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Sample records for reactor installation alteration

  1. Alteration of installation of reactors (alteration of No.1 and No.2 reactor facilities) in Oi Power Station, Kansai Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1984-01-01

    The Nuclear Safety Commission reported to the Minister of International Trade and Industry on October 27, 1983, that the technical capability was recognized to be adequate, and the safety after the alteration of the installation of reactors was judged to be ensured. At the time of deliberation, the guidelines for examining the safety design and safety evaluation of LWR facilities for power generation were used. Regarding the change of the degree of enrichment of replacement fuel from 3.2 to 3.4 wt.%, the limiting conditions are satisfied in the replacement core, and the nuclear design is appropriate. Eight test fuel assemblies using UO 2 pellets containing gadolinia are charged in the core of No.2 reactor, and the irradiation of two cycles is carried out. As the result of the safety examination regarding this test, the propriety of the nuclear design and mechanical design of the test fuel assemblies was confirmed. This alteration does not exert influence on the result of safety analysis made so far. This report was decided by the Committee on Examination of Reactor Safety based on the conclusion of No.26 subcommittee. (Kako, I.)

  2. Alteration of installation of nuclear reactors (alteration of No. 1 and No. 2 reactor facilities) in Shimane Nuclear Power Station, Chugoku Electric Power Co. , Inc. (report)

    Energy Technology Data Exchange (ETDEWEB)

    1987-07-01

    The Nuclear Safety Commission reported to the Minister of International Trade and Industry after prudent deliberation on this alteration problem which had been inquired on August 28, 1986. It was recognized that the technical capability of the applicant is appropriate, as the result of deliberation. It was judged that the safety after this alteration of the installation of the reactor facilities can be ensured. As the result of examining new type 8 x 8 zirconium liner fuel, there was no problem in its mechanical design, the analysis of dynamical characteristics, and the analysis of abnormal transient change and accident in operation. As to the change of the average degree of enrichment of replacement fuel, the thermonuclear design of the reactor core was adequate. In the incineration of spent resin and filter sludge, the effect of radioactive substances to the environment was negligible. The safety after abolishing the auxiliary protection function against exhaust radioactivity is ensured with a rare gas holdup equipment. The soundness of fuel and the soundness of reactor coolant pressure boundary are maintained in abnormal transient change and accident. (Kako, I.).

  3. Alteration of installation of nuclear reactors (alteration of No.1 and No.2 reactor facilities) in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. (report)

    International Nuclear Information System (INIS)

    1987-01-01

    The Nuclear Safety Commission reported to the Minister of International Trade and Industry after prudent deliberation on this alteration problem which had been inquired on August 28, 1986. It was recognized that the technical capability of the applicant is appropriate, as the result of deliberation. It was judged that the safety after this alteration of the installation of the reactor facilities can be ensured. As the result of examining new type 8 x 8 zirconium liner fuel, there was no problem in its mechanical design, the analysis of dynamical characteristics, and the analysis of abnormal transient change and accident in operation. As to the change of the average degree of enrichment of replacement fuel, the thermonuclear design of the reactor core was adequate. In the incineration of spent resin and filter sludge, the effect of radioactive substances to the environment was negligible. The safety after abolishing the auxiliary protection function against exhaust radioactivity is ensured with a rare gas holdup equipment. The soundness of fuel and the soundness of reactor coolant pressure boundary are maintained in abnormal transient change and accident. (Kako, I.)

  4. Nuclear reactor installation

    International Nuclear Information System (INIS)

    Keller, W.

    1976-01-01

    A nuclear reactor installation includes a pressurized-water coolant reactor vessel and a concrete biological shield surrounding this vessel. The shield forms a space between it and the vessel large enough to permit rapid escape of the pressurized-water coolant therefrom in the event the vessel ruptures. Struts extend radially between the vessel and shield for a distance permitting normal radial thermal movement of the vessel, while containing the vessel in the event it ruptures, the struts being interspaced from each other to permit rapid escape of the pressurized-water coolant from the space between the shield and the vessel

  5. On alteration of reactor installation (additional installation of No.3 and No.4 plants in the Genkai Nuclear Power Station, Kyushu Electric Power Co., Inc.)

