over safety of atomic energy sites on the territory of Russian Federation, which are used for peaceful purposes. Currently under control of Supervision Service on the whole territory of Russia 2000 (2179) (1.) organizations (enterprises), business entities in the field of atomic energy use (industry, medicine, scientific research, agriculture, geological survey, education and etc.) using in their activity radionuclide sources. Approximately 6000 (5955) territorially separated or technologically independent radiation-dangerous sites are counted in their structure, which are dealing with radionuclides. The total number of sealed radionuclide sources is more than 1000 pieces. More than thousands radiation-dangerous entities are dealing with unsealed radionuclide sources and radioactive wastes. At such scales of activity, when evident dynamic of source movement is observed, it is very important for regulatory authority to update information on source location, condition, safe use and security, as well as physical protection and prevention of its use in terrorist purposes. In its structure industrial and nuclear supervision service of Russia has 7 big subdivisions (according to directions regulation in the field of atomic energy use) - inter regional territory administrations on control over nuclear and radiation safety, ensuring control over whole territory of Russian Federation, each in within its border of Federal region of Russian Federation. Central inter regional territory administration on control over nuclear and radiation safety is the biggest according to its personnel and number of controlled sites by territorial subdivision of Federal environmental, industrial and nuclear supervision service of Russia (in the field of atomic energy use, according to Federal Law dated 21.11.1995, №170-Federal Low On atomic energy use) and carries out its activity

A study on the role adjustment between central and local government

Energy Technology Data Exchange (ETDEWEB)

Yook, Dong Il; Ji, Min Gu; Yun, Yo Il; Kim, Yong Cheon; Lee, Sang In; Lee, Chan Won [Chunnam National Univ., Taejon (Korea, Republic of)

2003-02-15

The goal of this study is to develop new model and feasible alternatives by seeking solutions for rational redistribution of the nuclear regulatory roles between central and local governments. Since local autonomy system has been reimplemented in Korea, It is imperative to improve reform measures for the decentralization of power between central and local governments. The core of decentralization is to redistribute administrative authorities and roles which have been centralized, toward both self-governing body and communities. The level of decentralization depends on how to redistribute roles and functions between central and local government. Therefore, it is necessary to examine principle and type of domestic foreign role adjustment for effective nuclear regulation. Based on three prerequisite studies, role adjustment model for more effective nuclear regulation is made taking account of the current domestic environments and conditions. In the long run, the outcomes of this study will be expected to improve the optimal and democratic regulatory system in Korea.

A study on the role adjustment between central and local government

International Nuclear Information System (INIS)

Ahn, S. K.; Yook, D. R.

2003-01-01

The goal of this study is to develop new model and feasible alternatives by seeking solutions for national redistribution of the nuclear regulatory roles between central and local governments. Since local autonomy system has been reimplemented in Korea, it is imperative to improve reform measures for the decentralization of powers between central and local governments. The core of decentralization is to redistribute administrative authorities and roles which have been centralized, toward both self-governing body and communities. The level of decentralization depends on how to redistribute roles and functions between central and local government. Therefore, it is necessary to examine principle and type of domestic foreign role adjustment for effective nuclear regulation. Based on three prerequisite studies, role adjustment model for more effective nuclear regulation is made taking account of the current domestic environments and conditions. In the long run, the outcomes of this study will be expected to improve the optimal and democratic regulatory system in Korea

The nuclear power decisions

International Nuclear Information System (INIS)

Williams, R.

1980-01-01

Nuclear power has now become highly controversial and there is violent disagreement about how far this technology can and should contribute to the Western energy economy. More so than any other energy resource, nuclear power has the capacity to provide much of our energy needs but the risk is now seen to be very large indeed. This book discusses the major British decisions in the civil nuclear field, and the way they were made, between 1953 and 1978. That is, it spans the period between the decision to construct Calder Hall - claimed as the world's first nuclear power station - and the Windscale Inquiry - claimed as the world's most thorough study of a nuclear project. For the period up to 1974 this involves a study of the internal processes of British central government - what the author terms 'private' politics to distinguish them from the very 'public' or open politics which have characterised the period since 1974. The private issues include the technical selection of nuclear reactors, the economic arguments about nuclear power and the political clashes between institutions and individuals. The public issues concern nuclear safety and the environment and the rights and opportunities for individuals and groups to protest about nuclear development. The book demonstrates that British civil nuclear power decision making has had many shortcomings and concludes that it was hampered by outdated political and administrative attitudes and machinery and that some of the central issues in the nuclear debate were misunderstood by the decision makers themselves. (author)

Nuclear Law Bulletin : Index Nbs. 1 to 55

International Nuclear Information System (INIS)

Anon.

1995-01-01

In this book are given the laws concerning the following subjects : the field of application of the Nuclear Conventions, international conventions relating to radioactive marine pollution, international co-operation in the field of radioactive transfrontier pollution, compensation for nuclear damage in OECD Member Countries, spent fuel and radioactive waste management issues, the regulation of food irradiation, the accident at Chernobyl-economic damage and its compensation in Western Europe, development and harmonization of intervention levels in case of a nuclear accident, three negotiations concerning nuclear law, potential liability of contractors working on nuclear safety improvement projects in Central and Eastern Europe, overview of nuclear legislation in Central and Eastern Europe countries, problems raised by the application of the Nuclear Third Party Liability Conventions to radioactive waste repositories. (O.L.)

In service inspection of the reactor pressure vessel coolant and moderator nozzles at Atucha 1. 1998/1999 outages

International Nuclear Information System (INIS)

Antonaccio, Carlos; Conde, Alberto; Fittipaldi, Andres H.; Maniotti, Jorge; Moliterno, Gabriel E.

2000-01-01

During the August 1998 and the August 1999 Atucha 1 outages, two areas were inspected on the Reactor Pressure Vessel: the nozzle inner radii and the nozzle shell welds on all 3 moderator nozzles and all 4 main coolant nozzles. The inspections themselves were carried out by Mitsui Babcock Energy Limited from Scotland. The coordination, maintenance assistant and mounting of the manipulator devices over the nozzles were carried out by NASA personnel. Although it was not the first time the nozzle shell welds were inspected, due to the technologies advances in the ultrasonic field and in the inspection manipulators (magnetic ones), it was possible to inspect more volume than in previous inspections. In the other hand, it was the first time NASA was able to inspect the inner radii. In this last case the mayor problems to inspect them were the nozzles geometry and the small space available to install manipulators. The result of the inspections were: 1) There were no reportable indications at any of the inner radii inspected; 2) The inspection of nozzle to shell welds in main-coolant nozzles R3 and R4 detected flaws (one in each nozzle) which were reported as exceeding the dimensions specified as the acceptance level under Table IWB 3512-1, Section XI of the ASME code. Subsequent analysis requested by NASA and performed by Mitsui Babcock, demonstrated that the flaws were over dimensioned and could be explained as due to 'point' flaws. The analysis was based on theoretical mathematic model and experimental trials. Therefore their dimension were under the acceptance level of the ASME XI code. Although the Mitsui Babcock analysis, and at the same time it was in progress, it was assumed that the flaws were as they were originally presented (exceeding the acceptance level). NASA asked SIEMENS/KWU, the designer of the plant, to perform the fracture assessment according to ASME XI App. A. The assessment shows that the expected crack growth is negligibly small and the safety

Ground acceleration in a nuclear power plant; Aceleracion del suelo en una central nuclear

Energy Technology Data Exchange (ETDEWEB)

Pena G, P.; Balcazar, M.; Vega R, E., E-mail: pablo.pena@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2015-09-15

A methodology that adopts the recommendations of international organizations for determining the ground acceleration at a nuclear power plant is outlined. Systematic presented here emphasizes the type of geological, geophysical and geotechnical studies in different areas of influence, culminating in assessments of Design Basis earthquake and the earthquake Operating Base. The methodology indicates that in regional areas where the site of the nuclear power plant is located, failures are identified in geological structures, and seismic histories of the region are documented. In the area of detail geophysical tools to generate effects to determine subsurface propagation velocities and spectra of the induced seismic waves are used. The mechanical analysis of drill cores allows estimating the efforts that generate and earthquake postulate. Studies show that the magnitude of the Fukushima earthquake, did not affect the integrity of nuclear power plants due to the rocky settlement found. (Author)

Jose Cabrera NPP; Central Nuclear Jose Cabrera

Energy Technology Data Exchange (ETDEWEB)

Diez, P.

2004-07-01

During 2003, the Jose Cabrera nuclear power plant (JCNPP) operated without any incidents involving an undue risk to the population or environment. The year 2003 was the Plant's 35th year of operation, and during that time it has provided 33.209 million kilowatt-hours to the electric grid. The Plant set a record for continuous operation with 386 days of uninterrupted operation. The Plant had an outage for the 27th refueling and for equipment and systems maintenance, inspection and testing activities. The Plant reported nine events to the Administration that were classified as zero on the International Nuclear Event Scale (INES) and another event classified as level 1. AENOR performance the audit for renewing certificate UNE-EN ISO-9001, and for tracking environmental management systems as per UNE-EN ISO 14001, with satisfactory results. The dose around the Plant caused by plant operation has been insignificant. For the first time in the Spanish industry, the Plant has implemented an integrated safety system that encompasses all the plant's safety-related activities.

77 FR 59679 - Central Vermont Public Service Corporation (Millstone Power Station, Unit 3); Order Approving...

Science.gov (United States)

2012-09-28

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0044; Docket No. 50-423] Central Vermont Public Service Corporation (Millstone Power Station, Unit 3); Order Approving Application Regarding Corporate Restructuring and Conforming Amendment I Dominion Nuclear Connecticut, Inc. (DNC), Central Vermont Public Service...

Ground beetles (Coleoptera, Carabidae) of the Hanford Nuclear Site in south-central Washington State.

Science.gov (United States)

Looney, Chris; Zack, Richard S; Labonte, James R

2014-01-01

Carabidae) collected from the Hanford Nuclear Reservation and Hanford National Monument (together the Hanford Site), which is located in south-central Washington State. The Site is a relatively undisturbed relict of the shrub-steppe habitat present throughout much of the western Columbia Basin before the westward expansion of the United States. Species, localities, months of capture, and capture method are reported for field work conducted between 1994 and 2002. Most species were collected using pitfall traps, although other capture methods were employed. Trapping results indicate the Hanford Site supports a diverse ground beetle community, with over 90% of the 92 species captured native to North America. Four species collected during the study period are newly recorded for Washington State: Bembidion diligens Casey, Calosoma obsoletum Say, Pseudaptinus rufulus (LeConte), and Stenolophus lineola (Fabricius). Based on these data, the Site maintains a diverse ground beetle fauna and, due to its size and diversity of habitats, is an important repository of shrub-steppe biodiversity.

Ndos: nuclear data online services

International Nuclear Information System (INIS)

Fan, T.S.; Guo, Z.Y.; Ye, W.G.; Liu, W.L.; Feng, Y.Q.; Song, X.X.; Huang, G.; Liu, T.J.; Hong, Y.J.; Liu, C.; Chen, J.X.; Tang, G.Y.; Shi, Z.M.; Huang, X.L.; Chen, J.E.

2004-01-01

A Nuclear Data Online Services, Ndos software, has been developed to extract and present nuclear data from various available libraries. Using relational databases the present web-based software offers online data services of a centralized repository of data including eight major international nuclear data libraries for nuclear reaction data, nuclear structure and decay data. A data plotting software package, NDVS (Nuclear Data Viewing Software), which is included in NDOS, facilitates the visualization and manipulation of nuclear data. The NDOS is developed on the Linux implementation of PHP and the MySQL software. The relational nuclear databases and data services are platform independent in a wide sense

Ndos: nuclear data online services

Energy Technology Data Exchange (ETDEWEB)

Fan, T.S. E-mail: tsfan@nst.pku.edu.cn; Guo, Z.Y.; Ye, W.G.; Liu, W.L.; Feng, Y.Q.; Song, X.X.; Huang, G.; Liu, T.J.; Hong, Y.J.; Liu, C.; Chen, J.X.; Tang, G.Y.; Shi, Z.M.; Huang, X.L.; Chen, J.E

2004-07-01

A Nuclear Data Online Services, Ndos software, has been developed to extract and present nuclear data from various available libraries. Using relational databases the present web-based software offers online data services of a centralized repository of data including eight major international nuclear data libraries for nuclear reaction data, nuclear structure and decay data. A data plotting software package, NDVS (Nuclear Data Viewing Software), which is included in NDOS, facilitates the visualization and manipulation of nuclear data. The NDOS is developed on the Linux implementation of PHP and the MySQL software. The relational nuclear databases and data services are platform independent in a wide sense.

Reflections on Britain's nuclear history: a conversation with Lord Hinton

International Nuclear Information System (INIS)

Lowry, D.

1984-09-01

This record of a discussion with Lord Hinton, who was in charge of the industrial side of the U.K. atomic energy project, and later Chairman of the Central Electricity Generating Board, covers the following topics: history of the development and construction of reactors for the production of plutonium and, later, nuclear power; secrecy; early relations between Central Electricity Authority (and later, CEGB), the Government, and Atomic Energy Authority; Government policy on the nuclear power programme; decision making in the area of nuclear power; economics of nuclear power; the nuclear industry; safety, insurance, National Nuclear Inspectorate; support research and development in CEGB; Sizewell-B proposed PWR. (U.K.)

Description of the PIE facility for research reactors irradiated fuels in CNEA

International Nuclear Information System (INIS)

Bisca, A.; Coronel, R.; Homberger, V.; Quinteros, A.; Ratner, M.

2002-01-01

The PIE Facility (LAPEP), located at the Ezeiza Atomic Center (CAE), was designed to carry out destructive and non-destructive post-irradiation examinations (PIE) on research and power reactor spent fuels, reactor internals and other irradiated materials, and to perform studies related with: Station lifetime extension; Fuel performance; Development of new fuels; and Failures and determination of their causes. LAPEP is a relevant facility where research and development can be carried out. It is worth mentioning that in this facility the PIE corresponding to the Surveillance Program for the Atucha I Nuclear Power Plant (CNA-1) were successfully performed. Materials testing during the CNA-1 repair and the study of failures in fuel element plugs of the Embalse Nuclear Power Plant (CNE) were also performed. (author)

Nuclear security and law

International Nuclear Information System (INIS)

Gozal, Y.

1999-01-01

The aim of this study is to show that the classical distinction between the military nuclear law and the civil nuclear law is outdated. The technologies are dual and might be misused from a pacific to a military goal. The central element of the nuclear law is thus the integration of the safety rules: the nuclear risk being universal, it has created an universal law (first part) that reflects our scientific knowledge and might thus evaluate. This universal law has been a factor of nuclear security (part 2), as in 50 years, there had been only one major nuclear accident and no nuclear conflict. The horizontal proliferation has been limited and the international community has understood that time had come to reduce our arsenals. (author)

Nuclear emergency buildings of Asco and Vandellos II nuclear power plants; Centros alternativos de emergencias de las centrales nucleares de Asco y Vandellos II

Energy Technology Data Exchange (ETDEWEB)

Massuet, J.; Sabater, J.; Mirallas Esteban, S.

2016-08-01

The Nuclear Emergency Buildings sited at Asco and Vandellos II Nuclear Power Plants (NPP) are designed to safety manage emergencies in extreme situations, beyond the design basis of the Nuclear Power Plants. Designed in accordance with the requirements of the Spanish Nuclear Regulator (Consejo de Seguridad Nuclear-CSN) these buildings are ready to operate over a period of 72 hours without external assistance and ensure habitability for crews of 120 and 70 people respectively. This article describes the architectural conception, features and major systems of the Nuclear Emergency Buildings sited at Asco and Vandellos II. (Author)

Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

The International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) recommended holding a Technical Committee Meeting on Water Channel Reactor Fuel including into this category fuels and pressure tubes/fuel channels for Atucha-I and II, BWR, CANDU, FUGEN and RBMK reactors. The IWGFPT considered that even if the characteristics of Atucha, CANDUs, BWRs, FUGEN and RBMKs differ considerably, there are also common features. These features include materials aspects, as well as core, fuel assembly and fuel rod design, and some safety issues. There is also some similarity in fuel power history and operating conditions (Atucha-I and II, FUGEN and RBMK). Experts from 11 countries participated at the meeting and presented papers on technology, performance, safety and design, and materials aspects of fuels and pressure tubes/fuel channels for the above types of water channel reactors. Refs, figs, tabs.

Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1998-01-01

The International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) recommended holding a Technical Committee Meeting on Water Channel Reactor Fuel including into this category fuels and pressure tubes/fuel channels for Atucha-I and II, BWR, CANDU, FUGEN and RBMK reactors. The IWGFPT considered that even if the characteristics of Atucha, CANDUs, BWRs, FUGEN and RBMKs differ considerably, there are also common features. These features include materials aspects, as well as core, fuel assembly and fuel rod design, and some safety issues. There is also some similarity in fuel power history and operating conditions (Atucha-I and II, FUGEN and RBMK). Experts from 11 countries participated at the meeting and presented papers on technology, performance, safety and design, and materials aspects of fuels and pressure tubes/fuel channels for the above types of water channel reactors

Modifications in secondary circuit chemistry of Atucha I nuclear power plant

International Nuclear Information System (INIS)

Iglesias, Alberto M.; Jimenez Rebagliatti, Raul; Gentilli, Nelida; Raffo Calderon, Maria C.; Gemini, Hector

1999-01-01

The CNA I secondary circuit presents, by design, some materials which are difficult to be compatible from the corrosion point of view. The presence of Cu alloys limits the use of ammonia (or products that for decomposition generates it) as pH regulator substance which would be convenient to minimize the corrosion processes. The pH limit value in agreement with the operative experience is 9.2. This value is below the one required to minimize the effects of corrosion on the carbon steel, which is present inside the secondary circuit with a considerable exposed area and under hydrodynamic and hydrothermal conditions that favor those processes. This corrosive effect diminishes below certain limits, i. d. if the pH value is increased. The realization of this study involves three stages at least: a)- Independent measurements and description of the circuit current state; b)- Laboratory experiences of the possible alternatives into replace NH3 as alkaline agent and to provide better control of the corrosion process, on Cu alloys as well as steel alloys; c)- Plant implementations of the actions that are feasible from the point of view of power station operation, in such a way that in the secondary circuit it minimizes the presence of ammonia in the vapor phase and at the same time, the possibility of increasing the pH of the liquid phase, to diminish the corrosion phenomena of carbon steel. (author)

The Next Nuclear Gamble. Transportation and storage of nuclear waste

International Nuclear Information System (INIS)

Resnikoff, M.