    International Nuclear Information System (INIS)

    1985-01-01

    The Nuclear Safty Commission sent the reply to the Minister of International Trade and Industry on October 4, 1984, on this matter after having received the report from the Committee on Examination of Nuclear Reactor Safety and carried out the deliberation. It was judged that the applicant has the technical capability required for installing and operating these reactor facilities. Also it was judged that on the safety after these reactor plants are installed, there is no obstacle in the prevention of disaster due to contaminated substances and reactors. The policy of the investigation and deliberation is reported. The contents of the investigation and deliberation are the condition of location such as site, geological features and ground, earthquake, weather, hydraulic problem and social environments, the safety design of reactor facilities, the evaluation of radiation exposure dose in normal operation, the analysis of abnormal transient change in operation, accident analysis and the evaluation of location. (Kako, I.)

  6. Nuclear reactor installation

    International Nuclear Information System (INIS)

    Jungmann, A.

    1976-01-01

    A nuclear reactor metal pressure vessel is surrounded by a concrete wall forming an annular space around the vessel. Thermal insulation is in this space and surrounds the vessel, and a coolant-conductive layer is also in this space surrounding the thermal insulation, coolant forced through this layer reducing the thermal stress on the concrete wall. The coolant-conductive layer is formed by concrete blocks laid together and having coolant passages, these blocks being small enough individually to permit them to be cast from concrete at the reactor installation, the thermal insulation being formed by much larger sheet-metal clad concrete segments. Mortar is injected between the interfaces of the coolant-conductive layer and concrete wall and the interfaces between the fluid-conductive layer and the insulation, a layer of slippery sheet material being interposed between the insulation and the mortar. When the pressure vessel is thermally expanded by reactor operation, the annular space between it and the concrete wall is completely filled by these components so that zero-excursion rupture safeguard is provided for the vessel. 4 claims, 1 figure

  7. New fast reactor installation concept

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The large size and complexity of fast reactor installations are emphasised and these difficulties will be increased with the advent of fast reactors of higher power. In this connection a new concept of fast reactor installation is described with a view to reducing the size of the installation and enabling most components, including even the primary vessel, to be constructed within the confines of a workshop. Full constructional details are given. (U.K.)

  8. Alteration in reactor installations (Unit 1 and 2 reactor facilities) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Inc. (report)

    International Nuclear Information System (INIS)

    1982-01-01

    A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry concerning the alteration in Unit 1 and 2 reactor facilities in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was presented. The technical capabilities for the alteration of reactor facilities in Chubu Electric Power Co., Inc., were confirmed to be adequate. The safety of the reactor facilities after the alteration was confirmed to be adequate. The items of examination made for the confirmation of the safety are as follows: reactor core design (nuclear design, mechanical design, mixed reactor core), the analysis of abnormal transients in operation, the analysis of various accidents, the analysis of credible accidents for site evaluation. (Mori, K.)

  9. Alteration in reactor installation (addition of Unit 2) in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. (inquiry)

    International Nuclear Information System (INIS)

    1983-01-01

    An inquiry was made by the Ministry of International Trade and Industry to Nuclear Safety Commission on the addition of Unit 2 in Shimane Nuclear Power Station of The Chugoku Electric Power Co., Inc., concerning the technical capability of Chugoku Electric Power Co., Inc., and the plant safety. The NSC requested the Committee on Examination of Reactor Safety to make a deliberation on this subject. Both the technical capability and the safety of Unit 1 were already confirmed by MITI. Unit 2 to be newly added in the Shimane Nuclear Power Station is a BWR power plant with electric output of 820 MW. The examination made by MITI is described: the technical capability of Chugoku Electric Power Co., Inc., the safety of Unit 2 about its siting, reactor proper, reactor cooling system, radioactive waste management, etc. (J.P.N.)