1985-01-01

The Next Nuclear Gamble examines risks, costs, and alternatives in handling irradiated nuclear fuel. The debate over nuclear power and the disposal of its high-level radioactive waste is now nearly four decades old. Ever larger quantities of commercial radioactive fuel continue to accumulate in reactor storage pools throughout the country and no permanent storage solution has yet been designated. As an interim solution, the government and utilities prefer that radioactive wastes be transported to temporary storage facilities and subsequently to a permanent depository. If this temporary and centralized storage system is implemented, however, the number of nuclear waste shipments on the highway will increase one hundredfold over the next fifteen years. The question directly addressed is whether nuclear transport is safe or represents the American public's domestic nuclear gamble. This Council on Economic Priorities study, directed by Marvin Resnikoff, shows on the basis of hundreds of government and industry reports, interviews and surveys, and original research, that transportation of nuclear materials as currently practiced is unsafe

First Central and Eastern European Workshop on Quality control, patient dosimetry and radiation protection in diagnostic and interventional radiology and nuclear medicine

International Nuclear Information System (INIS)

National Frederic Joliot-Curie Research Institute for Radiobiology and Radiohygiene

2007-01-01

First Central and Eastern European Workshop on Quality Control, Patient Dosimetry and Radiation Protection in Diagnostic and Interventional Radiology and Nuclear Medicine, scientifically supported and accredited as a CPD event for medical physicists by EFOMP, National 'Frederic Joliot-Curie' Research Institute for Radiobiology and Radiohygiene (NRIRR), Budapest, Hungary, April 25-28, 2007. Topics of the meeting included all areas of medical radiation physics except radiation therapy. A unique possibility was realized by inviting four European manufacturers of quality control instrumentation, not only for exhibiting but they also had 45 minutes individual presentations about each manufacturer's product scale and conception. Further sessions dealt with dosimetry, optimization, quality control and testing, radiation protection and standardization, computed tomography and nuclear medicine, in 29 oral presentations and 1 poster of the participants. (S.I.)

Whole study of nuclear matter collective motion in central collisions of heavy ions of the FOPI detector; Etude complete du mouvement collectif de la matiere nucleaire dans les collisions centrales d'ions lourds avec le detecteur FOPI

Energy Technology Data Exchange (ETDEWEB)

Bendarag, A

1999-07-09

In this work we study the collective phenomena in the central collisions of heavy ions for the Au + Au, Xe + CsI and Ni + Ni systems at incident energies from 150 to 400 MeV/nucleon with the data of the FOPI detector. In order to describe completely the flow of the nuclear matter, we fit the double differential momentum distributions with two-dimensional Gaussian. We study the characteristic parameters of the collective flow (flow range, aspect ratios, flow parameter) versus the charge and the mass of the fragments as well as the incident energy and the centrality of the collisions. The transverse energy is used for selecting the central collisions. The method of the Gaussian fits requires also to reconstruct the reaction plane of the event. Then we correct the parameters for the finite number of particles effects and account for the influence of the acceptance of the detector. We confirm the importance of the thermal motion for the light charge or mass fragments and, conversely, the predominance of the collective motion for the heavy fragments. A common flow angle for all the types of particles is highlighted for the first time, demonstrating the power of the method of the Gaussian fits; The evolution of the other parameters confirms the observations done with other methods of flow analysis. These results should contribute to put constraints on the collision models and to enlarge our knowledge of the properties of the nuclear matter. (author)

Centrality dependence of the nuclear modification factor of charged pions, kaons, and protons in Pb-Pb collisions at root s(NN)=2.76 TeV

Czech Academy of Sciences Publication Activity Database

Adam, J.; Adamová, Dagmar; Bielčík, J.; Bielčíková, Jana; Brož, M.; Čepila, J.; Contreras, J. G.; Eyyubova, G.; Ferencei, Jozef; Křelina, M.; Křížek, Filip; Kučera, Vít; Kushpil, Svetlana; Mareš, Jiří A.; Petráček, V.; Pospíšil, Jan; Schulc, M.; Špaček, M.; Šumbera, Michal; Vajzer, Michal; Vaňát, Tomáš; Závada, Petr

2016-01-01

Roč. 93, č. 3 (2016), s. 034913 ISSN 0556-2813 R&D Projects: GA MŠk(CZ) LG13031 Institutional support: RVO:68378271 ; RVO:61389005 Keywords : ALICE collaboration * heavy ion collisions * centrality dependece Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders; BF - Elementary Particles and High Energy Physics (FZU-D) Impact factor: 3.820, year: 2016

Nuclear energy

International Nuclear Information System (INIS)

Rippon, S.

1984-01-01

Do we need nuclear energy. Is it safe. What are the risks. Will it lead to proliferation. The questions are endless, the answers often confused. In the vigorous debates that surround the siting and operation of nuclear power plants, it is all too easy to lose sight of the central issues amid the mass of arguments and counter-arguments put forward. And there remains the doubt, who do we believe. This book presents the facts, simply, straightforwardly, and comprehensibly. It describes the different types of nuclear reactor, how they work, how energy is produced and transformed into usable power, how nuclear waste is handled, what safeguards are built in to prevent accident, contamination and misuse. More important, it does this in the context of the real world, examining the benefits as well as the dangers of a nuclear power programme, quantifying the risks, and providing an authoritative account of the nuclear industry worldwide. Technically complex and politically controversial, the contribution of nuclear energy to our future energy requirements is a crucial topic of our time. (author)

Nonstrategic Nuclear Weapons

Science.gov (United States)

2017-02-21

of their nonstrategic nuclear weapons and eliminate many of them. These 1991 announcements, coming after the abortive coup in Moscow in July 1991...of these weapons. The abortive coup in Moscow in August 1991 had also caused alarms about the strength of central control over nuclear weapons...assure other allies of the U.S. commitment to their security, but these assurances do not necessarily include legally binding commitments to retaliate

AP1000, a nuclear central of advanced design

International Nuclear Information System (INIS)

Hernandez M, N.; Viais J, J.

2005-01-01

The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

Nuclear imaging in pediatrics

International Nuclear Information System (INIS)

Siddiqui, A.R.

1985-01-01

The author's intent is to familiarize practicing radiologists with the technical aspects and interpretation of nuclear medicine procedures in children and to illustrate the indications for nuclear medicine procedures in pediatric problems. Pediatric doses, dosimetry, sedation, and injection techniques, organ systems, oncology and infection, testicular scanning and nuclear crystography, pediatric endocrine and skeletal systems, ventilation and perfusion imaging of both congenital and acquired pediatric disorders, cardiovascular problems, gastrointestinal, hepatobiliary, reticuloendothelial studies, and central nervous system are all topics which are included and discussed

The Technical Training Programme for Nuclear Power Station Personnel; Programme de formation technique du personnel des centrales nucleaires; Programma tekhnicheskoj podgotovki personala yadernoj ehlektrostantsii; El programa de formacion tecnica del personal de una central nucleoelectrica

Energy Technology Data Exchange (ETDEWEB)

Howey, G. R. [Hydro-Electric Power Commission of Ontario, Toronto, Ontario (Canada)

1963-10-15

.), responsible for maintenance of all mechanical equipment; and (5) Service maintainers: responsible for a wide variety of less skilled tasks requiring lower qualifications. In addition to these general categories a few specialists are required, such as chemists and radiation protection officers. Organization of the NPD staff and training for future nuclear-power needs will be discussed. (author) [French] La centrale nucleaire de demonstration canadienne (NPD), creee par un organisme federal, l'Atomic Energy of Canada Limited, est exploitee par une compagnie provinciale de distribution d'electricite, la Hydro-Electric Power Commission of Ontario, qui pourvoit aussi aux besoins en personnel. Le recrutement et la formation du personnel de la centrale ont ete difficiles du fait que, recemment encore, la plupart des besoins en electricite de l'Ontario pouvaient etre satisfaits par les abondantes ressources hydro-electriques de cette province. La multiplication des centrales thermiques, depuis 1950, a cree une enorme demande de personnel. Pour faire face a cette situation, on a organise la formation de personnel pour les centrales nucleaires de la maniere suivante: a) un groupe initial d'ingenieurs a ete selectionne parmi des specialistes ayant une vaste experience des travaux dans le domaine nucleaire de l 'exploitation des centrales thermiques et de la production d'electricite; b) on a selectionne un autre groupe d'operateurs et d'agents des services d'entretien hautement qualifies; c) ces groupes ont recu une formation systematique comprenant l'exploitation de centrales nucleaires et de centrales thermiques a charbon, un enseignement theorique et pratique et des instructions donnees par les specialistes qui ont concu les plans de NPD ; d) un centre de formation nucleaire a ete cree et charge de la selection et de la formation du personnel supplementaire ainsi que de l 'organisation des examens officiels; il doit s'assurer, d'une maniere generale, de la competence du personnel

Comparison between a finite difference model (PUMA) and a finite element model (DELFIN) for simulation of the reactor of the atomic power plant of Atucha I; Comparacion entre un modelo de diferencias finitas (PUMA) y uno de elementos finitos (DELFIN) para la simulacion del reactor de la CNA-I (central nuclear Atucha-I)

Energy Technology Data Exchange (ETDEWEB)

Grant, C R [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

1997-12-31

The reactor code PUMA, developed in CNEA, simulates nuclear reactors discretizing space in finite difference elements. Core representation is performed by means a cylindrical mesh, but the reactor channels are arranged in an hexagonal lattice. That is why a mapping using volume intersections must be used. This spatial treatment is the reason of an overestimation of the control rod reactivity values, which must be adjusted modifying the incremental cross sections. Also, a not very good treatment of the continuity conditions between core and reflector leads to an overestimation of channel power of the peripherical fuel elements between 5 to 8 per cent. Another code, DELFIN, developed also in CNEA, treats the spatial discretization using heterogeneous finite elements, allowing a correct treatment of the continuity of fluxes and current among elements and a more realistic representation of the hexagonal lattice of the reactor. A comparison between results obtained using both methods in done in this paper. (author). 4 refs., 3 figs.

Nuclear energy in central and eastern Europe; L'energie nucleaire en Europe centrale et orientale

Energy Technology Data Exchange (ETDEWEB)

Cognet, G.; Billaud, E.; Battista, L.; Pascal, J. [CEA/Ambassade de France a Budapest (Hungary)

2010-07-15

Bulgaria, Hungary, Czech Republic, Romania, Slovakia and Slovenia have all nuclear power plants on their soil, their entry to the European Union has counter-balanced the number of member states that are not in favour of nuclear energy. All these countries committed themselves to upgrade their installations to European safety standards. This work is going on and new programs for service life extension and for construction of new units have been launched. All these countries have a strong culture and know-how in nuclear engineering inherited from soviet era. They stay very active in this field, for instance the ALLEGRO project that is carried out by a collaboration between Hungarian, Slovak, Czech research institutes and western partners aims at building the first demonstration plant of the future fourth generation reactor: a fast reactor cooled by gas. The situation of each country plus Croatia (that is a candidate to full E.U. membership) is reviewed. (A.C.)

Status of the nuclear sector in Spain Situación del sector nuclear en España

Directory of Open Access Journals (Sweden)

Antonio González Jiménez

2010-12-01

ó a desarrollarse en los años sesenta, como consecuencia de la decisión de construir las centrales nucleares de José Cabrera, Santa María de Garoña y Vandellós I. En la siguiente etapa, en la década de los años setenta, se construyeron las centrales de Almaraz, Ascó y Cofrentes. Durante la tercera etapa, en la década de los años ochenta, se construyeron las centrales de Vandellós II y Trillo I. Actualmente, la industria nuclear española, experta y eficaz, es garantía de que la tecnología nuclear se conserva en España no solo para apoyar a las centrales nucleares en operación, sino para atender un mercado nuclear reactivado a nivel internacional. España dispone de la infraestructura necesaria, la capacidad técnica, los recursos financieros y la voluntad de las empresas en el empeño común de proporcionar a los españoles una energía eléctrica fiable, barata y sostenible, con respeto al medio ambiente y seguridad para los ciudadanos. La energía nuclear es, en definitiva, una pieza clave hoy y lo será en el futuro.

A cosmic-ray nuclear event with an anomalously strong concentration of energy and particles in the central region

International Nuclear Information System (INIS)

Amato, N.M.; Arata, N.; Maldonado, R.H.C.

1986-01-01

A cosmic-ray induced nuclear event detected in the emulsion chamber is described. The event consists of 217 shower cores with ΣEγ = 1,275 TeV. In log scale, energy and particles are emitted most densely at the small lateral distance corresponding to 0.5 mm; 77 % of the total energy and 61 % of the total multiplicity are inside the radius of 0.65 cm. The shower cores in the central region show exponential-type energy distribution and non-isotropic azimuthal distribution. This event indicates a possibility that phenomena of large transverse momentum could happen to produce a strong concentration of energy and particles in the very forward direction. (Authors) [pt

Power generation

International Nuclear Information System (INIS)

Nunez, Anibal D.

2001-01-01

In the second half of twentieth century, nuclear power became an industrial reality. Now the operating 433 power plants, the 37 plants under construction, near 9000 years/reactor with only one serious accident with emission of radioactive material to the environment (Chernobyl) show the maturity of this technology. Today nuclear power contribute a 17% to the global generation and an increase of 75 % of the demand of electricity is estimated for 2020 while this demand is expected to triplicate by 2050. How this requirement can be satisfied? All the indicators seems to demonstrate that nuclear power will be the solution because of the shortage of other sources, the increase of the prices of the non renewable fuels and the scarce contribution of the renewable ones. In addition, the climatic changes produced by the greenhouse effect make even more attractive nuclear power. The situation of Argentina is analyzed and compared with other countries. The convenience of an increase of nuclear power contribution to the total national generation seems clear and the conclusion of the construction of the Atucha II nuclear power plant is recommended

The nuclear case book

International Nuclear Information System (INIS)

Stephenson, M.; Hearn, R.

1983-01-01

The subject is covered in sections, entitled: the truth about nukes; disarmament, arms control and arms limitation; directory of nuclear weapons; tables of principal nuclear weapons; points of view 1 (Anglican); proliferation of nuclear technology; the just war; preventing proliferation; the numbers business; war scenario 1 (the Gulf); points of view 2 (Roman Catholic); deterrence; European Nuclear Balance; war scenario 2 (Germany); arguing about war and peace; points of view 3 (Jewish); is there a Soviet military threat; the view from Omsk; points of view 4 (Pugwash); the British deterrent; points of view 5 (generals for peace and disarmament); 'broken arrows'; costs of nuclear weapons; war scenario 3 (Pakistan); nuclear weapons - what is the moral response; non-use of nuclear weapons; points of view 6 (women and families for defence); dear Mr. Heseltine; why acquire nuclear weapons; the effects of nuclear weapons; war scenario 4 (Central America and the Middle East); civil defence; alternatives to nuclear defence; points of view 7 (Quaker). (U.K.)

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

Energy Technology Data Exchange (ETDEWEB)

Esteban, G.

2014-10-01

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

Ground beetles (Coleoptera, Carabidae of the Hanford Nuclear Site in south-central Washington State

Directory of Open Access Journals (Sweden)

Chris Looney

2014-04-01

Full Text Available In this paper we report on ground beetles (Coleoptera: Carabidae collected from the Hanford Nuclear Reservation and Hanford National Monument (together the Hanford Site, which is located in south-central Washington State. The Site is a relatively undisturbed relict of the shrub-steppe habitat present throughout much of the western Columbia Basin before the westward expansion of the United States. Species, localities, months of capture, and capture method are reported for field work conducted between 1994 and 2002. Most species were collected using pitfall traps, although other capture methods were employed. Trapping results indicate the Hanford Site supports a diverse ground beetle community, with over 90% of the 92 species captured native to North America. Four species collected during the study period are newly recorded for Washington State: Bembidion diligens Casey, Calosoma obsoletum Say, Pseudaptinus rufulus (LeConte, and Stenolophus lineola (Fabricius. Based on these data, the Site maintains a diverse ground beetle fauna and, due to its size and diversity of habitats, is an important repository of shrub-steppe biodiversity.

Workers doses in central European PWR NPPs

International Nuclear Information System (INIS)

Janzekovic, H.; Krizman, M.

2003-01-01

As is stated, the ISOE database which was established in 1992 forms an excellent basis for studies and comparisons of occupational exposure data between nuclear power plants. In the year 2001, 69% of all participating reactors were pressurised water reactors. The ISOE database presents workers' exposure from 213 participating pressurised reactors (PWR) from 27 countries in that year. Among these 32 PWRs belong to six Central European Countries. The analysis of the exposure of workers based on radiation protection performance indicators (collective dose, average dose etc.) in these PWRs could be related to some nuclear safety performance indicators for recent years using ISOE database. The comparison is made to ISOE world - wide data. In the six Central European Countries altogether 32 PWR operated in the year 2001.The international databases of performance indicators related to radiation protection as for example the ISOE or the UNSCEAR database can be use as an efficient tool in the management of radiation protection of workers in a nuclear facilities and regulatory bodies. The databases enable the study of performance trends and the improvement of radiation protection. (authors)

Report on the Fourth Reactor Refueling. Laguna Verde Nuclear Central. Unit 1. April-May 1995

International Nuclear Information System (INIS)

Mendoza L, A.; Flores C, E.; Lopez G, C.P.F.