  10. Safety concerning the alteration in fuel material usage (new installation of the uranium enrichment pilot plant) at Ningyo Pass Mine of Power Reactor and Nuclear Fuel Development Corporation

    International Nuclear Information System (INIS)

    1978-01-01

    A report of the Committee on Examination of Nuclear Fuel Safety was presented to the Atomic Energy Commission of Japan, which is concerned with the safety in the alteration of fuel material usage (new installation of the uranium enrichment pilot plant) at the Ningyo Pass Mine. Its safety was confirmed. The alteration, i.e. installation of the uranium enrichment pilot plant, is as follows. Intended for the overall test of centrifugal uranium enrichment technology, the pilot plant includes a two-storied main building of about 9,000 m 2 floor space, containing centrifuges, UF 6 equipment, etc., a uranium storage of about 1,000 m 2 floor space, and a waste water treatment facility, two-storied with about 300 m 2 floor space. The contents of the examination are safety of the facilities, criticality control, radiation control, waste treatment, and effects of accidents on the surrounding environment. (Mori, K

  11. A method of installing a reactor container

    International Nuclear Information System (INIS)

    Hayashi, Kenji; Murakawa, Hisao.

    1975-01-01

    Object: To achieve exact installation of a reactor container at a site. Structure: A pole is set upright at the center of a cylindrical base portion, a plurality of beams are disposed around the pole in a radial fashion to form a cone, a plurality of steel plates are mounted successively around the cone through a ring, and the steel plates are welded to each other to assemble and install a reactor container at the same time. (Kamimura, M.)

  12. Considerations of the opinions and others in the public hearing on the alteration in reactor installation (addition of Unit 3) in the Hamaoka Nuclear Power Station of the Chubu Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1982-01-01

    A public hearing was held in Hamaoka Town, Shizuoka Prefecture, on the alteration in reactor installation, i.e., the addition of Unit 3 in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., on March 19, 1981, by the Nuclear Safety Commission. The opinions and others stated by the local people were taken into consideration in the governmental examinations on the installation, etc. The considerations of such opinions principally in the examinations by NSC are explained in the form of questions (i.e. opinion, etc.) and answers (i.e. considerations) as follows: site conditions (earthquakes, ground, hydraulic features, etc.), the safety design of the reactor facilities (overall plant, aseismic design, the control of inflammable gas concentration, radioactive waste treatment, the reflection of accident experiences, etc.), radioactive waste management, radiation exposure relation, the technical capabilities of personnel (operation, etc.). (J.P.N.)

  13. Consideration of the opinions and others in the public hearing on the alteration in reactor installation (addition of Unit 2) in the Tsuruga Power Station of the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    1982-01-01

    A public hearing was held in Tsuruga City, Fukui Prefecture, on the alteration in reactor installation, i.e., the addition of Unit 2 in the Tsuruga Power Station, JAPC, on November 20, 1980, by the Nuclear Safety Commission. The opinions and others stated by the local people were taken into consideration in the governmental examinations on the installation, etc. The considerations of such opinions principally in the examinations by NSC are explained in the form of questions (i.e. opinion, etc.) and answers (i.e. consideration) as follows: site conditions (site, earthquakes, ground, meteorology, siting situation, etc.), the safety design of the reactor facilities (overall plant, aseismic design, the teaching by the TMI accident in U.S., ECCS, pre-stressed concrete containment vessel, radioactive waste release, etc.), radioactive waste management, radiation exposure relation, the technical capabilities of personnel (operation, etc.). (J.P.N.)

  14. Regulation for installation and operation of reactor

    International Nuclear Information System (INIS)

    1977-01-01

    Concerning the description of an application for the approval of installation of a reactor, stipulated in Article 23 paragraph 2 of the Law for Regulation of Nuclear Source Materials, Nuclear Fuel Materials and Reactors (hereinafter referred to as the Law), the following items must be written. Namely, the heat output of the reactor in Article 23 paragraph 2 item 3 of the Law, the position, structure and facilities of the reactor facilities, described according to the stipulated classifications, the work plan, nuclear fuel materials employed, and the disposal of spent fuel. Concerning an application for the approval of a reactor installed aboard a foreign ship, stipulations are made separately. Description of an application for the approval of change of the heat output of a reactor and others should include the stipulated items. When it is wished to undergo inspection of the construction and performance of reactor facilities, an application for that end including the required items should be filed. Various safety measures preventing personnel from being exposed to radiation should be taken. When a foreign atomic-powered ship tries to enter a Japanese port, the stipulated necessary informations should be reported 60 days before such ship actually enters the Japanese port. A chief technician of reactors should take and pass the official examination. (Rikitake, Y.)

  15. Selection of persons expressing opinions etc. and attendants in the public hearing concerning the alteration in reactor installations (addition of Unit 3 and 4) in the Genkai Nuclear Power Station of Kyushu Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1984-01-01

    The Nuclear Safety Commission has selected 18 persons expressing opinions etc. and 255 (other) attendants for the public hearing on the alteration of reactor installations (addition of Unit 3 and 4) in Kyushu Electric's Genkai Nuclear Power Station to be held on June 18th, 1984. The order of expressing opinions etc., number of reception, names, addresses, ages and occupations are given of the persons expressing opinions etc. For both the groups, against the selected numbers there are given applicants etc. in number by towns and city. (Mori, K.)

  16. Safety in connection with the request for approval of the installation alteration in the fuel reprocessing facilities of Power Reactor and Nuclear Fuel Development Corporation (report)

    International Nuclear Information System (INIS)

    1982-01-01

    A report to the Prime Minister by the Nuclear Safety Commission was presented concerning the safety in the installation alteration of the fuel reprocessing facilities, as PNC had requested its approval to the Prime Minister. The safety was confirmed. The items of examination on the safety made by the committee on Examination of Nuclear Fuel Safety of NSC were the aseismic design of liquid waste storage, uranium denitration facility, intermediate gate and radioactive solid waste storage; the criticality safety design of the denitration facility; the radiation shielding design of the liquid waste storage, denitration facility and solid waste storage; the function of radioactive material containment of the liquid waste storage and denitration facility; the radiation control in the liquid waste storage, denitration facility and solid waste storage; the waste management in the liquid waste storage and denitration facility; fire and explosion prevention in the liquid waste storage; exposure dose from the liquid waste storage and denitration facility. (Mori, K.)

  17. Regulation for installation and operation of marine reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The regulation is defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and the provisions of the order for execution of the law. The regulation is applied to marine reactors and reactors installed in foreign nuclear ships. Basic concepts and terms are explained, such as: radioactive waste; fuel assembly; exposure dose; accumulative dose; controlled area; safeguarded area; inspected surrounding area and employee. The application for permission of installation of reactors shall list maximum continuous thermal power, location and general structure of reactor facilities, structure and equipment of reactors and treatment and storage facilities of nuclear fuel materials, etc. The application for permission of reactors installed in foreign ships shall describe specified matters according to the provisions for domestic reactors. The operation program of reactors for three years shall be filed to the Minister of Transportation for each reactor every fiscal year from that year when the operation is expected to start. Records shall be made for each reactor and kept for particular periods on inspection of reactor facilities, operation, fuel assembly, control of radiation, maintenance and others. Exposure doses, inspection and check up of reactor facilities, operation of reactors, transport and storage of nuclear fuel materials, etc. are designated in detail. (Okada, K.)

  18. Regulations of local choices for installation of power reactors

    International Nuclear Information System (INIS)

    1969-09-01

    The present regulations specify the criteria under which the Comissao Nacional de Energia Nuclear will approve the local proposed for the installation of power reactors, according to his attributions established in the Law 4118, dated of August 27, 1962

  19. Handling of views and opinions by staters and others in a public hearing on alteration in reactor installation (addition of Unit 2) in the Sendai Nuclear Power Station of Kyushu Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1981-01-01

    A public hearing on the addition of Unit 2 in the Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc., was held on July 17, 1980, in Sendai City, Kagoshima Prefecture. The views and opinions by the local staters and those by the notification of statement were expressed concerning its nuclear safety. The handling of these views and opinions by the Nuclear Safety Commission is explained. The most important in this action is the instruction by the NSC to the Committee on Examination of Reactor Safety to reflect the results of the public hearing to the reactor safety examination of the Unit 2 installation by the CERS. The views and opinions expressed in this connection are summarized as follows: the sitting conditions, the safety design of the reactor plant, and the release of radioactive materials, involving such aspects as earthquakes, accidents and radioactive waste management. (J.P.N.)