1995-01-01

The fourth refueling of the Unit 1 of Laguna Verde Nuclear Central was executed in the period of April 17 to May 31 of 1995 with the participation of a task group of 358 persons, included technicians and radiation protection officials and auxiliaries.The radiation monitoring and radiological surveillance to the workers was present length ways the refueling process and always attached to the ALARA criteria. The check points for radiation levels were set at: primary container or dry well, reloading floor, decontamination room (level 10.5), turbine building and radioactive waste building. To take advantage of the refueling process, rooms 203 and 213 of the turbine buildings were subject to inspection and maintenance work in valves, heaters and drains of heaters. Management aspects as personnel selection and training, costs, and countable are also presented in this report. Owing to the high cost of man-hour of the members of the ININ staff, its participation in the refueling process was in smaller number than years before. (Author)

The Staffing of Central Electricity Generating Board Nuclear Power Stations; Organigramme des centrales nucleaires du central electricity generating board; Politika v oblasti kadrov na atomnykh ehlektrostantsiyakh CEGB; El personal de las plantas nucleoelectricas de la central electricity generating board.

Energy Technology Data Exchange (ETDEWEB)

Bartlett, J. S.; Shepherd, G. T. [Central Electricity Generating Board, Western Division, Bristol (United Kingdom)

1963-10-15

An account is given of the staffing requirements and organization at a CEBG nuclear power station. The training of staff and licensing requirements for reactoroperating staff are discussed. Experience gained to data of the outcome of pre-operating training and detailed planning in the operational sphere is given. (author) [French] Le memoire donne un apercu de l'organigramme d'une centrale nucleaire du CEGB et des conditions auxquelles doit satisfaire le personnel (formation, qualifications requises pour la fonction d'operateur). Il rend compte egalement de l'experience acquise a ce jour quant a l'interet qu'il y a a former le personnel au prealable et a etablir des plans d'operation detailles. (author) [Spanish] La memoria informa sobre la organizacion de las centrales nucleoelectricas de la CEGB y sobre la plantilla de personal que estas requieren. Discute la formacion del personal y los requisitos para obtener la licencia de operador de reactores. Describe la experiencia adquirida hasta el presente en materia de formacion previa del personal y de organizacion detallada de las operaciones. (author) [Russian] Daetsya otchet o trebovaniyakh, pred{sup y}avlyaemykh k personalu, i organizatsiya nabora personala na atomnykh ehlektrostantsiyakh Tsentral'nogo upravleniya proizvodstva ehlektroehnergii (CEGB). Obsuzhdayutsya voprosy podgotovki personala i normativnykh trebovanij, pred{sup y}avlyaemykh k ehkspluatatsionnomu personalu. Izlagaetsya opyt, nakoplennyj k nastoyashchemu vremeni v rezul'tate osushchestvleniya predehkspluatatsionnoj podgotovki i podrobnogo planirovaniya v usloviyakh ehkspluatatsii. (author)

Central depression of the charge density distributions in lead isotopes

International Nuclear Information System (INIS)

Haddad, S.

2008-01-01

The central-depression parameters is determined by fitting the charge density distributions in lead isotopes to a three-parameter Fermi distribution. The central-depression parameter increases with the number of neutrons due to the isovector coupling channel of the nuclear interaction and its dependency on density. (author)

Central depression of the charge density distributions in lead isotopes

International Nuclear Information System (INIS)

Haddad, S.

2007-01-01

The central-depression parameter is determined by fitting the charge density distributions in lead isotopes to a three-parameter Fermi distribution. The central-depression parameter increases with the number of neutrons due to the isovector coupling channel of the nuclear interaction and its dependency on density. (author)

Nuclear power in the developing countries

International Nuclear Information System (INIS)

Perera, J.

1984-01-01

The subject is covered in chapters, entitled: the general energy situation (including nuclear power); the nuclear fuel cycle; the history of nuclear power in the third world; economic considerations; environmental considerations (including general environmental effects of power generation; radiation; normal fuel cycle operation; nuclear waste management; accidents; sabotage; health and safety regulations); political considerations (nuclear weapons proliferation; technology transfer; energy independence and national prestige); the suppliers (mainly USA, France, West Germany, Canada, UK, USSR); Sub-Saharan Africa; the Arab World and Israel; Central Asia; South and East Asia; Latin America; conclusions. (U.K.)

Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

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

Second School of Nuclear Energetics

International Nuclear Information System (INIS)

2009-01-01

At 3-5 Nov 2009 Institute of Nuclear Energy POLATOM, Association of Polish Electrical Engineers (SEP) and Polish Nuclear Society have organized Second School of Nuclear Energetics. 165 participants have arrived from all Poland and represented both different central institutions (e.g. ministries) and local institutions (e.g. Office of Technical Inspection, The Voivodship Presidential Offices, several societies, consulting firms or energetic enterprises). Students from the Warsaw Technical University and Gdansk Technical University, as well as the PhD students from the Institute of Nuclear Chemistry and Technology (Warsaw) attended the School. 20 invited lectures presented by eminent Polish specialists concerned basic problems of nuclear energetics, nuclear fuel cycle and different problems of the NPP construction in Poland. [pl

Commercial nuclear power: prospects for the United States and the world

International Nuclear Information System (INIS)

1986-01-01

This analysis report presents the current status and outlook for commercial nuclear power reactors for all countries in the world outside centrally planned economic areas (WOCA). Information regarding operable reactors in countries with centrally planned economies is presented in an appendix. The report provides documentation of the US nuclear capacity and generation projections through 1995. Projections for US nuclear capacity and generation through 2020 are presented for various nuclear power supply scenarios. These long-term projections are provided in support of the Department of Energy's activities pertaining to the Nuclear Waste Policy Act of 1982 and are used to produce the projections of fuel cycle requirements and spent fuel discharges

Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2007 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2007/01/01; Worldwide status of nuclear power plants (12/31/2007); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2007; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2007; Performance indicator of French PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2007; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2007; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2007; Long term shutdown units at 12/31/2007; COL (combined licences) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary.

14th German nuclear law symposium

International Nuclear Information System (INIS)

Burgi, Martin

2013-01-01

Nuclear law is still relevant and topical. The nuclear power phase-out in response to the nuclear accident of Fukushima and the turnaround in German energy policy raise new legal issues. In several lectures of practioners and scientists the 14th German Nuclear Law Symposium examined questions regarding the retrofitting of nuclear power plants, their decommissioning and disposal, the current developements in the European nuclear and radiation protection law and the search for a final nuclear waste repository. The nuclear law provides examples for central challenges of administrative law, such as the independence of authorities and the protection of third parties. The discussions between the almost 150 participants are documented in several reports.

Panorama of the nuclear physics

International Nuclear Information System (INIS)

Aragones, J.M.

1981-01-01

A summary of the topics covered by the nuclear physics, as disciplinary basis of the nuclear engineering, is presented, including from the fundamentals of modern physics used in nuclear physics, to the methods and more important applications, with the nucleus structure as central topic of the nuclear physics. In addition to a survey of the essential historical development in the different areas, this survey summarizes the basic concepts, postulates, laws and processes, which are the starting points, as in every scientific discipline for the understanding, interpretation and prediction of the variety of nuclear phenomena observed by methods increasingly improved and more complex, although such experimental methods are not discussed. (author) [es

Report of the State Office for Nuclear Safety on state supervision of nuclear safety of nuclear facilities and radiation protection in 1998

International Nuclear Information System (INIS)

1999-05-01

The legislative basis of the authority of the State Office for Nuclear Safety as the Czech national regulatory body is outlined, its organizational scheme is presented, and the responsibilities of the various departments are highlighted. The operation of major Czech nuclear facilities, including the Dukovany NPP which is in operation and the Temelin NPP which is under construction, is described with respect to nuclear safety. Since the Office's responsibilities also cover radiation protection in the Czech Republic, a survey of ionizing radiation sources and their supervision is given. Other topics include, among other things, nuclear material transport, the state system for nuclear materials accountancy and control, central registries for radiation protection, nuclear waste management, the National Radiation Monitoring Network, personnel qualification and training, emergency planning, legislative activities, international cooperation, and public information. (P.A.)

Nuclear reactor instrumentation power monitor

International Nuclear Information System (INIS)

Suzuki, Shigeru.

1989-01-01

The present invention concerns a nuclear reactor instrumentation power monitor that can be used in, for example, BWR type nuclear power plants. Signals from multi-channel detectors disposed on field units are converted respectively by LPRM signal circuits. Then, the converted signals are further converted by a multiplexer into digital signals and transmitted as serial data to a central monitor unit. The thus transmitted serial data are converted into parallel data in the signal processing section of the central monitor unit. Then, LPRM signals are taken out from each of channel detectors to conduct mathematical processing such as trip judgment or averaging. Accordingly, the field unit and the central monitor unit can be connected by way of only one data transmission cable thereby enabling to reduce the number of cables. Further, since the data are transmitted on digital form, it less undergoes effect of noises. (I.S.)

Centralization and decentralization in energy systems and associated risks

International Nuclear Information System (INIS)

Rehm, W.; Schinner, F.; Kromp, W.

1998-01-01

Full text of publication follows: the concept of centralization/decentralization is - considering its widespread use - surprisingly ill-defined. Within the SERF-program (Socio Economic Research on Fusion) an attempt is made to clarify the complex issue of centralization/decentralization and to analyze its expected interaction with electricity production system in the case of nuclear fusion. Fusion research at the time is a multinational, highly centralized undertaking. As a result of this, and due to the expected large energy production units, it is generally expected that fusion will be embedded in a highly centralized, international energy supply system. The degree of centralization of an energy supply system, however, is believed to have for reaching consequences on the stability of the system, and beyond that, on decision making processes in energy policy, as well as democratic structures on the national or even international level. Internationalization might require control instruments that do not exist so far. Amongst other reservations, it is the possibly unwanted consequences of such a highly centralized, international energy supply system that limit acceptance of the fusion technology in the public. Therefore, centralization and decentralization trends of energy supply systems over the years are being looked at, to study their influence on the political and social systems (and vice-versa). In a first step, an attempt is made to classify centralization. Careful analyses and evaluation of available literature revealed a broad spectrum of different forms and degrees of centralization. Various parameters describing energy production and distribution are used. A differentiation of centralization on a technical and on an organizational level seems necessary, although they are not fully independent of each other. Beyond this, the choice of parameters must depend on the questions to be addressed. A new approach defining different levels and degrees of

Centralization and decentralization in energy systems and associated risks

Energy Technology Data Exchange (ETDEWEB)

Rehm, W.; Schinner, F.; Kromp, W. [Vienna Univ., Institute of Risk Research, IRR (Austria)

1998-07-01

Full text of publication follows: the concept of centralization/decentralization is - considering its widespread use - surprisingly ill-defined. Within the SERF-program (Socio Economic Research on Fusion) an attempt is made to clarify the complex issue of centralization/decentralization and to analyze its expected interaction with electricity production system in the case of nuclear fusion. Fusion research at the time is a multinational, highly centralized undertaking. As a result of this, and due to the expected large energy production units, it is generally expected that fusion will be embedded in a highly centralized, international energy supply system. The degree of centralization of an energy supply system, however, is believed to have for reaching consequences on the stability of the system, and beyond that, on decision making processes in energy policy, as well as democratic structures on the national or even international level. Internationalization might require control instruments that do not exist so far. Amongst other reservations, it is the possibly unwanted consequences of such a highly centralized, international energy supply system that limit acceptance of the fusion technology in the public. Therefore, centralization and decentralization trends of energy supply systems over the years are being looked at, to study their influence on the political and social systems (and vice-versa). In a first step, an attempt is made to classify centralization. Careful analyses and evaluation of available literature revealed a broad spectrum of different forms and degrees of centralization. Various parameters describing energy production and distribution are used. A differentiation of centralization on a technical and on an organizational level seems necessary, although they are not fully independent of each other. Beyond this, the choice of parameters must depend on the questions to be addressed. A new approach defining different levels and degrees of

US central station nuclear electric generating units: significant milestones

International Nuclear Information System (INIS)

1979-09-01

Listings of US nuclear power plants include significant dates, reactor type, owners, and net generating capacity. Listings are made by state, region, and utility. Tabulations of status, schedules, and orders are also presented

Nuclear power in Europe

International Nuclear Information System (INIS)

Perera, J.

2000-01-01

Currently nuclear power accounts for more than 25% of total electricity production in Europe (including Eastern Europe and the former Soviet Union) However, significant new construction is planned in Central and Eastern Europe only, apart from some in France and, possibly in Finland. Many countries in Western Europe have put nuclear construction plans on hold and several have cancelled their nuclear programs. This report looks at the history of nuclear power and its current status in both Eastern and Western Europe. It provides an outline of nuclear fuel cycle facilities, from uranium procurement to final waste disposal. Economic and environmental issues are discussed, as well as the prospect of increased East-West trade and cooperation in the new poso-cold war world. Detailed profiles are provided of all the countries in Western Europe with significant nuclear power programs, as well as profiles of major energy and nuclear companies

Situación del sector nuclear en España

Directory of Open Access Journals (Sweden)

Antonio González Jiménez

2010-12-01

Full Text Available España comenzó a interesarse por la energía nuclear a finales de los años cuarenta. En el año 1964 se aprobó la Ley de Energía Nuclear, y en el año 1972 se desarrolló el Reglamento de Instalaciones Nucleares y Radiactivas. Las actividades de seguridad y regulación se encomendaron al Consejo de Seguridad Nuclear, creado en 1980, y la investigación y gestión de los residuos radiactivos a la Empresa Nacional de Residuos Radiactivos (ENRESA, creada en 1985. La estructura industrial nuclear en España comenzó a desarrollarse en los años sesenta, como consecuencia de la decisión de construir las centrales nucleares de José Cabrera, Santa María de Garoña y Vandellós I. En la siguiente etapa, en la década de los años setenta, se construyeron las centrales de Almaraz, Ascó y Cofrentes. Durante la tercera etapa, en la década de los años ochenta, se construyeron las centrales de Vandellós II y Trillo I.Actualmente, la industria nuclear española, experta y eficaz, es garantía de que la tecnología nuclear se conserva en España no solo para apoyar a las centrales nucleares en operación, sino para atender un mercado nuclear reactivado a nivel internacional. España dispone de la infraestructura necesaria, la capacidad técnica, los recursos financieros y la voluntad de las empresas en el empeño común de proporcionar a los españoles una energía eléctrica fiable, barata y sostenible, con respeto al medio ambiente y seguridad para los ciudadanos. La energía nuclear es, en definitiva, una pieza clave hoy y lo será en el futuro.

Regional comparison of nuclear and fossil electric power generation costs

International Nuclear Information System (INIS)

Bowers, H.I.

1984-01-01

Nuclear's main disadvantages are its high capital investment cost and uncertainty in schedule compared with alternatives. Nuclear plant costs continue to rise whereas coal plant investment costs are staying relative steady. Based on average experience, nuclear capital investment costs are nearly double those of coal-fired generation plants. The capital investment cost disadvantage of nuclear is balanced by its fuel cost advantages. New base load nuclear power plants were projected to be competitive with coal-fired plants in most regions of the country. Nuclear power costs wre projected to be significantly less (10% or more) than coal-fired power costs in the South Atlantic region. Coal-fired plants were projected to have a significant economic advantage over nuclear plants in the Central and North Central regions. In the remaining seven regions, the levelized cost of power from either option was projected to be within 10%. Uncertainties in future costs of materials, services, and financing affect the relative economics of the nuclear and coal options significantly. 10 figures

Climatologia no Entorno da Central Nuclear de Angra dos Reis, RJ

Directory of Open Access Journals (Sweden)

João Batista Araujo Figueiredo

Full Text Available Resumo Este trabalho tem por objetivo caracterizar os ciclos diurno e sazonal médios no entorno da Central Nuclear de Angra dos Reis. As condições médias são derivadas de dados horários, do período de janeiro de 2005 a dezembro de 2012. O local conta com quatro torres A, B, C e D. A Torre A mede vento e temperatura do ar a 10, 60 e 100 m e também precipitação, enquanto as demais torres medem somente vento a 15 m de altura. A atmosfera apresenta condições predominantemente estáveis ao longo do dia, com redução a partir das 6 e 7 h, sendo que condições instáveis predominam entre às 8 e 16 h no verão e primavera. Os ventos da região são predominantemente fracos, a maior frequência ocorre nas intensidades entre 1,5 e 2 m/s. O mínimo de intensidade dos ventos a 10 m ocorre no momento da entrada da brisa marítima, às 9 h. Os ventos catabáticos produzem um forte cisalhamento vertical dos ventos na região. Nas demais torres a máxima intensidade ocorre entre 13 e 15 h local. Ventos mais intensos e chuvas mais intensas foram registrados no outono (MAM, o que sugere ser este o período de tempestades mais intensas.

Aplicación de la metodología de Análisis Probabilístico de la Seguridad al procedimiento de evaluación de las Funciones Clave de Seguridad en parada de una central nuclear de agua a presión

OpenAIRE

Viñals Atienza, Òscar

2008-01-01

El Proyecto Final de Carrera “Aplicación de la metodología de Análisis Probabilístico de la Seguridad al procedimiento de evaluación de las Funciones Clave de Seguridad en parada de una central nuclear de agua a presión” se enmarca en un convenio de colaboración entre el Departament de Física i Enginyeria Nuclear y una central nuclear para la investigación y aplicación de los APS en decisiones basadas en el riesgo. El hilo conductor de este proyecto ha sido la petición por parte del depart...