  20. Regulation for installation and operation of experimental-research reactor

    International Nuclear Information System (INIS)

    1979-01-01

    The ordinance is stipulated under the Law for regulation of nuclear raw materials, nuclear fuel materials and reactors and the provisions for installation and operation of reactor in the order for execution of the law. Basic concepts and terms are defined, such as, radioactive waste; fuel assembly; exposure dose; accumulative dose; controlled area; preserved area; inspected surrounding area and employee. An application for permission of installation of reactor shall list such matters as: the maximum continuous thermal output of reactor; location and general construction of reactor facilities; construction and equipment of the main reactor and other facilities for nuclear fuel materials; cooling and controlling system and radioactive waste, etc. An operation plan of reactor for three years shall be filed till January 31 of the fiscal year preceding that one the operation begins. Records shall be made and kept for specified periods respectively on inspection of reactor facilities, operation, fuel assembly, radiation control, maintenance, accidents of reactor equipment and weather. Detailed rules are settled for entrance limitation to controlled area, exposure dose, inspection, check up and regular independent examination of reactor facilities, operation of reactor, transportation of substances contaminated by nuclear fuel materials within the works and storage, etc. (Okada, K.)

  1. Treatment of opinions, etc. in the public hearing on the alteration of reactor installation (addition of Unit 2) in the Shimane Nuclear Power Station of The Chugoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1983-01-01

    The Nuclear Safety Commission has acknowledged the governmental policy, and further decided on the treatment of the opinions expressed by the local people in the public hearing held in May, 1983, in Shimane Prefecture on the addition of Unit 2 to the Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. The NSC has directed the Committee on Examination of Reactor Safety to take into consideration the opinions in its later examination. The opinions expressed by the local people in the form of question are given as follows: siting conditions (earthquake, ground, weather, etc.), the safety design for reactor installation (general aspect, aseismatic design, core design, ECCS, the teaching of TMI accident, etc.), radioactive wastes, radiation exposure, site evaluation. (Mori, K.)

  2. Treatment and management of opinions stated in and notified to the public hearing on the alteration in reactor installation (addition of Unit 3) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Ltd

    International Nuclear Information System (INIS)

    1981-01-01

    A public hearing was made in Hamaoka Town, Shizuoka Prefecture, on March 19, 1981, on the addition of Unit 3 in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc. Treatment and management of the opinions and others stated and notified by the local people, which are understood and to be carried out by the Nuclear Safety Commission, are: to publish them as the report of the public hearing, to include them in the safety examination report of NSC and to refer to them in the examination by the Committee on Examination of Reactor Safety, etc. The opinions and others stated and notified in the public hearing, to which CERS should refer in its examination, are summarized in the form of the questions on siting conditions, safety design of reactor installation, release of radioactivities, etc. (J.P.N.)

  3. Licensing of away-from-reactor (AFR) installations

    International Nuclear Information System (INIS)

    Gray, P.L.

    1980-01-01

    Storage of spent fuel at Away-From-Reactor (AFR) installations will allow reactors to continue to operate until reprocessing or other fuel disposal means are available. AFR installations must be licensed by the Nuclear Regulatory Commission (NRC). Although wide experience in licensing reactors exists, the licensing of an AFR installation is a relatively new activity. Only one has been licensed to date. This paper delineates the requirements for licensing an AFR installation and projects a licensing schedule. Because the NRC is developing specific AFR requirements, this schedule is based primarily on draft NRC documents. The major documents needed for an AFR license application are similar to those for a reactor. They include: a Safety Analysis Report (SAR), and Environmental Report (ER), safeguards and security plans, decommissioning plans, proposed technical specifications, and others. However, the licensing effort has one major difference in that for AFR installations it will be a one-step effort, with follow-up, rather than the two-step process used for reactors. The projected licensing schedule shows that the elapsed time between filing an application and issuance of a license will be about 32 months, assuming intervention. The legal procedural steps will determine the time schedule and will override considerations of technical complexity. A license could be issued in about 14 months in the absence of intervention

  4. ORPHEE reactor. Upgrade of the installation

    International Nuclear Information System (INIS)

    Farnoux, B.; Maziere, M.

    1995-01-01

    Designed by the end of the seventies, the ORPHEE Reactor is equipped with two hydrogen cold sources, one hot source and six cold neutron guides. The neutron beams are extracted by nine beam ports and used in two experimental halls, the reactor hall and the neutron guide hall. After fourteen years of use, a modernisation programme is in progress. One step concerns the neutron guides, another one the cold sources with the modification of the cell geometry in order to increase the cold neutron flux. This operation requires the use a new cryogenerator to ensure liquefaction capabilities for the new cells. It is also scheduled to replace the Zircaloy core housing in order to avoid difficulties linked to the expansion under irradiation. (author)

  5. The installation welding of pressure water reactor coolant piping

    International Nuclear Information System (INIS)

    Deng Feng

    2010-01-01

    Large pressure water reactor nuclear power plants are constructing in our country. There are three symmetry standard loops in reactor coolant system. Each loop possesses a steam generator and a primary poop, in which one of the loops is equipped with a pressurizer. These components are connected with reactor pressure vessel by installation welding of the coolant piping. The integrity of reactor coolant pressure boundary is the second barrier to protect the radioactive substance from release to outside, so the safe operation of nuclear power plant is closely related to the quality of coolant piping installation welding. The heavy tube with super low carbon content austenitic stainless steel is selected for coolant piping. This kind of material has good welding behavior, but the poor thermal conductivity, the big liner expansion coefficient and the big welding deformation will cause bigger welding stress. To reduce the welding deformation, to control the dimension precision, to reduce the residual stress and to ensure the welding quality the installation sequence should be properly designed and the welding technology should be properly controlled. (authors)

  6. Installation technology of reactor internals on shroud replacement work

    International Nuclear Information System (INIS)

    Miyano, Hiroshi

    1999-01-01

    Since the replacement of large welded reactor internals much as a core shroud did not have a precedent in the world, quite a few technologies had to be developed. Especially for the installation of new core shroud, jet pumps, core plate and top guide, the accurate weld and fit-up techniques for large structures was required to secure their integrity. The vessel shielding system was utilized to reduce general area dose rate such that all replacement work. For jet pump installation, automatic remote welding machines were used for high radiation area. As for the core shroud, shroud support weld prep machining tool with high accuracy, jacking system to support fit-up, new weld machine for small work space and low heat input weld joint were developed. Shroud replacement work in Fukushima Dai-ichi NPS Unit 3 (1F-3) with application of these development techniques, was successfully accomplished. The technology is applied for 1F-2 replacement work also. (author)

  7. International guidelines for fire protection at nuclear installations including nuclear fuel plants, nuclear fuel stores, teaching reactors, research establishments

    International Nuclear Information System (INIS)

    The guidelines are recommended to designers, constructors, operators and insurers of nuclear fuel plants and other facilities using significant quantities of radioactive materials including research and teaching reactor installations where the reactors generally operate at less than approximately 10 MW(th). Recommendations for elementary precautions against fire risk at nuclear installations are followed by appendices on more specific topics. These cover: fire protection management and organization; precautions against loss during construction alterations and maintenance; basic fire protection for nuclear fuel plants; storage and nuclear fuel; and basic fire protection for research and training establishments. There are numerous illustrations of facilities referred to in the text. (U.K.)