Iodine prophylaxis following nuclear accidents - a concept how to distribute potassium-iodide tablets out of the central stocks in the event of an accident

International Nuclear Information System (INIS)

Portius, U.

2007-01-01

With its recommendation ''Iodine prophylaxis following nuclear accidents'' (1996) and its reports of 1997 and 2001 the German Commission on Radiological Protection (SSK) followed the recommendations of the WHO ''Guidelines for iodine prophylaxis following nuclear accidents'' of 1989. The intervention levels were lowered (50 mSv for children/adolescents (up to the age of 18 years) and pregnant women, 250 mSv for adults), the iodine prophylaxis was restricted to persons up to the age of 45 years and the recommended dosage of stable iodine was changed. Due to the lowered reference levels the radius of 25 km around a nuclear power plant that had been the planning radius for the distribution of iodine tablets so far was extended to 100 km. Based on these recommendations the German authorities began to set up new strategies for the provision and distribution of potassium-iodide tablets (iodine tablets). Since 2004, within the radius of 25 km the iodine tablets are pre-distributed to households and/or stored at several points in the municipality for persons up to the age of 45 years. For the new planning radius of 25-100 km iodine tablets are stored in 8 central stocks in Germany for children/adolescents (up to the age of 18 years) and pregnant women. A working group with representatives from federal and Laender authorities has developed a distribution strategy for the distribution out of these central stocks in the event of an accident. It describes a possibility of organising and implementing the distribution of the iodine tablets within the radius of 25-100 km in a nationwide standardised way. (orig.)

Behind the UK nuclear flip-flop

International Nuclear Information System (INIS)

Anon.

1990-01-01

Because it failed to attract commercial investors on acceptable terms, the British government has exempted the nation's nuclear powerplants from privatization, lopping off about 8,000 MW from National Power - the larger of the two successors to the broken-up Central Electricity Generating Board - and whipping up an antiprivatization political storm in the process. A new state company - to be called the Nuclear Electric Co - will be set up to control nuclear powerplants

A study on the nuclear foreign policy

International Nuclear Information System (INIS)

Lee, Byungwook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Noh, B. C.

2008-12-01

This study addresses four arenas to effectively assist national nuclear foreign policies under international nuclear nonproliferation regimes and organizations. Firstly, this study analyzes the trends of the international nuclear non-proliferation regime, which includes the Treaty on the Non-proliferation of Nuclear Weapons (NPT), the international nuclear export control regime, and proposals for assurance of nuclear fuel supply. Secondly, this study analyzes the trends of international nuclear organizations, which include the IAEA as a central body of international nuclear diplomacy and technical cooperation and the OECD/NEA as a intergovernmental organization to consist of nuclear advanced countries. Thirdly, this study predicts the nuclear foreign policy of Obama Administration and reviews U. S.-India nuclear cooperation. Lastly, this study analyzes the nuclear issues of North Korea and current issues for regulation of nuclear materials.

Experience gained in enhancing operational safety at ComEd's nuclear power plants

International Nuclear Information System (INIS)

Elias, D.

1997-01-01

The following aspects of experience gained in enhancing operational safety at Comed's nuclear power plants are discussed: nuclear safety policy; centralization/decentralization; typical nuclear operating organization; safety review boards; human performance enhancement; elements of effective nuclear oversight

Alarm-Processing in Nuclear Power Plants

International Nuclear Information System (INIS)

Otazo, J; Fernandez, R

2000-01-01

.The knowledge base also includes rules for alarm-filtering.The implementation of the system, that still is in developing phase is made in G2 (Gensym Inc.), an industrial object oriented tool for the development of expert systems.The prototype of the systems will be validated with the real time simulator of the Atucha-I Nuclear Power Plant, using one of its subsystems like model.This implementation has planned the development of an interface between G2 and the plant simulator

Diffraction in nuclear scattering

International Nuclear Information System (INIS)

Wojciechowski, H.

1986-01-01

The elastic scattering amplitudes for charged and neutral particles have been decomposed into diffractive and refractive parts by splitting the nuclear elastic scattering matrix elements into components responsible for these effects. It has been shown that the pure geometrical diffractive effect which carries no information about the nuclear interaction is always predominant at forward angle of elastic angular distributions. This fact suggests that for strongly absorbed particles only elastic cross section at backward angles, i.e. the refractive cross section, can give us basic information about the central nuclear potential. 12 refs., 4 figs., 1 tab. (author)

Improved nuclear fuel element

International Nuclear Information System (INIS)

Klepfer, H.H.

1974-01-01

A nuclear fuel element is described which comprises: 1) an elongated clad container, 2) a layer of high lubricity material being disposed in and adjacent to the clad container, 3) a low neutron capture cross section metal liner being disposed in the clad container and adjacent to the layer, 4) a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, 5) an enclosure integrally secured and sealed at each end of the container, and a nuclear fuel material retaining means positioned in the cavity. (author)

Nuclear Waste Fund management

International Nuclear Information System (INIS)

Mills, L.

1984-01-01

The Nuclear Waste Policy Acts requires that DOE enter into contracts with nuclear utilities and others to accept their nuclear wastes at some unspecified date, at some unspecified rate, hopefully starting in 1998. Contracts between DOE and the states, and with civilian and other government agencies must be sufficiently detailed to secure competitive bids on definable chunks of work at a fixed-cost basis with incentives. The need is stressed for a strong central program for the selection of contractors on the basis of competitive bidding on a fixed price basis to perform the task with defined deliverables

Advances in nuclear physics

CERN Document Server

Vogt, Erich

1975-01-01

Review articles on three topics of considerable current interest make up the present volume. The first, on A-hypernuclei, was solicited by the editors in order to provide nuclear physicists with a general description of the most recent developments in a field which this audience has largely neglected or, perhaps, viewed as a novelty in which a bizarre nuclear system gave some information about the lambda-nuclear intersection. That view was never valid. The very recent developments reviewed here-particularly those pertaining to hypernuclear excitations and the strangeness exchange reactions-emphasize that this field provides important information about the models and central ideas of nuclear physics. The off-shell behavior of the nucleon-nucleon interaction is a topic which was at first received with some embarrassment, abuse, and neglect, but it has recently gained proper attention in many nuclear problems. Interest was first focused on it in nuclear many-body theory, but it threatened nuclear physicists'comf...

A comprehensive centralized control system for radiation waste treatment facility

International Nuclear Information System (INIS)

Kong Jinsong

2014-01-01

A comprehensive centralized control system is designed for the radiation waste treatment facility that lacking of coordinated operational mechanism for the radiation waste treatment. The centralized control and alarm linkage of various systems is implemented to ensure effectively the safety of nuclear facility and materials, improve the integral control ability through advanced informatization ways. (author)

Nuclear waste: Status of DOE's nuclear waste site characterization activities

International Nuclear Information System (INIS)

1987-01-01

Three potential nuclear waste repository sites have been selected to carry out characterization activities-the detailed geological testing to determine the suitability of each site as a repository. The sites are Hanford in south-central Washington State, Yucca Mountain in southern Nevada, and Deaf Smith in the Texas Panhandle. Two key issues affecting the total program are the estimations of the site characterization completion data and costs and DOE's relationship with the Nuclear Regulatory Commission which has been limited and its relations with affected states and Indian tribes which continue to be difficult

Development of database for spent fuel and special waste from the Spanish nuclear power plants; Desarrollo de la base de datos para el combustible gastado y residuos especiales de las centrales nucleares espanolas

Energy Technology Data Exchange (ETDEWEB)

Gonzalez Gandal, R.; Rodriguez Gomez, M. A.; Serrano, G.; Lopez Alvarez, G.

2013-07-01

GNF Engineering is developing together with ENRESA and with the UNESA participation, the spent fuel and high activity radioactive waste data base of Spanish nuclear power plants. In the article is detailed how this strategic project essential to carry out the CTS (centralized temporary storage) future management and other project which could be emerged is being dealing with, This data base will serve as mechanics of relationship between ENRESA and Spanish NPPS, covering the expected necessary information to deal with mentioned future management of spent fuel and high activity radioactive waste. (Author)

Central Accountability System (CLAS)

International Nuclear Information System (INIS)

Hairston, L.A.

1991-01-01

The Central Accountability System (CLAS) is a high level accountability system that consolidates data from the site's 39 material balance areas (MBA) for reporting to Westinghouse Savannah River Company (WSRC) management, Department of Energy (DOE) and the Nuclear Materials Management and Safeguards System (NMMSS) in Oak Ridge, TN. Development of the system began in 1989 and became operational in April, 1991. The CLAS system enhances data accuracy and accountability records, resulting in increased productivity and time and cost savings. This paper reports that the system is in compliance with DOE Orders and meets NMMSS reporting requirements. WSRC management is provided with the overall status of the site's nuclear material inventory. CLAS gives WSRC a leading edge in accounting technology and enhances good accounting practices

Meeting of socialist conntries' representatives on problems of nuclear materials analyses

International Nuclear Information System (INIS)

Pacak, P.; Moravec, J.; Krtil, J.; Sus, F.

1982-01-01

A meeting of representatives of the socialist countries was held in Prague from May 18 to 22, 1981, to discuss cooperation in the field of analytical control of nuclear materials. The Czechoslovak delegation informed the participants of the extent and results of the work of the Central Control Laboratory of the Nuclear Research Institute in Rez. A brief survey is given of the nondestructive methods of measuring the physical parameters of nuclear fuel, the methods of destructive determination of uranium and plutonium and the methods of preparation of standard materials for mass spectrometry which the Central Control Laboratory has introduced and verified for securing analytical control of nuclear materials. (B.S.)

DTN and international cooperation of the Spanish Nuclear Sector in nuclear technology development processes

International Nuclear Information System (INIS)

Acero, M.

1995-01-01

The Spanish electrical utilities with interests in the Nuclear Sector-IBERDROLA, ENDESA,FUERZAS ELECTRICAS DE CATALU=A5A (FECSA), UNION ELECTRICA FENOSA S.A., COMPA=A5IA SEVILLANA DE ELECTRICIDAD S.A., AND HIDROELECTRICA DEL CANTABRICO S.A.-created on September 26, 1994 the ''Agrupacion Electrica para el Desarrollo Tecnologico Nuclear, A.I.E. (DTN)'' (Electrical Society for Nuclear technology Development A.I.E.) for the purpose of promoting and managing Nuclear Nechnology Development, and integrating and coordinating the efforts of the Nuclear Electrical Sector with industrial companies and other related institutions in spain and abroad. This mission is primarily accomplished by establinhing a common strategy for the Nuclear Electrical Sector in the different areas of responsibility of DTN, centralizing actions by implementing a clear and coherent policy, and ensuring the presence of the entire Electrical Sector in all those fora deemed to be strategic to the Nuclear Sector

Energy/war: breaking the nuclear link

International Nuclear Information System (INIS)

Lovins, A.B.; Lovins, L.H.

1980-01-01

Policies to control the spread of nuclear weapons have assumed that the rapid worldwide spread of nuclear power is essential to replace oil, is both economically desirable and inevitable, and that the international political order must remain inherently discriminatory and dominated by the nuclear arms race. These assumptions are challenged as contrary to economic fact and market behavior. The authors feel that the link between nuclear reactors and nuclear bombs is inextricable, making proliferation inevitable and nuclear power a dangerous and costly alternative to oil. Instead, they suggest that nuclear power will collapse in response to market forces because only a few centrally-planned economies can override economic pressures. Acknowledgement of this collapse should be encouraged and the benefits of nuclear power accepted as illusory, according to the authors. 349 references, 2 figures

INTERNET and information about nuclear sciences. The world wide web virtual library: nuclear sciences

International Nuclear Information System (INIS)

Kuruc, J.

1999-01-01

In this work author proposes to constitute new virtual library which should centralize the information from nuclear disciplines on the INTERNET, in order to them to give first and foremost the connection on the most important links in set nuclear sciences. The author has entitled this new virtual library The World Wide Web Library: Nuclear Sciences. By constitution of this virtual library next basic principles were chosen: home pages of international organizations important from point of view of nuclear disciplines; home pages of the National Nuclear Commissions and governments; home pages of nuclear scientific societies; web-pages specialized on nuclear problematic, in general; periodical tables of elements and isotopes; web-pages aimed on Chernobyl crash and consequences; web-pages with antinuclear aim. Now continue the links grouped on web-pages according to single nuclear areas: nuclear arsenals; nuclear astrophysics; nuclear aspects of biology (radiobiology); nuclear chemistry; nuclear company; nuclear data centres; nuclear energy; nuclear energy, environmental aspects of (radioecology); nuclear energy info centres; nuclear engineering; nuclear industries; nuclear magnetic resonance; nuclear material monitoring; nuclear medicine and radiology; nuclear physics; nuclear power (plants); nuclear reactors; nuclear risk; nuclear technologies and defence; nuclear testing; nuclear tourism; nuclear wastes; nuclear wastes. In these single groups web-links will be concentrated into following groups: virtual libraries and specialized servers; science; nuclear societies; nuclear departments of the academic institutes; nuclear research institutes and laboratories; centres, info links

Sector activities related to spent nuclear fuel in the spanish nuclear power plants; Actuaciones sectoriales en relaci@n con el combustible nuclear gastado en las centrales nucleares espa@olas.

Energy Technology Data Exchange (ETDEWEB)

Francia, L.

2016-07-01

Royal Decree 102/2014 of February 21 defines spent nuclear fuel as the irradiated nuclear fuel in the reactor core that is permanently removed from it. Spent nuclear fuel can be considered either as a usable resource that can be reprocessed, or else as a radioactive waste destined for final disposal. Likewise, spent nuclear fuel management refers to all the activities related to handling, temporary storage, reprocessing and final storage. The article presents all the plans and actions taken by the nuclear power plants, which can be divided into the following two categories: Actions taken by the plants themselves to not only maintain the fuel in stable, safe conditions, but also to characterize and process it for the subsequent management routes established by the current General Radioactive Waste Plan. Activities undertaken under the UNESA umbrella to help implement the above mentioned management routes.

Mechanical and Radiological Characterization of Different parts of an Irradiation Coolant Channel Tube from Atucha I Nuclear Plant

International Nuclear Information System (INIS)

Piquin, Ruben

2001-01-01

The widespread replacement of reactor internals has generated a substantial volume of active material. It is essential to work with these components at least in a partial way before the next planned stop, which will take place during the second semester of the year 2002. Due to the fact that the reactor internals pool and the storage pool for irradiated nuclear fuel have limited capacities, it has been proposed to compact an experimental shift of 50 irradiated coolant channels, that are currently placed in storage pools. Basically the processed waste will be put in baskets at the bottom pools.The alternative choice proposes to divide an irradiation coolant channel tube into different parts: stainless steel section, zircaloy-4 section and stainless steel section with hardened zones with cobalt alloys named Estelite-6. The person in charge has already planned the constructive and operative solutions but the mechanical characterization of the different parts of the channel tube is necessary in order to dimension the compaction tool needed for the semi-industrial installation.In the present special report, two well-differentiated actions will be described. The necessary compacted strength of the irradiation coolant channel tube will be estimated for the stainless steel section and the zircaloy-4 section starting from experiment with unirradiated material and considering effects of radiation damage and hydrides on the ductility.These results will be used to design the necessary compacted tools for the semi-industrial installation. The necessary equipment for the radiological characterization of the different material sections already specified will be described and the most important emitting particles of radiation that could be detected will be mentioned. Also the decontamination process to use including the radiological characterization of every stage of the process will be described in order to establish the decontamination factor. Finally the most important

Perspectives in high energy nuclear collisions

International Nuclear Information System (INIS)

Rafelski, J.

1983-08-01

This report gives an overview of some aspects of hadronic physics relevant for the conception of a research facility devoted to the study of high energy nuclear collisions. Several concepts to be studied in nuclear collisions are selected, with emphasis placed on the properties and nature of the quark-gluon plasma, the formation of the plasma state in the central region and its anticipated lifetime, and the observability, through strangeness content of this new form of nuclear matter. (orig.)

Pro-Nuclear Environmentalism: Should We Learn to Stop Worrying and Love Nuclear Energy?

Science.gov (United States)

van Munster, Rens; Sylvest, Casper

2015-10-01

In light of repeated failures to reach political agreement on effective policies to combat climate change, pro-nuclear environmentalists have set out to reverse the traditionally anti-nuclear inclinations of environmentalists. This essay examines the ideological commitments and assumptions of pro-nuclear environmentalism by performing a critical, historical analysis of the nuclear-environment nexus through the prism of documentary film. We focus on the work and career of documentary filmmaker Rob Stone, whose most recent production, Pandora's Promise (PP) (2013), has emerged as a central statement of this creed. PP actively forges a new political imaginary that replaces the apocalyptic image of nuclear fallout with that of catastrophic climate change. In terms of its rhetorical and visual strategies, however, PP also reveals that pro-nuclear environmentalist arguments have a long lineage. A close study of such continuities reveals a number of political implications that call for reflection as well as caution.

Failure Analysis

International Nuclear Information System (INIS)

Iorio, A.F.; Crespi, J.C.

1987-01-01

After ten years of operation at the Atucha I Nuclear Power Station a gear belonging to a pressurized heavy water reactor refuelling machine, failed. The gear box was used to operate the inlet-outlet heavy-water valve of the machine. Visual examination of the gear device showed an absence of lubricant and that several gear teeth were broken at the root. Motion was transmitted with a speed-reducing device with controlled adjustable times in order to produce a proper fitness of the valve closure. The aim of this paper is to discuss the results of the gear failure analysis in order to recommend the proper solution to prevent further failures. (Author)

Communication system and spectral analysis for Ge-Li and GeHp detectors

International Nuclear Information System (INIS)

Fernandez, J.; Castano, P.; Bonino, A.D.; Righetti, M.A.