  8. RA reactor building and installations; Zgrada 'RA' i instalacije

    Energy Technology Data Exchange (ETDEWEB)

    Badrljica, R; Sanovic, V; Skoric, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1985-08-15

    RA reactor building is made of reinforced concrete and bricks. It is closed facility with a limited number of controlled openings, doors and windows. The site of the building is 100 m above the sea level, 20 m above the mean Danube level and 8 m above the level of the neighbouring stream Mlaka. The building consists of three parts: central prismatic part, annex - surrounding the central part and the sanitary corridor. The biggest space is the reactor hall. In addition to the detailed description and drawings of the reactor building this documents includes design specifications of: electrical installation, water supply system, sewage system, ventilation and heating, gas and compressed air systems. A separate chapter is devoted to fire protection. Zgrada reaktora RA izgradjena je od armiranog betona i opeke, kao zatvoreni objekat ogranicenog broja kontolisanih otvora, sa ogranicenim brojem vrata i prozora. Plato na kojem je zgrada izgradjena nalazi se na 100 m nadmorske visine, na 20 m iznad srednjeg vodostaja Dunava i 8 m iznad nivoa obliznjeg potoka Mlaka. Zgrada se sastoji iz tri dela: sredisnjeg prizmaticnog dela, aneksa - prstenastog okvira sredisnog dela i sanitarnog propusnika. Pojedinacno najveci prostor zauzima reaktorska hala. Pored detaljnog opisa i plana zgrade, ovaj dokument sadrzi projekat elektricne instalacije, projekat vodovoda i kanalizacije, ventilacije i grejanja, instalacije gasa i komprimovanog vazduha. Posebno poglavlje posveceno je protivpozarnoj zastiti.

  9. Manufacture and installation of reactor auxiliary facilities for advanced thermal prototype reactor 'Fugen'

    International Nuclear Information System (INIS)

    Kawahara, Toshio; Matsushita, Tadashi

    1977-01-01

    The facilities of reactor auxiliary systems for the advanced thermal prtotype reactor ''Fugen'' were manufactured in factories since 1972, and the installation at the site began in November, 1974. It was almost completed in March, 1977, except a part of the tests and inspections, therefore the outline of the works is reported. The ATR ''Fugen'' is a heavy water-moderated, boiling light water reactor, and its reactor auxiliary systems comprise mainly the facilities for handling heavy water, such as heavy water cooling system, heavy water cleaning system, poison supplying system, helium circulating system, helium cleaning system, and carbon dioxide system. The poison supplying system supplies liquid poison to the heavy water cooling system to absorb excess reactivity in the initial reactor core. The helium circulating system covers heavy water surface with helium to prevent the deterioration of heavy water and maintains heavy water level by pressure difference. The carbon dioxide system flows highly pure CO 2 gas in the space of pressure tubes and carandria tubes, and provides thermal shielding. The design, manufacture and installation of the facilities of reactor auxiliary systems, and the helium leak test, synthetic pressure test and total cleaning are explained. (Kako, I.)

  10. Reactor installation and maintenance for the Advanced Neutron Source

    International Nuclear Information System (INIS)

    Smith, B.R.

    1993-01-01

    Advanced Neutron Source (ANS) reactor assembly components have been modeled in great detail in IGRIP in order to realistically simulate preliminary installation and maintenance processes. Animation of these processes has been captured in a 15-minute video with narration. Approximately 90% of the parts were initially translated from CADAM (a two-dimensional drawing package) to IGRIP and then revolved or extruded. IGRIP's IGES translator greatly reduced the time required to perform this operation. The interfacing of devices in the work cell has identified numerous design inconsistencies. Most of the modeled reactor components are devices with a single degree of freedom (DOF) however, some of the slanted experiments required 6 DOF so that they could be removed at an angle in order to clear the reflector vessel flanges. IGRIP's collision detection feature proved to be extremely helpful in determining interferences when removing the experiments. The combination of three-dimensional visualization and collision detection allows engineers to clearly and easily visualize potential design problems before the construction phase of the project

  11. Installation of a new type of nuclear reactor in Mexico: advantages and disadvantages

    International Nuclear Information System (INIS)

    Jurado P, M.; Martin del Campo M, C.