1990-01-01

An integral communication and spectral analysis system (SICADE) was developed and implemented to satisfy the need to optimize and automate the measurement system used in Atucha I nuclear power plant for the activity in the primary loop's water extracted by the TV system. The importance of these measurements is based on the fact that from the spectrometric analysis of the samples extracted, the Iodines-GN and Iodines-Iodines relations, which allow to detect the presence of deficient fuel elements, are calculated. The system developed is based on two modules integrated in a unique set commanded by the operators through the screen dialogue. (Author) [es

Commercial nuclear power 1988: Prospects for the United States and the world

International Nuclear Information System (INIS)

1988-01-01

This report presents historical data on commercial nuclear power in the United States, with projections of domestic nuclear capacity and generation through the year 2020. The report also gives country-specific projections of nuclear capacity and generation through the year 2010 for other countries in the world outside centrally planned economic areas (WOCA). Information is also presented regarding operable reactors and those under construction in countries with centrally planned economies. This report presents three different nuclear supply scenarios. The Optimistic-case scenario, included in previous issues of this report, has been deleted. 7 figs; 36 tabs

Limits to the Recognizability of Flaws in Non-Destructive Testing Steam-Generator Tubes for Nuclear-Power Plants; Limitations de l'Efficacite de la Detection des Defauts par Essais Non Destructifs de Tubes de Bouilleurs pour Centrales Nucleaires; Predely ehffektivnosti nedestruktivnoj defektoskopii trub parogeneratorov yadernykh ehlektrostantsij; Limites para Distinguir los Defectos en el Ensayo No Destructivo de Tubo para Generadores de Vapor Destinados a Centrales Nucleares

Energy Technology Data Exchange (ETDEWEB)

Kuhlmann, A.; Adamsky, F. -J. [Technischer Ueberwachungs-Verein Reinland e.V., Cologne (Germany)

1965-10-15

In the Federal Republic of Germany there are nuclear reactors under construction with steam generators inside the reactor pressure-vessel. As a result design repairs of steam- generator tubes are very difficult and cause large shut-down times of the nuclear-power plant. It is known that numerous troubles in operating conventional power plants are results of steam-generator tube damages. Because of the high total costs of these reactors it. is necessary to construct the steam generators especially in such a manner that the load factor of the power plant is as high as possible. The Technischer Ueberwachungs-Verein Rheinland was charged to supervise and to test fabrication and construction of the steam generators to see that this part of the plant was as free of defects as possible. The experience gained during this work is of interest for manufacture and construction of steam generators for nuclear-power plants in general. This paper deals with the efficiency limits of non-destructive testing steam-generator tubes. The following tests performed will be discussed in detail: (a) Automatic ultrasonic testing of the straight tubes in the production facility; (b) Combined ultrasonic and radiographic testing of the bent tubes and tube weldings; (c) Other non-destructive tests. (author) [French] En Allemagne, on construit actuellement des generatrices nucleaires dans lesquelles les bouilleurs sont installes a l'interieur du caisson etanche du reacteur. Il s'ensuit que les reparations des tubes des bouilleurs sont tres difficiles et provoquent de longs arrets des centrales nucleaires. On sait que de nombreuses perturbations du fonctionnement des centrales classiques sont dues a des dommages dans les tubes des bouilleurs. C'est en grande partie en raison du prix de revient eleve de ces reacteurs qu'il est necessaire de construire les bouilleurs notamment de sorte que le facteur d'utilisation de la centrale soit aussi eleve que possible. C'est le ' Technischer Ueberwachungs

Nuclear training and experience feedback in Sweden

International Nuclear Information System (INIS)

Olofsson, B.G.

1987-01-01

There are several different ways of educating and training the personnel at the Swedish nuclear power plants: centralized training in full-scale and part-task simulators; centralized education in the form of technical academic courses where computerized teaching is also used; extensive decentralized training out at the nuclear power plants, where compact simulators are also used; and experience feedback forms an important part of the training. Five performance indicators will be identified and the results will be presented. The excellent results are a good indication of the fact that well-executed education and training and smoothly functioning experience feedback give results

1989 annual report of the Rossendorf Central Institute of Nuclear Research

International Nuclear Information System (INIS)

Fromm, W.; Kaun, K.H.; Moeller, K.; Naehring, F.; Schulz, H.; Winter, G.; Heidel, I.; Breiter, S.

1990-01-01

The research and development results are classified by research lines. Each section starts with an introduction summing up the developments of the particular field of work, followed by progress reports on specific projects, contributions on partial results not published so far, and summaries of 1989 publications. Research priorities are, among others, the fields of nuclear spectroscopy; ion-beam solid state physics; positron emission tomography; nuclear trace technology; neutron doping, and accelerator development. (DG) [de

Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

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

Commercial nuclear power: prospects for the United States and the world

International Nuclear Information System (INIS)

Mayes, F.; Gielecki, M.; Diedrich, R.; Hewlett, J.; Murphy, T.

1985-01-01

This analysis report presents the current status and outlook for commercial nuclear power reactors for all countries in the world outside centrally planned economic areas (WOCA). Information regarding operable reactors in countries with centrally planned economies is also presented. The report provides documentation of the US middle-case nuclear capacity and generation projections through 1995 that are presented in the Annual Energy Outlook 1984. Additionally, US nuclear capacity and generation projections through 2020 are presented for various nuclear power supply scenarios. These long-term projections are provided in support of the Department of Energy's activities pertaining to the Nuclear Waste Policy Act of 1982. The projections for foreign nuclear capacity through 1990 supplant the preliminary foreign WOCA projections presented in the Annual Energy Outlook 1984 and are supplemented by WOCA country-specific projections through the year 2000

Nuclear DNA content variation among central European Koeleria taxa

Czech Academy of Sciences Publication Activity Database

Pečinka, A.; Suchánková, Pavla; Lysák, Martin; Trávníček, B.; Doležel, Jaroslav

2006-01-01

Roč. 98, - (2006), s. 117-122 ISSN 0305-7364 R&D Projects: GA MŠk(CZ) LC06004 Institutional research plan: CEZ:AV0Z50380511 Keywords : Chromosome number * nuclear DNA content * flow cytometry Subject RIV: EB - Genetics ; Molecular Biology Impact factor: 2.448, year: 2006

Improvements to the wastewater treatment from the beginning of the operation of Nuclear Asco; Mejoras en la depuracion de aguas residuales desde el inicio de la explotacion de la Central Nuclear de Asco

Energy Technology Data Exchange (ETDEWEB)

Esparza Martin, J. L.; Boronat Medico, M.

2014-07-01

Sanitary sewage in the Central Nuclear de Asco (CNA), are subject to a series of physico-chemical and biological processes in the wastewater waste (WWTP) before being discharged to the River Ebro. Since the beginning of the exploitation of CNA, the number of workers and administrative restrictions have evolved so that they have forced the execution of modifications of lowest and highest wingspan to comply with applicable legal requirements in the field of discharges. The overall objective of this work is to present the different stages of evolution of the WWTP of CNA from the start of operation of the plant up to the present day. The specific objective is to show the latest enhancements implanted in the sewage treatment plant and the benefits obtained. With technical improvements carried out in the WWTP of CNA, fixed the problem of disposal coming from the central nitrogen, one of the key problems and reason of failure to comply with the parameters imposed by the administration. (Author)

Atucha I nuclear power plant: Probabilistic safety study. Loss-of-coolant accidents

International Nuclear Information System (INIS)

Perez, S.S.

1987-01-01

The plant response to the group of events 'large coolant loss' in order to evaluate the associated risk is analyzed. The event that covers all events of similar sequence due to its evolution features, being also the most demanded, is selected as starting event. The representative event is the 'guillotine type rupture of cold primary branch'. An annual occurrence frequency of 10/year is assumed for this event. The safety systems, when the event occurs, must assure the reactor shutdown and the core cooling, creating a heat sink to remove the decay heat. The annual frequency of core meltdown due to great loss of coolant is obtained multiplying the annual frequency of the starting event by the probability of failure of involved safety systems. By means of failure trees, the following is obtained: a) probability of failure to demand of the boron injection shutdown system = 4 x 10 -2 ; b) probability of failure to demand of the high pressure safety injection = 3 x 10 -3 ; c) probability of emergency cooling system failure = 4.4 x 10 -2 . Therefore, the three possible sequences of core meltdown have the following frequencies: λ 1 = 4 x 10 -6 /year λ 2 = 3 x 10 -7 /year λ 3 = 4.4 x 10 -6 /year. (Author)

Suggestions of radiation protection instruments in ships used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants

International Nuclear Information System (INIS)

Warenmo, G.

1979-01-01

Some radiation protection measures are necessary in ships which will be used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants in order to protect the crew from unnecessarily high radiation doses and to ensure that not allowable values occur. Such measures are discussed in this report as well as suitable radiation protection instruments for such ships. (E.R.)

75 FR 9576 - Civil Nuclear Policy Mission to Central and Eastern Europe

Science.gov (United States)

2010-03-03

.... civil nuclear industry. Increasing energy demands, dependence on Russian fossil fuels, and a small but aging fleet of Russian reactor technologies is colliding with pressure from the EU to meet stricter..., language included in the Czech Republic's nuclear tender allows for the awarded company to have the...

Seismotectonic model of Central Europe

International Nuclear Information System (INIS)

Prochazkova, D.; Roth, Z.

1994-01-01

Earthquakes belong to natural disasters which are associated with tectonic processes in the interior of the Earth. They are extremely devastating in populated areas; they cause human losses and damage personal estates and the environment. To mitigate the potential effects of earthquakes it is necessary that relief and mitigation structures operate following an earthquake, but it is also essential to stimulate and enhance preparedness and prevention. Prevention includes the development of scenarios of potential earthquakes, hazard mapping, formulation of regulations, etc. Preparedness includes the installation and operation of warning systems, establishing communication networks to operate before, during, and after earthquakes. As nuclear technology belongs to high-risk technologies with regard to human health and the environment and its hazard substantially increases in consequence of earthquakes, in the siting of a nuclear plant engineering solutions are generally available to mitigate the potential vibratory effects through design. For the choice of a suitable engineering solution, reliable data must be processed by reliable techniques. The IAEA safety guide of the safety series No. 50-SG-S1(Rev. 1) specifies the demands on data and on their processing and also on the regional seismotectonic model. With a view of this the regional seismotectonic model of Central Europe was created. The paper presents regional geological characteristics of Central Europe and a chronological model of neotectonic movements in Central Europe with specification of neotectonic regional units and their present movements. Moreover, it contains earthquake characteristics for Central Europe and the specification of seismogenic movements. It was found that the genesis of local regions with occurrence of the strongest earthquakes is connected with several movement trends in the last 5 Ma. Six more or less tectonically separate regional units were revealed. The earthquake epicenters often

1981 Annual status report. Nuclear measurements

International Nuclear Information System (INIS)

1982-01-01

The Nuclear Measurements programme is divided into two main projects, Nuclear Data on the one hand and Nuclear Reference Materials and Techniques on the other. In the former the JRC actions form part of world-wide sets of actions to establish reliable, and in many cases very precise, figures for important nuclear parameters - e.g. neutron interaction cross-sections, radio-nuclide half lives. In this work the Central Bureau for Nuclear Measurements (CBNM) pays particular attention to the specific needs of the Community and to complement similar actions undertaken in the laboratories belonging to the Member States. Concerning Nuclear Reference Materials and Techniques the actions are to provide materials to which analytical and other measurements carried out in the nuclear industry or by the nuclear community can be referred. The basic aim of the Nuclear measurement programme is therefore to develop nuclear metrology with special orientation towards satisfying the demands for basic nuclear data and for materials and methods or reference

Nuclear Power in South-Central Brazil

International Nuclear Information System (INIS)

Cintra do Prado, L.

1966-01-01

The region of South-Central Brazil includes the states of Sao Paulo, Rio de Janeiro, Guanabara and Minas Gerais. The most recent power study was made by Canambra Engineering Consultants Limited. This group reported that the public-grid electricity output for the area in 1962 was 2.16 GW (average generation), with an installed capacity of 3.41 GW and annual mean load factor of 63.4; an increase in power requirements for 1970 was forecast, corresponding to an average output of 5.37 GW and an installed capacity of 8.3 GW. This forecast was based on an annual growth rate of 11.9% in generation. ''The energy requirements have grown at an average annual rate of 10.9% since 1955; however, the present forecast is based on the assumption of power being available as required, and hence includes the suppressed demand resulting from existing restrictions in generating and distribution capacity''

Experience gained in enhancing operational safety at ComEd`s nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Elias, D [Commonwealth Edison Co. (United States)

1997-09-01

The following aspects of experience gained in enhancing operational safety at Comed`s nuclear power plants are discussed: nuclear safety policy; centralization/decentralization; typical nuclear operating organization; safety review boards; human performance enhancement; elements of effective nuclear oversight.

Law no. 111/1996 on the safe deployment of nuclear activities - A law central to the Romanian nuclear law system

International Nuclear Information System (INIS)

Chiripus, Vlad-Ionut

2004-01-01

Law no. 111/1996 on the safe deployment of nuclear activities was published in its original form in the Official Gazette of Romania, Part no. 267 of 29th October 1996. The complexity of this law prevents from performing a comprehensive analysis of the legal provisions thereof for which reason the author shall review only those aspects he consider to be relevant to the issues dealt with by this law. Furthermore, as the author intends his undertaking to be a comparative analysis of Law no. 111/1996 in its successive stages - from its issue till the present - he uses mostly the present tense even though the law has been amended and in some respects the changes are quite significant. The presentation contains the following three sections: 1. Passing of Law no. 111/1996 on the safe deployment of nuclear activities - a turning point in the development of the Romanian nuclear law; 2. The successive modifications of Law no. 111/1996 on safe deployment of nuclear activities; 3. Law no. 193/2003 for the modification and completion of Law no. 111/1996 on the safe deployment of nuclear activities - a key moment in the modernization of Romanian nuclear law and harmonization with the relevant international requirement. In conclusion, the issue of Law no. 111/1996 on safe deployment of nuclear activities represents a turning point in the development of Romanian nuclear law. From this moment on one may regard it as a modern area of the Romanian law, European in spirit. The pre-existent legal framework - namely the Law no. 61/1974 on the deployment of activities in the Romanian nuclear field - was no longer up to the existing standards and its replacement by a new, modern law, fully harmonized with the European and NATO accession requirements was a must. Such a new, European law was to fully guarantee the safe deployment of nuclear activities for exclusively peaceful purposes, so that the requirements regarding the nuclear safety, protection of professionally exposed personnel

A Study on the Nuclear Foreign Policy

International Nuclear Information System (INIS)

Lee, Byung Wook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Oh, K. B.; Yang, M. H.; Lee, K. S.

2007-12-01

This study approaches the international trends related to nuclear non-proliferation in four aspects. First, this study analyzes the trend of the international nuclear non-proliferation regime, which includes the Treaty on the Non-proliferation of Nuclear Weapons (NPT), the international nuclear export control regime and proposals for assurance of nuclear fuel supply. Second, this study analyzes the trend of international nuclear organizations, which includes the International Atomic Energy Agency (IAEA), a central body of development of nuclear technology and international nuclear diplomacy, and the Organization for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA), a intergovernmental organization to consist of a group of nuclear advanced countries. Third, this study analyzes the trends of the U.S.'s nuclear foreign policies, particularly nuclear non-proliferation. Fourth, this study analyzes the nuclear issues of North Korea and Iran as they cause serious concerns to a international society

A Study on the Nuclear Foreign Policy

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Wook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Oh, K. B.; Yang, M. H.; Lee, K. S

2007-12-15

This study approaches the international trends related to nuclear non-proliferation in four aspects. First, this study analyzes the trend of the international nuclear non-proliferation regime, which includes the Treaty on the Non-proliferation of Nuclear Weapons (NPT), the international nuclear export control regime and proposals for assurance of nuclear fuel supply. Second, this study analyzes the trend of international nuclear organizations, which includes the International Atomic Energy Agency (IAEA), a central body of development of nuclear technology and international nuclear diplomacy, and the Organization for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA), a intergovernmental organization to consist of a group of nuclear advanced countries. Third, this study analyzes the trends of the U.S.'s nuclear foreign policies, particularly nuclear non-proliferation. Fourth, this study analyzes the nuclear issues of North Korea and Iran as they cause serious concerns to a international society.

Analysis of the phenomena associated with structural damage using real time vibration analysis

International Nuclear Information System (INIS)

Garcia Peyrano, O; Cismondi, L; Damiani, H; Torres, E

2004-01-01

It is of interest to have analytical methodologies available for the dynamic behavior of large mechanical structures like those in thermal cycle systems of nuclear power plants or in transport systems during the experimental stage prior to their construction, as happens in aeronautics, where prototypes are tested in experimental banks on a scale of 1 to 1. The same does not occur with systems for the generation of electrical energy such as a nuclear power plant or in ships, competition automobiles, railway systems, etc. Not because of the technical impossibility but because of the high costs involved. This work aims to implement a technology based on the analysis of the vibrations to obtain a profile of the modal dynamic response and its influence on the critical components of the mechanisms with the particularity of detecting the preventive location of the component that may suffer a potential damage. The Vibrations Analysis Laboratory has resolved different cases in the Embalse Nuclear Plant, in the Atucha Nuclear Plant, in the Heavy Water Industrial Plant, in the automobile industry and in other industrial areas (CW)

Quality assurance programmes and normalization for the Argentine-Brazilian integration

International Nuclear Information System (INIS)

Biernat, A.E.

1987-01-01

Within the frame of the tasks developed by the Argentine-Brazilian Contractors Coordination Committee in the nuclear area, which was at the beginning promoted by the Contractor Committee of the Argentine Association of Nuclear Technology, a working team was created between both countries in order to analyze the existing regulations and the Quality Assurance systems applied in Brazil and Argentina for their nuclear projects. This paper describes the steps to be followed so as to fulfill the compatibility of the rules, quality assurance and firm certification, laboratories, personnel and materials, and the applicable quality assurance programmes. At first, the methodology applied was the collection of the information and the existing regulations in each one of the countries, to exchange them, analyze them and arrange joint meetings and organize a seminar with experts from both countries to develop and discuss the objectives of this working team. As a result of these activities, the criteria adopted will allow, together with another actions, that both Argentine and Brazilian firms make exchanges and integrations in the nuclear field to supply Atucha II and Angra II. (Author)

Nuclear energy: a world of service to humanity. 27th annual conference of the Canadian Nuclear Society and 30th Canadian Nuclear Society/Canadian Nuclear Association student conference

International Nuclear Information System (INIS)

2006-01-01

The 27th Annual conference of the Canadian Nuclear Society was held on June 11-14, 2006 in Toronto, Ontario, Canada. The conference gathered close to 400 scientists, engineers, technologists and students interested in all aspects and applications of energy from the atom. The central objective of this conference was to provide a forum for exchange of views on how this technical enterprise can best serve the needs of humanity, now and in the future. The plenary sessions addressed broad industrial and commercial developments in the field. Over eighty papers were presented in 15 technical sessions on the following topics: safety analysis; plant refurbishment; control room operation; nuclear chemistry and materials; advanced reactor design; plant operation; reactor physics; safety analysis; nuclear instrumentation; and, nuclear general topics. Embedded in the conference was the 30th student conference, sponsored by the Canadian Nuclear Society and the Canadian Nuclear Association. Over thirty-five papers were presented in five sessions on the following topics: corrosion processes; control systems / physics / modelling; and, chemistry / chemical engineering

Nuclear power: tomorrow's energy source

International Nuclear Information System (INIS)

2002-01-01

In France, 76% of electricity is produced by nuclear power. The industry's pricing levels are among the most competitive in Europe. Thanks to its 58 nuclear reactors France enjoys almost 50% energy autonomy thus ensuring a highly stable supply. Equally, as a non-producer of greenhouse gases, the nuclear sector can rightfully claim to have an environmentally friendly impact. Against a background to increasing global demand with predictions that fossil fuels will run out and global warming a central issue, it is important to use production methods which face up to problems of this nature. There is no question that nuclear energy has a vital role to play alongside other energy sources. (authors)

Centrality dependence of the nuclear modification factor of charged pions, kaons, and protons in Pb-Pb collisions at $\\sqrt{s_{NN}}$ = 2.76 TeV

CERN Document Server

Adam, Jaroslav; Aggarwal, Madan Mohan; Aglieri Rinella, Gianluca; Agnello, Michelangelo; Agrawal, Neelima; Ahammed, Zubayer; Ahn, Sang Un; Aimo, Ilaria; Aiola, Salvatore; Ajaz, Muhammad; Akindinov, Alexander; Alam, Sk Noor; Aleksandrov, Dmitry; Alessandro, Bruno; Alexandre, Didier; Alfaro Molina, Jose Ruben; Alici, Andrea; Alkin, Anton; Millan Almaraz, Jesus Roberto; Alme, Johan; Alt, Torsten; Altinpinar, Sedat; Altsybeev, Igor; Alves Garcia Prado, Caio; Andrei, Cristian; Andronic, Anton; Anguelov, Venelin; Anielski, Jonas; Anticic, Tome; Antinori, Federico; Antonioli, Pietro; Aphecetche, Laurent Bernard; Appelshaeuser, Harald; Arcelli, Silvia; Armesto Perez, Nestor; Arnaldi, Roberta; Arsene, Ionut Cristian; Arslandok, Mesut; Audurier, Benjamin; Augustinus, Andre; Averbeck, Ralf Peter; Azmi, Mohd Danish; Bach, Matthias Jakob; Badala, Angela; Baek, Yong Wook; Bagnasco, Stefano; Bailhache, Raphaelle Marie; Bala, Renu; Baldisseri, Alberto; Baltasar Dos Santos Pedrosa, Fernando; Baral, Rama Chandra; Barbano, Anastasia Maria; Barbera, Roberto; Barile, Francesco; Barnafoldi, Gergely Gabor; Barnby, Lee Stuart; Ramillien Barret, Valerie; Bartalini, Paolo; Barth, Klaus; Bartke, Jerzy Gustaw; Bartsch, Esther; Basile, Maurizio; Bastid, Nicole; Basu, Sumit; Bathen, Bastian; Batigne, Guillaume; Batista Camejo, Arianna; Batyunya, Boris; Batzing, Paul Christoph; Bearden, Ian Gardner; Beck, Hans; Bedda, Cristina; Behera, Nirbhay Kumar; Belikov, Iouri; Bellini, Francesca; Bello Martinez, Hector; Bellwied, Rene; Belmont Iii, Ronald John; Belmont Moreno, Ernesto; Belyaev, Vladimir; Bencedi, Gyula; Beole, Stefania; Berceanu, Ionela; Bercuci, Alexandru; Berdnikov, Yaroslav; Berenyi, Daniel; Bertens, Redmer Alexander; Berzano, Dario; Betev, Latchezar; Bhasin, Anju; Bhat, Inayat Rasool; Bhati, Ashok Kumar; Bhattacharjee, Buddhadeb; Bhom, Jihyun; Bianchi, Livio; Bianchi, Nicola; Bianchin, Chiara; Bielcik, Jaroslav; Bielcikova, Jana; Bilandzic, Ante; Biswas, Rathijit; Biswas, Saikat; Bjelogrlic, Sandro; Blair, Justin Thomas; Blanco, Fernando; Blau, Dmitry; Blume, Christoph; Bock, Friederike; Bogdanov, Alexey; Boggild, Hans; Boldizsar, Laszlo; Bombara, Marek; Book, Julian Heinz; Borel, Herve; Borissov, Alexander; Borri, Marcello; Bossu, Francesco; Botta, Elena; Boettger, Stefan; Braun-Munzinger, Peter; Bregant, Marco; Breitner, Timo Gunther; Broker, Theo Alexander; Browning, Tyler Allen; Broz, Michal; Brucken, Erik Jens; Bruna, Elena; Bruno, Giuseppe Eugenio; Budnikov, Dmitry; Buesching, Henner; Bufalino, Stefania; Buncic, Predrag; Busch, Oliver; Buthelezi, Edith Zinhle; Bashir Butt, Jamila; Buxton, Jesse Thomas; Caffarri, Davide; Cai, Xu; Caines, Helen Louise; Calero Diaz, Liliet; Caliva, Alberto; Calvo Villar, Ernesto; Camerini, Paolo; Carena, Francesco; Carena, Wisla; Carnesecchi, Francesca; Castillo Castellanos, Javier Ernesto; Castro, Andrew John; Casula, Ester Anna Rita; Cavicchioli, Costanza; Ceballos Sanchez, Cesar; Cepila, Jan; Cerello, Piergiorgio; Cerkala, Jakub; Chang, Beomsu; Chapeland, Sylvain; Chartier, Marielle; Charvet, Jean-Luc Fernand; Chattopadhyay, Subhasis; Chattopadhyay, Sukalyan; Chelnokov, Volodymyr; Cherney, Michael Gerard; Cheshkov, Cvetan Valeriev; Cheynis, Brigitte; Chibante Barroso, Vasco Miguel; Dobrigkeit Chinellato, David; Chochula, Peter; Choi, Kyungeon; Chojnacki, Marek; Choudhury, Subikash; Christakoglou, Panagiotis; Christensen, Christian Holm; Christiansen, Peter; Chujo, Tatsuya; Chung, Suh-Urk; Zhang, Chunhui; Cicalo, Corrado; Cifarelli, Luisa; Cindolo, Federico; Cleymans, Jean Willy Andre; Colamaria, Fabio Filippo; Colella, Domenico; Collu, Alberto; Colocci, Manuel; Conesa Balbastre, Gustavo; Conesa Del Valle, Zaida; Connors, Megan Elizabeth; Contreras Nuno, Jesus Guillermo; Cormier, Thomas Michael; Corrales Morales, Yasser; Cortes Maldonado, Ismael; Cortese, Pietro; Cosentino, Mauro Rogerio; Costa, Filippo; Crochet, Philippe; Cruz Albino, Rigoberto; Cuautle Flores, Eleazar; Cunqueiro Mendez, Leticia; Dahms, Torsten; Dainese, Andrea; Danu, Andrea; Das, Debasish; Das, Indranil; Das, Supriya; Dash, Ajay Kumar; Dash, Sadhana; De, Sudipan; De Caro, Annalisa; De Cataldo, Giacinto; De Cuveland, Jan; De Falco, Alessandro; De Gruttola, Daniele; De Marco, Nora; De Pasquale, Salvatore; Deisting, Alexander; Deloff, Andrzej; Denes, Ervin Sandor; D'Erasmo, Ginevra; Di Bari, Domenico; Di Mauro, Antonio; Di Nezza, Pasquale; Diaz Corchero, Miguel Angel; Dietel, Thomas; Dillenseger, Pascal; Divia, Roberto; Djuvsland, Oeystein; Dobrin, Alexandru Florin; Dobrowolski, Tadeusz Antoni; Domenicis Gimenez, Diogenes; Donigus, Benjamin; Dordic, Olja; Drozhzhova, Tatiana; Dubey, Anand Kumar; Dubla, Andrea; Ducroux, Laurent; Dupieux, Pascal; Ehlers Iii, Raymond James; Elia, Domenico; Engel, Heiko; Erazmus, Barbara Ewa; Erdemir, Irem; Erhardt, Filip; Eschweiler, Dominic; Espagnon, Bruno; Estienne, Magali Danielle; Esumi, Shinichi; Eum, Jongsik; Evans, David; Evdokimov, Sergey; Eyyubova, Gyulnara; Fabbietti, Laura; Fabris, Daniela; Faivre, Julien; Fantoni, Alessandra; Fasel, Markus; Feldkamp, Linus; Felea, Daniel; Feliciello, Alessandro; Feofilov, Grigorii; Ferencei, Jozef; Fernandez Tellez, Arturo; Gonzalez Ferreiro, Elena; Ferretti, Alessandro; Festanti, Andrea; Feuillard, Victor Jose Gaston; Figiel, Jan; Araujo Silva Figueredo, Marcel; Filchagin, Sergey; Finogeev, Dmitry; Fiore, Enrichetta Maria; Fleck, Martin Gabriel; Floris, Michele; Foertsch, Siegfried Valentin; Foka, Panagiota; Fokin, Sergey; Fragiacomo, Enrico; Francescon, Andrea; Frankenfeld, Ulrich Michael; Fuchs, Ulrich; Furget, Christophe; Furs, Artur; Fusco Girard, Mario; Gaardhoeje, Jens Joergen; Gagliardi, Martino; Gago Medina, Alberto Martin; Gallio, Mauro; Gangadharan, Dhevan Raja; Ganoti, Paraskevi; Gao, Chaosong; Garabatos Cuadrado, Jose; Garcia-Solis, Edmundo Javier; Gargiulo, Corrado; Gasik, Piotr Jan; Germain, Marie; Gheata, Andrei George; Gheata, Mihaela; Ghosh, Premomoy; Ghosh, Sanjay Kumar; Gianotti, Paola; Giubellino, Paolo; Giubilato, Piero; Gladysz-Dziadus, Ewa; Glassel, Peter; Gomez Coral, Diego Mauricio; Gomez Ramirez, Andres; Gonzalez Zamora, Pedro; Gorbunov, Sergey; Gorlich, Lidia Maria; Gotovac, Sven; Grabski, Varlen; Graczykowski, Lukasz Kamil; Graham, Katie Leanne; Grelli, Alessandro; Grigoras, Alina Gabriela; Grigoras, Costin; Grigoryev, Vladislav; Grigoryan, Ara; Grigoryan, Smbat; Grynyov, Borys; Grion, Nevio; Grosse-Oetringhaus, Jan Fiete; Grossiord, Jean-Yves; Grosso, Raffaele; Guber, Fedor; Guernane, Rachid; Guerzoni, Barbara; Gulbrandsen, Kristjan Herlache; Gulkanyan, Hrant; Gunji, Taku; Gupta, Anik; Gupta, Ramni; Haake, Rudiger; Haaland, Oystein Senneset; Hadjidakis, Cynthia Marie; Haiduc, Maria; Hamagaki, Hideki; Hamar, Gergoe; Hansen, Alexander; Harris, John William; Hartmann, Helvi; Harton, Austin Vincent; Hatzifotiadou, Despina; Hayashi, Shinichi; Heckel, Stefan Thomas; Heide, Markus Ansgar; Helstrup, Haavard; Herghelegiu, Andrei Ionut; Herrera Corral, Gerardo Antonio; Hess, Benjamin Andreas; Hetland, Kristin Fanebust; Hilden, Timo Eero; Hillemanns, Hartmut; Hippolyte, Boris; Hosokawa, Ritsuya; Hristov, Peter Zahariev; Huang, Meidana; Humanic, Thomas; Hussain, Nur; Hussain, Tahir; Hutter, Dirk; Hwang, Dae Sung; Ilkaev, Radiy; Ilkiv, Iryna; Inaba, Motoi; Ippolitov, Mikhail; Irfan, Muhammad; Ivanov, Marian; Ivanov, Vladimir; Izucheev, Vladimir; Jacobs, Peter Martin; Jadlovska, Slavka; Jahnke, Cristiane; Jang, Haeng Jin; Janik, Malgorzata Anna; Pahula Hewage, Sandun; Jena, Chitrasen; Jena, Satyajit; Jimenez Bustamante, Raul Tonatiuh; Jones, Peter Graham; Jung, Hyungtaik; Jusko, Anton; Kalinak, Peter; Kalweit, Alexander Philipp; Kamin, Jason Adrian; Kang, Ju Hwan; Kaplin, Vladimir; Kar, Somnath; Karasu Uysal, Ayben; Karavichev, Oleg; Karavicheva, Tatiana; Karayan, Lilit; Karpechev, Evgeny; Kebschull, Udo Wolfgang; Keidel, Ralf; Keijdener, Darius Laurens; Keil, Markus; Khan, Kamal; Khan, Mohammed Mohisin; Khan, Palash; Khan, Shuaib Ahmad; Khanzadeev, Alexei; Kharlov, Yury; Kileng, Bjarte; Kim, Beomkyu; Kim, Do Won; Kim, Dong Jo; Kim, Hyeonjoong; Kim, Jinsook; Kim, Mimae; Kim, Minwoo; Kim, Se Yong; Kim, Taesoo; Kirsch, Stefan; Kisel, Ivan; Kiselev, Sergey; Kisiel, Adam Ryszard; Kiss, Gabor; Klay, Jennifer Lynn; Klein, Carsten; Klein, Jochen; Klein-Boesing, Christian; Kluge, Alexander; Knichel, Michael Linus; Knospe, Anders Garritt; Kobayashi, Taiyo; Kobdaj, Chinorat; Kofarago, Monika; Kollegger, Thorsten; Kolozhvari, Anatoly; Kondratev, Valerii; Kondratyeva, Natalia; Kondratyuk, Evgeny; Konevskikh, Artem; Kopcik, Michal; Kour, Mandeep; Kouzinopoulos, Charalampos; Kovalenko, Oleksandr; Kovalenko, Vladimir; Kowalski, Marek; Koyithatta Meethaleveedu, Greeshma; Kral, Jiri; Kralik, Ivan; Kravcakova, Adela; Krelina, Michal; Kretz, Matthias; Krivda, Marian; Krizek, Filip; Kryshen, Evgeny; Krzewicki, Mikolaj; Kubera, Andrew Michael; Kucera, Vit; Kugathasan, Thanushan; Kuhn, Christian Claude; Kuijer, Paulus Gerardus; Kulakov, Igor; Kumar, Ajay; Kumar, Jitendra; Lokesh, Kumar; Kurashvili, Podist; Kurepin, Alexander; Kurepin, Alexey; Kuryakin, Alexey; Kushpil, Svetlana; Kweon, Min Jung; Kwon, Youngil; La Pointe, Sarah Louise; La Rocca, Paola; Lagana Fernandes, Caio; Lakomov, Igor; Langoy, Rune; Lara Martinez, Camilo Ernesto; Lardeux, Antoine Xavier; Lattuca, Alessandra; Laudi, Elisa; Lea, Ramona; Leardini, Lucia; Lee, Graham Richard; Lee, Seongjoo; Legrand, Iosif; Lehas, Fatiha; Lemmon, Roy Crawford; Lenti, Vito; Leogrande, Emilia; Leon Monzon, Ildefonso; Leoncino, Marco; Levai, Peter; Li, Shuang; Li, Xiaomei; Lien, Jorgen Andre; Lietava, Roman; Lindal, Svein; Lindenstruth, Volker; Lippmann, Christian; Lisa, Michael Annan; Ljunggren, Hans Martin; Lodato, Davide Francesco; Lonne, Per-Ivar; Loginov, Vitaly; Loizides, Constantinos; Lopez, Xavier Bernard; Lopez Torres, Ernesto; Lowe, Andrew John; Luettig, Philipp Johannes; Lunardon, Marcello; Luparello, Grazia; Ferreira Natal Da Luz, Pedro Hugo; Maevskaya, Alla; Mager, Magnus; Mahajan, Sanjay; Mahmood, Sohail Musa; Maire, Antonin; Majka, Richard Daniel; Malaev, Mikhail; Maldonado Cervantes, Ivonne Alicia; Malinina, Liudmila; Mal'Kevich, Dmitry; Malzacher, Peter; Mamonov, Alexander; Manko, Vladislav; Manso, Franck; Manzari, Vito; Marchisone, Massimiliano; Mares, Jiri; Margagliotti, Giacomo Vito; Margotti, Anselmo; Margutti, Jacopo; Marin, Ana Maria; Markert, Christina; Marquard, Marco; Martin, Nicole Alice; Martin Blanco, Javier; Martinengo, Paolo; Martinez Hernandez, Mario Ivan; Martinez-Garcia, Gines; Martinez Pedreira, Miguel; Martynov, Yevgen; Mas, Alexis Jean-Michel; Masciocchi, Silvia; Masera, Massimo; Masoni, Alberto; Massacrier, Laure Marie; Mastroserio, Annalisa; Masui, Hiroshi; Matyja, Adam Tomasz; Mayer, Christoph; Mazer, Joel Anthony; Mazzoni, Alessandra Maria; Mcdonald, Daniel; Meddi, Franco; Melikyan, Yuri; Menchaca-Rocha, Arturo Alejandro; Meninno, Elisa; Mercado-Perez, Jorge; Meres, Michal; Miake, Yasuo; Mieskolainen, Matti Mikael; Mikhaylov, Konstantin; Milano, Leonardo; Milosevic, Jovan; Minervini, Lazzaro Manlio; Mischke, Andre; Mishra, Aditya Nath; Miskowiec, Dariusz Czeslaw; Mitra, Jubin; Mitu, Ciprian Mihai; Mohammadi, Naghmeh; Mohanty, Bedangadas; Molnar, Levente; Montano Zetina, Luis Manuel; Montes Prado, Esther; Morando, Maurizio; Moreira De Godoy, Denise Aparecida; Moretto, Sandra; Morreale, Astrid; Morsch, Andreas; Muccifora, Valeria; Mudnic, Eugen; Muhlheim, Daniel Michael; Muhuri, Sanjib; Mukherjee, Maitreyee; Mulligan, James Declan; Gameiro Munhoz, Marcelo; Murray, Sean; Musa, Luciano; Musinsky, Jan; Nandi, Basanta Kumar; Nania, Rosario; Nappi, Eugenio; Naru, Muhammad Umair; Nattrass, Christine; Nayak, Kishora; Nayak, Tapan Kumar; Nazarenko, Sergey; Nedosekin, Alexander; Nellen, Lukas; Ng, Fabian; Nicassio, Maria; Niculescu, Mihai; Niedziela, Jeremi; Nielsen, Borge Svane; Nikolaev, Sergey; Nikulin, Sergey; Nikulin, Vladimir; Noferini, Francesco; Nomokonov, Petr; Nooren, Gerardus; Cabanillas Noris, Juan Carlos; Norman, Jaime; Nyanin, Alexander; Nystrand, Joakim Ingemar; Oeschler, Helmut Oskar; Oh, Saehanseul; Oh, Sun Kun; Ohlson, Alice Elisabeth; Okatan, Ali; Okubo, Tsubasa; Olah, Laszlo; Oleniacz, Janusz; Oliveira Da Silva, Antonio Carlos; Oliver, Michael Henry; Onderwaater, Jacobus; Oppedisano, Chiara; Orava, Risto; Ortiz Velasquez, Antonio; Oskarsson, Anders Nils Erik; Otwinowski, Jacek Tomasz; Oyama, Ken; Ozdemir, Mahmut; Pachmayer, Yvonne Chiara; Pagano, Paola; Paic, Guy; Pajares Vales, Carlos; Pal, Susanta Kumar; Pan, Jinjin; Pandey, Ashutosh Kumar; Pant, Divyash; Papcun, Peter; Papikyan, Vardanush; Pappalardo, Giuseppe; Pareek, Pooja; Park, Woojin; Parmar, Sonia; Passfeld, Annika; Paticchio, Vincenzo; Patra, Rajendra Nath; Paul, Biswarup; Peitzmann, Thomas; Pereira Da Costa, Hugo Denis Antonio; Pereira De Oliveira Filho, Elienos; Peresunko, Dmitry Yurevich; Perez Lara, Carlos Eugenio; Perez Lezama, Edgar; Peskov, Vladimir; Pestov, Yury; Petracek, Vojtech; Petrov, Viacheslav; Petrovici, Mihai; Petta, Catia; Piano, Stefano; Pikna, Miroslav; Pillot, Philippe; Pinazza, Ombretta; Pinsky, Lawrence; Piyarathna, Danthasinghe; Ploskon, Mateusz Andrzej; Planinic, Mirko; Pluta, Jan Marian; Pochybova, Sona; Podesta Lerma, Pedro Luis Manuel; Poghosyan, Martin; Polishchuk, Boris; Poljak, Nikola; Poonsawat, Wanchaloem; Pop, Amalia; Porteboeuf, Sarah Julie; Porter, R Jefferson; Pospisil, Jan; Prasad, Sidharth Kumar; Preghenella, Roberto; Prino, Francesco; Pruneau, Claude Andre; Pshenichnov, Igor; Puccio, Maximiliano; Puddu, Giovanna; Pujahari, Prabhat Ranjan; Punin, Valery; Putschke, Jorn Henning; Qvigstad, Henrik; Rachevski, Alexandre; Raha, Sibaji; Rajput, Sonia; Rak, Jan; Rakotozafindrabe, Andry Malala; Ramello, Luciano; Raniwala, Rashmi; Raniwala, Sudhir; Rasanen, Sami Sakari; Rascanu, Bogdan Theodor; Rathee, Deepika; Read, Kenneth Francis; Real, Jean-Sebastien; Redlich, Krzysztof; Reed, Rosi Jan; Rehman, Attiq Ur; Reichelt, Patrick Simon; Reidt, Felix; Ren, Xiaowen; Renfordt, Rainer Arno Ernst; Reolon, Anna Rita; Reshetin, Andrey; Rettig, Felix Vincenz; Revol, Jean-Pierre; Reygers, Klaus Johannes; Riabov, Viktor; Ricci, Renato Angelo; Richert, Tuva Ora Herenui; Richter, Matthias Rudolph; Riedler, Petra; Riegler, Werner; Riggi, Francesco; Ristea, Catalin-Lucian; Rivetti, Angelo; Rocco, Elena; Rodriguez Cahuantzi, Mario; Rodriguez Manso, Alis; Roeed, Ketil; Rogochaya, Elena; Rohr, David Michael; Roehrich, Dieter; Romita, Rosa; Ronchetti, Federico; Ronflette, Lucile; Rosnet, Philippe; Rossi, Andrea; Roukoutakis, Filimon; Roy, Ankhi; Roy, Christelle Sophie; Roy, Pradip Kumar; Rubio Montero, Antonio Juan; Rui, Rinaldo; Russo, Riccardo; Ryabinkin, Evgeny; Ryabov, Yury; Rybicki, Andrzej; Sadovskiy, Sergey; Safarik, Karel; Sahlmuller, Baldo; Sahoo, Pragati; Sahoo, Raghunath; Sahoo, Sarita; Sahu, Pradip Kumar; Saini, Jogender; Sakai, Shingo; Saleh, Mohammad Ahmad; Salgado Lopez, Carlos Alberto; Salzwedel, Jai Samuel Nielsen; Sambyal, Sanjeev Singh; Samsonov, Vladimir; Sanchez Castro, Xitzel; Sandor, Ladislav; Sandoval, Andres; Sano, Masato; Sarkar, Debojit; Scapparone, Eugenio; Scarlassara, Fernando; Scharenberg, Rolf Paul; Schiaua, Claudiu Cornel; Schicker, Rainer Martin; Schmidt, Christian Joachim; Schmidt, Hans Rudolf; Schuchmann, Simone; Schukraft, Jurgen; Schulc, Martin; Schuster, Tim Robin; Schutz, Yves Roland; Schwarz, Kilian Eberhard; Schweda, Kai Oliver; Scioli, Gilda; Scomparin, Enrico; Scott, Rebecca Michelle; Seger, Janet Elizabeth; Sekiguchi, Yuko; Sekihata, Daiki; Selyuzhenkov, Ilya; Senosi, Kgotlaesele; Seo, Jeewon; Serradilla Rodriguez, Eulogio; Sevcenco, Adrian; Shabanov, Arseniy; Shabetai, Alexandre; Shadura, Oksana; Shahoyan, Ruben; Shangaraev, Artem; Sharma, Ankita; Sharma, Mona; Sharma, Monika; Sharma, Natasha; Shigaki, Kenta; Shtejer Diaz, Katherin; Sibiryak, Yury; Siddhanta, Sabyasachi; Sielewicz, Krzysztof Marek; Siemiarczuk, Teodor; Silvermyr, David Olle Rickard; Silvestre, Catherine Micaela; Simatovic, Goran; Simonetti, Giuseppe; Singaraju, Rama Narayana; Singh, Ranbir; Singha, Subhash; Singhal, Vikas; Sinha, Bikash; Sarkar - Sinha, Tinku; Sitar, Branislav; Sitta, Mario; Skaali, Bernhard; Slupecki, Maciej; Smirnov, Nikolai; Snellings, Raimond; Snellman, Tomas Wilhelm; Soegaard, Carsten; Soltz, Ron Ariel; Song, Jihye; Song, Myunggeun; Song, Zixuan; Soramel, Francesca; Sorensen, Soren Pontoppidan; Spacek, Michal; Spiriti, Eleuterio; Sputowska, Iwona Anna; Spyropoulou-Stassinaki, Martha; Srivastava, Brijesh Kumar; Stachel, Johanna; Stan, Ionel; Stefanek, Grzegorz; Steinpreis, Matthew Donald; Stenlund, Evert Anders; Steyn, Gideon Francois; Stiller, Johannes Hendrik; Stocco, Diego; Strmen, Peter; Alarcon Do Passo Suaide, Alexandre; Sugitate, Toru; Suire, Christophe Pierre; Suleymanov, Mais Kazim Oglu; Sultanov, Rishat; Sumbera, Michal; Symons, Timothy; Szabo, Alexander; Szanto De Toledo, Alejandro; Szarka, Imrich; Szczepankiewicz, Adam; Szymanski, Maciej Pawel; Takahashi, Jun; Tambave, Ganesh Jagannath; Tanaka, Naoto; Tangaro, Marco-Antonio; Tapia Takaki, Daniel Jesus; Tarantola Peloni, Attilio; Tarhini, Mohamad; Tariq, Mohammad; Tarzila, Madalina-Gabriela; Tauro, Arturo; Tejeda Munoz, Guillermo; Telesca, Adriana; Terasaki, Kohei; Terrevoli, Cristina; Teyssier, Boris; Thaeder, Jochen Mathias; Thomas, Deepa; Tieulent, Raphael Noel; Timmins, Anthony Robert; Toia, Alberica; Trogolo, Stefano; Trubnikov, Victor; Trzaska, Wladyslaw Henryk; Tsuji, Tomoya; Tumkin, Alexandr; Turrisi, Rosario; Tveter, Trine Spedstad; Ullaland, Kjetil; Uras, Antonio; Usai, Gianluca; Utrobicic, Antonija; Vajzer, Michal; Vala, Martin; Valencia Palomo, Lizardo; Vallero, Sara; Van Der Maarel, Jasper; Van Hoorne, Jacobus Willem; Van Leeuwen, Marco; Vanat, Tomas; Vande Vyvre, Pierre; Varga, Dezso; Diozcora Vargas Trevino, Aurora; Vargyas, Marton; Varma, Raghava; Vasileiou, Maria; Vasiliev, Andrey; Vauthier, Astrid; Vechernin, Vladimir; Veen, Annelies Marianne; Veldhoen, Misha; Velure, Arild; Venaruzzo, Massimo; Vercellin, Ermanno; Vergara Limon, Sergio; Vernet, Renaud; Verweij, Marta; Vickovic, Linda; Viesti, Giuseppe; Viinikainen, Jussi Samuli; Vilakazi, Zabulon; Villalobos Baillie, Orlando; Vinogradov, Alexander; Vinogradov, Leonid; Vinogradov, Yury; Virgili, Tiziano; Vislavicius, Vytautas; Viyogi, Yogendra; Vodopyanov, Alexander; Volkl, Martin Andreas; Voloshin, Kirill; Voloshin, Sergey; Volpe, Giacomo; Von Haller, Barthelemy; Vorobyev, Ivan; Vranic, Danilo; Vrlakova, Janka; Vulpescu, Bogdan; Vyushin, Alexey; Wagner, Boris; Wagner, Jan; Wang, Hongkai; Wang, Mengliang; Wang, Yifei; Watanabe, Daisuke; Watanabe, Yosuke; Weber, Michael; Weber, Steffen Georg; Wessels, Johannes Peter; Westerhoff, Uwe; Wiechula, Jens; Wikne, Jon; Wilde, Martin Rudolf; Wilk, Grzegorz Andrzej; Wilkinson, Jeremy John; Williams, Crispin; Windelband, Bernd Stefan; Winn, Michael Andreas; Yaldo, Chris G; Yang, Hongyan; Yang, Ping; Yano, Satoshi; Yin, Zhongbao; Yokoyama, Hiroki; Yoo, In-Kwon; Yurchenko, Volodymyr; Yushmanov, Igor; Zaborowska, Anna; Zaccolo, Valentina; Zaman, Ali; Zampolli, Chiara; Correia Zanoli, Henrique Jose; Zaporozhets, Sergey; Zardoshti, Nima; Zarochentsev, Andrey; Zavada, Petr; Zavyalov, Nikolay; Zbroszczyk, Hanna Paulina; Zgura, Sorin Ion; Zhalov, Mikhail; Zhang, Haitao; Zhang, Xiaoming; Zhang, Yonghong; Zhao, Chengxin; Zhigareva, Natalia; Zhou, Daicui; Zhou, You; Zhou, Zhuo; Zhu, Hongsheng; Zhu, Jianhui; Zhu, Xiangrong; Zichichi, Antonino; Zimmermann, Alice; Zimmermann, Markus Bernhard; Zinovjev, Gennady; Zyzak, Maksym

2016-03-25

Transverse momentum ($p_{\\rm{T}}$) spectra of pions, kaons, and protons up to $p_{\\rm{T}} = 20$ GeV/$c$ have been measured in Pb-Pb collisions at $\\sqrt{s_{\\rm NN}} = 2.76$ TeV using the ALICE detector for six different centrality classes covering 0-80%. The proton-to-pion and the kaon-to-pion ratios both show a distinct peak at $p_{\\rm{T}} \\approx 3$ GeV/$c$ in central Pb-Pb collisions that decreases towards more peripheral collisions. For $p_{\\rm{T}} > 10$ GeV/$c$, the nuclear modification factor is found to be the same for all three particle species in each centrality interval within systematic uncertainties of 10-20%. This suggests there is no direct interplay between the energy loss in the medium and the particle species composition in the hard core of the quenched jet. For $p_{\\rm{T}} < 10$ GeV/$c$, the data provide important constraints for models aimed at describing the transition from soft to hard physics.

The nuclear waste primer: A handbook for citizens

International Nuclear Information System (INIS)

Anon.

1987-01-01

A sourcebook of facts about the production of nuclear waste and radioactive materials, this volume looks at the debate over safe storage, transportation, and disposal of hazardous radioactive materials. Addressing such concerns as the dangers of nuclear waste, protecting the public, and affecting the decision-making process at all levels of government, this book explores the issues central to the handling and disposal of nuclear waste

First Conference on African Youth Nuclear Summit 2017: Nuclear for a Sustainable Future

International Nuclear Information System (INIS)

2017-03-01

Kenyan Young Generation in Nuclear (KYGN) hosted the inaugural African Youth Nuclear Summit, dubbed AYNS2017 that took place on the 27th to 30th March, 2017, Nairobi, Kenya. The participants were drawn from academia, research and development institutes, radiation services providers, health institutions, nuclear facilities and regulatory bodies. They shared experiences, exchanged ideas and built networks on issues related to safe application of nuclear science and technology. The theme of the summit was ''Nuclear for a Sustainable future'', which centered on three thematic areas: Nuclear powering Africa, Radiation Protection and safety culture; and application of nuclear science and technology for a sustainable future. The Director General, World Nuclear Association who pointed out that nuclear energy had made a major contribution to world energy output and was set to increase by two and half time by 2040. The importance of nuclear science and technology for a sustainable socio-economic development in Africa shared and highlight on many areas IAEA has helped member states in improving the life of its populations. The main activities of project 60 whose focus is to strengthen the nuclear security culture in East and Central Africa through improved regulation, training, capacity and awareness were highlighted

Turbine model for the Laguna Verde nucleo electric central based in the RELAP code; Modelo de turbina para la Central nucleoelectrica de Laguna Verde basado en el codigo RELAP

Energy Technology Data Exchange (ETDEWEB)

Cortes M, F.S.; Ramos P, J.C.; Salazar S, E.; Chavez M, C. [Facultad de Ingenieria, Division de Estudios de Posgrado, Grupo de Ingenieria Nuclear, UNAM (Mexico)]. e-mail: cchavez2@cableonline.com.mx

2003-07-01

The Nuclear Power stations as Laguna Verde occupy at the present time a place every time but important as non pollutant alternative, economic and trusty to generate electricity. It is for it that the Group of Nuclear Engineering of the Engineering Faculty (GrlNFI) of the National Autonomous University of Mexico (UNAM) it develops investigation projects applied to Nuclear Centrals. One of the projects in process is the development of a Classroom simulator, which it can configures to consent to diverse models of nuclear systems with training purposes in normal operation, or, to consent to specialized nuclear codes for the analysis of transitory events and have a severe accident. This work describes the development, implementation and it proves of a simplified model of the Main turbine to be integrated to the group of models of the Classroom simulator. It is part of the current effort of GrlNFI guided to obtain a representation of all the dynamic models necessary to simulate the Plant Balance of the Laguna Verde Central. It is included the development of the unfolding graphic which represent the modeling of the Main turbine, and of the control interface that allows the user to manipulate in simple way, direct and interactive this device during the training or the analysis. With this work it is wanted to contribute to the training of new technicians and to support the operation personnel of the Centrals. Also, the developed infrastructure is guided to contribute in the design and analysis of new Nuclear Power stations with the contribution of new computational tools for the visualization, simulation and process control. (Author)

Nuclear fuels accounting interface: River Bend experience

International Nuclear Information System (INIS)

Barry, J.E.

1986-01-01

This presentation describes nuclear fuel accounting activities from the perspective of nuclear fuels management and its interfaces. Generally, Nuclear Fuels-River Bend Nuclear Group (RBNG) is involved on a day-by-day basis with nuclear fuel materials accounting in carrying out is procurement, contract administration, processing, and inventory management duties, including those associated with its special nuclear materials (SNM)-isotopics accountability oversight responsibilities as the Central Accountability Office for the River Bend Station. As much as possible, these duties are carried out in an integrated, interdependent manner. From these primary functions devolve Nuclear Fuels interfacing activities with fuel cost and tax accounting. Noting that nuclear fuel tax accounting support is of both an esoteric and intermittent nature, Nuclear Fuels-RBNG support of developments and applications associated with nuclear fuel cost accounting is stressed in this presentation

30 years in the Veracruz state coast landscape: Laguna Verde nuclear power station. 1. ed.; 30 anos de paisaje costero veracruzano: Central Nucleoelectrica Laguan Verde

Energy Technology Data Exchange (ETDEWEB)

Guevara, S; Moreno Casasola, P; Castillo Campos, G; Dorantes, C; Gonzalez Garcia, F; Halffter, G; Isunza, E; Lot H, A; Mendoza, R; Paradowska, K; Priego, A; Sanchez Vigil, C; Vazquez, G [Comision Federal de Electricidad and Instituto Nacional de Ecologia A.C. (Mexico)

2008-07-01

results of the environmental measurements also demonstrate that the nuclear option of electrical energy generation, when it is operated with safety and efficiency, is one of the friendlier forms with the environment of power generation. [Spanish] Hace 36 anos nacio uno de los proyectos energeticos mas importantes de Mexico; el diseno y construccion de la Central Nuclear Laguna Verde. Este proyecto se volvio realidad gracias al compromiso de un grupo de profesionistas mexicanos que dieron lo mejor de ellos para su realizacion. En Mexico no existia en ese momento una legislacion que contemplara la proteccion del medio ambiente; sin embargo, la Constitucion preve que cuando en el pais no exista legislacion para el desarrollo de un proyecto. Este debe adoptar la legislacion del pais que lo esta vendiendo. En el caso especifico de Laguna Verde, se adopto la legislacion de los Estados Unidos de America y en la parte ambiental se tuvo que realizar el primer Manifiesto de Impacto Ambiental, que se titulo Informe ambiental para la construccion de la Central Nuclear Laguna Verde en el Estado de Veracruz. Este estudio lo realizaron varias instituciones tanto nacionales como extranjeras. Entre las mas sobresalientes se cuenta con: la Universidad Nacional autonoma de Mexico, el Instituto Politecnico Nacional, la Universidad Veracruzana, el Instituto Nacional para la Investigacion de los Recursos Biologicos, el Instituto de Ecologia, A.C. Con este informe, los ingenieros se dieron a la tarea de disenar y construir, los biologos y ecologos a realizar los estudios para mitigar los efectos causados al medio ambiente durante la construccion y, posteriormente, durante la operacion de la Central Nuclear. Despues de 18 anos de operacion comercial de la central se concluye el presente libro, en el cual se comparan los resultados obtenidos en 1972, cuando se iniciaron los estudios para el informe ambiental, contra los obtenidos a lo largo de este periodo. Es importante ver en los resultados de

Progress of laser nuclear fusion research

International Nuclear Information System (INIS)

Shiraga, Hiroyuki

2017-01-01

This paper describes the principle and features of nuclear fusion using laser, as well as its basic concepts such as high-temperature / high-density implosion system and fast ignition of fuel. At present, researches aiming at nuclear fusion ignition have been developing. As the current state of researches, this paper reviews the situations of FIREX (Fast Ignition Realization Experiment) project of Japan focusing on direct irradiation implosion and fast ignition system, as well as NIF (National Ignition Facility) project of the U.S. aiming at ignition combustion based on indirect irradiation implosion and central ignition system. In collaboration with the National Institute for Fusion Science, Osaka University started FIREX-1 project in 2003. It built a heating laser LFEX of 10 kJ/1 to 10ps, and started an implosion/heating integration experiment in 2009. Currently, it is developing experiment to achieve heating to 5 keV. At NIF, the self-heating of central sparks via energy of α particles generated in the nuclear fusion reaction has been realized. This paper also overviews R and D issues surrounding the lasers for reactors for use in laser nuclear fusion power generators. (A.O.)

Atucha II: building a 745 MWe pressure-vessel PHWR in the Argentine

International Nuclear Information System (INIS)

Leibovich, H.; Coll, J.; Backhaus, K.

1982-01-01

The history of the Comision Nacional de Energia Atomica and its involvement with the development in Argentina of a nuclear power plant manufacturing technology is described. The way in which technology transfer from German industry has enabled increasing Argentine participation is outlined. The formation of the joint Argentine/German engineering company ENACE in 1981 will promote this process. (U.K.)

Nuclear Law Bulletin: Index + supplement no.56

International Nuclear Information System (INIS)

Anon.

1995-01-01

This book deals with the status of legislation governing the peaceful uses of nuclear energy in Central and Eastern European Countries. Readers are informed about regulatory and institutional developments in these countries. The Supplement to this Bulletin reproduces the Ukraine fundamental nuclear law of the 8 february 1995 on the use of nuclear energy and radiation safety. It shall establish the priority of human and environmental safety and the rights and responsibilities of citizens with regard to the use of nuclear energy, it shall regulate activities connected with the use of nuclear installations and ionizing radiation sources, and, as well, establish the legal basis for Ukraine's international commitments with respect to the use of nuclear energy. (authors). 71 refs

Toward fostering the scientific and technological literacy establishment of the 'Central Scientific and Technological Museum-Institute' and nuclear development

International Nuclear Information System (INIS)

Murata, Takashi

1999-01-01

The public in general does not necessarily have enough knowledge for the reasonable decision making in the application of scientific and technological development even in the ear of the Information Society. However strongly the necessity of the consensus in the scientific policy like nuclear R and D is required, it is impossible to attain the goal, unless the scientific literacy of the general public is. In order to improve it the role of the scientific museum as a social educational facility is very important. In this respect, there still remains vast room to improve in the Japanese museum system and its activities. The concept of the 'Central Scientific and Technological Museum-Institute', which also operates very small-sized reactor for the educational use, is developed in this paper. (author)

Nuclear electric power and the proliferation of nuclear weapon states

International Nuclear Information System (INIS)

Walske, C.

1977-01-01

Control and elimination of the strategic nuclear weapons held by the nuclear weapon states remains the central problem in the arms control and disarmament field. Whether the proliferation of nations with nuclear weapons can be stopped is dubious. A sovereign nation will launch a nuclear weapons program if it has the motivation and resource. Motivation depends on military and political considerations. The necessary resources are economic and technological. Conditions in some sovereign states explain this issue. A survey of commercial nuclear power programs outside the USA lists 45 countries using or planning to use nuclear reactors for power generation. There are currently 112 reactors now operating outside the United States, 117 more under construction, 60 on order, and 180 planned. The U. S. as of December 1976 has 64 operating reactors, 72 under construction, 84 on order, and 8 planned. Nuclear trade and export policies are discussed. In this article, Mr. Walske says that American industry is convinced that the need for nuclear energy abroad is more urgent than in the United States; that in the long run, the breeder reactor must be developed to enable the supply of nuclear fuel to last for centuries; and that the experience of American industry abroad has convinced it that emphasis on restrictive, denial type policies will almost certainly fail--a collapse of what has been gained through the test ban treaty and the nonproliferation treaty

Environmental radiation monitoring system in nuclear power station

International Nuclear Information System (INIS)

Matsuoka, Sadazumi; Tadachi, Katsuo; Endo, Mamoru; Yuya, Hiroshi

1983-01-01

At the time of the construction of nuclear power stations, prior to their start of operation, the state of environmental radiation must be grasped. After the start of the power stations, based on those data, the system of environmental radiation monitoring is established. Along with the construction of Kashiwazaki-Kariwa Nuclear Power Station, The Tokyo Electric Power Co., Inc. jointly with Fujitsu Ltd. has developed a high-reliability, environmental radiation monitoring system, and adopted ''optical data highways'' using optical fiber cables for communication. It consists of a central monitoring station and 11 telemeter observation points, for collecting both radiation and meteorological data. The data sent to the central station through the highways are then outputted on a monitoring panel. They are analyzed with a central processor, and the results are printed out. (Mori, K.)

Uranium to Electricity: The Chemistry of the Nuclear Fuel Cycle

Science.gov (United States)

Settle, Frank A.

2009-01-01

The nuclear fuel cycle consists of a series of industrial processes that produce fuel for the production of electricity in nuclear reactors, use the fuel to generate electricity, and subsequently manage the spent reactor fuel. While the physics and engineering of controlled fission are central to the generation of nuclear power, chemistry…

La sostenibilidad y el debate nuclear

Directory of Open Access Journals (Sweden)

Amparo Vilches

2008-01-01

Full Text Available Las centrales nucleares están siendo presentadas como “solución verde” al problema energético, debido a que no conllevan emisiones de CO2. En este artículo se pretende poner de manifiesto que, sin embargo, esta indudable ventaja va acompañada de muy serios inconvenientes que obligan a rechazar la opción nuclear.

French nuclear harvest: abundant energy or bitter fruit

International Nuclear Information System (INIS)

Bupp, I.C.

1980-01-01

In France, the nuclear-development program is a high-priority objective of a strong, centralized government. The administrators responsible for its success can draw on concentrated fiscal and technical resources and are free to take decisive action. A major pillar of the entire French nuclear-development effort is the expectation of significant long-term export markets on all fronts: for nuclear power plants, uranium enrichment, and fuel reprocessing

Nuclear Weapons Security Crisis: What Does History Teach?

Science.gov (United States)

2013-07-01

or tempo - rary storage.” It was uncertain if the Chinese would keep nuclear warheads stored at launch bases or in a central stockpile, then...activities. His account can be considered the most complete and credible of all available ones. Other accounts have small variations . See, for example...the National Journal article “Nuclear Negligence,” by Jeffrey Goldberg and Marc Ambinder, who reported that nuclear materials in Paki- stan were

Nuclear energy - overview of development trends

International Nuclear Information System (INIS)

1985-01-01

Proceeding from the organizational structure of the IAEA selected activities of the IAEA in connection with power reactor safety are dealt with. Based on the IAEA's computerized Power Reactor Information System (PRIS) a survey is presented of the most recent statistical data concerning status and trends of nuclear power plant development throughout the world. The central role of the IAEA in assisting Member States in the utilization of nuclear energy for peaceful purposes is underscored. Finally, a brief account of the state-of-the-art of the USSR's nuclear power programme is given

Movies about nuclear disasters

International Nuclear Information System (INIS)

Portelli, A.; Guarnieri, F.; Martin, C.

2014-01-01

'The China Syndrome' by J.Bridges is the most famous film about nuclear energy, it was released in 1979 and tells the story of a television reporter who discovers safety cover-ups in the Ventana nuclear power plant. In the film 'Mount Fuji in red' a part of 'Akira Kurosawa's dreams' film released in 1990, the eruption of the Mount Fuji triggered a series of accidents in Japanese nuclear plants which sent millions of people fleeing in terror and blocked by the ocean. More recent films are 'Land of Oblivion' by M.Boganim - 2012, 'The land of hope' by S.Sion - 2012 or 'Grand Central' by R. Zlotowski - 2013. All this list of films depicting nuclear disasters and their dramatic consequences on the daily life of people contribute to build a frightening picture of nuclear energy in the mind of people. Although any film is fictional it can influence people but also open people's eyes on society issues like sub-contracting, unemployment, risk assessment... (A.C.)

Integrative structure and functional anatomy of a nuclear pore complex

Science.gov (United States)

Kim, Seung Joong; Fernandez-Martinez, Javier; Nudelman, Ilona; Shi, Yi; Zhang, Wenzhu; Raveh, Barak; Herricks, Thurston; Slaughter, Brian D.; Hogan, Joanna A.; Upla, Paula; Chemmama, Ilan E.; Pellarin, Riccardo; Echeverria, Ignacia; Shivaraju, Manjunatha; Chaudhury, Azraa S.; Wang, Junjie; Williams, Rosemary; Unruh, Jay R.; Greenberg, Charles H.; Jacobs, Erica Y.; Yu, Zhiheng; de La Cruz, M. Jason; Mironska, Roxana; Stokes, David L.; Aitchison, John D.; Jarrold, Martin F.; Gerton, Jennifer L.; Ludtke, Steven J.; Akey, Christopher W.; Chait, Brian T.; Sali, Andrej; Rout, Michael P.

2018-03-01

Nuclear pore complexes play central roles as gatekeepers of RNA and protein transport between the cytoplasm and nucleoplasm. However, their large size and dynamic nature have impeded a full structural and functional elucidation. Here we determined the structure of the entire 552-protein nuclear pore complex of the yeast Saccharomyces cerevisiae at sub-nanometre precision by satisfying a wide range of data relating to the molecular arrangement of its constituents. The nuclear pore complex incorporates sturdy diagonal columns and connector cables attached to these columns, imbuing the structure with strength and flexibility. These cables also tie together all other elements of the nuclear pore complex, including membrane-interacting regions, outer rings and RNA-processing platforms. Inwardly directed anchors create a high density of transport factor-docking Phe-Gly repeats in the central channel, organized into distinct functional units. This integrative structure enables us to rationalize the architecture, transport mechanism and evolutionary origins of the nuclear pore complex.

Integrative structure and functional anatomy of a nuclear pore complex.

Science.gov (United States)

Kim, Seung Joong; Fernandez-Martinez, Javier; Nudelman, Ilona; Shi, Yi; Zhang, Wenzhu; Raveh, Barak; Herricks, Thurston; Slaughter, Brian D; Hogan, Joanna A; Upla, Paula; Chemmama, Ilan E; Pellarin, Riccardo; Echeverria, Ignacia; Shivaraju, Manjunatha; Chaudhury, Azraa S; Wang, Junjie; Williams, Rosemary; Unruh, Jay R; Greenberg, Charles H; Jacobs, Erica Y; Yu, Zhiheng; de la Cruz, M Jason; Mironska, Roxana; Stokes, David L; Aitchison, John D; Jarrold, Martin F; Gerton, Jennifer L; Ludtke, Steven J; Akey, Christopher W; Chait, Brian T; Sali, Andrej; Rout, Michael P

2018-03-22

Nuclear pore complexes play central roles as gatekeepers of RNA and protein transport between the cytoplasm and nucleoplasm. However, their large size and dynamic nature have impeded a full structural and functional elucidation. Here we determined the structure of the entire 552-protein nuclear pore complex of the yeast Saccharomyces cerevisiae at sub-nanometre precision by satisfying a wide range of data relating to the molecular arrangement of its constituents. The nuclear pore complex incorporates sturdy diagonal columns and connector cables attached to these columns, imbuing the structure with strength and flexibility. These cables also tie together all other elements of the nuclear pore complex, including membrane-interacting regions, outer rings and RNA-processing platforms. Inwardly directed anchors create a high density of transport factor-docking Phe-Gly repeats in the central channel, organized into distinct functional units. This integrative structure enables us to rationalize the architecture, transport mechanism and evolutionary origins of the nuclear pore complex.

Safety related terms for advanced nuclear plants; Terminos relacionados con la seguridad para centrales nucleares avanzadas

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety.

International nuclear material safeguards

International Nuclear Information System (INIS)

Syed Azmi Syed Ali

1985-01-01

History can be a very dull subject if it relates to events which have long since lost their relevance. The factors which led to the creation of the International Atomic Energy Agency (IAEA), however, are as important and relevant today as they were when the Agency was first created. Without understanding these factors it is impossible to realise how important the Agency is in the present world or to understand some of the controversies surrounding its future. Central to these controversies is the question of how best to promote the international transfer of nuclear technology without contributing further to the problem of proliferating nuclear explosives or explosive capabilities. One effective means is to subject nuclear materials (see accompanying article in box), which forms the basic link between the manufacture of nuclear explosives and nuclear power generation, to international safeguards. This was realized very early in the development of nuclear power and was given greater emphasis following the deployment of the first two atomic bombs towards the end of World War II. (author)

Knowledge management in nuclear power plants; Gestion del conocimiento en las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Cal, C. de la; Barasoain, F.; Buedo, J. L.

2013-03-01

This article aims to show the importance of knowledge management from different perspectives. In this first part part of the article, the overall approach that performs CNAT of knowledge management is described. In the second part, a specific aspect of knowledge management in ANAV, tacit knowledge transfer is showed. finally, the third part discusses the strategies and actions that are followed in CNCO for knowledge management. All this aims to show an overview of knowledge management held in the Spanish Nuclear Power Plants. (Author)