    2005-01-01

    In this work the main advantages and disadvantages of the installation of a new type of nuclear reactor different to the BWR type reactor in Mexico are presented. A revision of the advanced reactors is made that are at the moment in operation and of the advanced reactors that are in construction or one has already planned its construction in the short term. Specifically the A BWR and EPR reactors are analyzed. (Author)

  12. Dimensional control and check of field machining parts for reactor internals installation

    International Nuclear Information System (INIS)

    Zhang Caifang

    2010-01-01

    Some key issues of dimensional control for reactor internals installation are analyzed, and important technical requirements of crucial quality control elements on the measurement, machining, and checking of reactor internals filed machining parts are discussed. Moreover, provisions on quality control and risk prevention of reactor internals filed machining parts are presented in this paper. (author)

  13. Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations

    International Nuclear Information System (INIS)

    Lacour, J.

    1964-01-01

    In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [fr

  14. Installation of the Light-Water Breeder Reactor at the Shippingport Atomic Power Station (LWBR Development Program)

    International Nuclear Information System (INIS)

    Massimino, R.J.; Williams, D.A.

    1983-05-01

    This report summarizes the refueling operations performed to install a Light Water Breeder Reactor (LWBR) core into the existing pressurized water reactor vessel at the Shippingport Atomic Power Station. Detailed descriptions of the major installation operations (e.g., primary system preconditioning, fuel installation, pressure boundary seal welding) are included as appendices to this report; these operations are of technical interest to any reactor servicing operation, whether the reactor is a breeder or a conventional light water non-breeder core

  15. Installation of the Light-Water Breeder Reactor at the Shippingport Atomic Power Station (LWBR Development Program)

    Energy Technology Data Exchange (ETDEWEB)

    Massimino, R.J.; Williams, D.A.

    1983-05-01

    This report summarizes the refueling operations performed to install a Light Water Breeder Reactor (LWBR) core into the existing pressurized water reactor vessel at the Shippingport Atomic Power Station. Detailed descriptions of the major installation operations (e.g., primary system preconditioning, fuel installation, pressure boundary seal welding) are included as appendices to this report; these operations are of technical interest to any reactor servicing operation, whether the reactor is a breeder or a conventional light water non-breeder core.

  16. Regulation concerning installation and operation of reactors for power generation

    International Nuclear Information System (INIS)

    1987-01-01

    This report shows the Ordinance of the Ministry of International Trade and Industry No.77 of December 28, 1978. The ordinance consists of provisions covering application for permission for construction of nuclear reactor (concerning continuous maximum thermal output, location, structure, reactor core, fuel material, moderator, reflector, cooling system, measurement control system, safety circuit, control system, emergency system, radioactive waste proposal facilities, construction plan, meteorology and other environmental conditions, etc.), operation plan (to be submitted every year), application for approval of joint management (name, address, facilities location, conditions for joint management, etc.), cancellation of permission (in five years from the date of permission), record keeping (density and temperature of neutron, temperature and pressure of coolant, purity of mederator, etc.), restriction on access to areas under management (measures to be taken in such areas), measures concerning exposure to radioactive rays (allowable dosage, etc.), patrol and checking in nuclear reactor facilities, self-imposed regular inspection of nuclear reactor facilities, operation of nuclear reactor, transport within plant or business establishment, storage (storing facilities, etc.), waste disposal, etc. (Nogami, K.)

  17. RESEARCH CONCERNING INSTALATION OF ALTERATIVE PROCESSES IN COW AND BUFFALO BUTTER DURING FREEZING STORAGE

    OpenAIRE

    Andreea Lup Dragomir; Flavia Pop

    2009-01-01

    Physicochemical characteristics and freshness indicators of cow and buffalo butter during freezing (-15 ... -18oC) storage were studied. Changes in freshness parameters and alterative processes installation, when butter becomes improperly for consumption were studied, inducing acidity, peroxide value (PV), iodine value (IV) andthe presence of epyhidrinic aldehyde. There was an increase of titrable acidity during storage, cow butter hydrolysis was installed after 35 days and after 30 days for ...

  18. Safety challenges after the Fukushima accident for operated installations others than EDF reactors

    International Nuclear Information System (INIS)

    Sene, Monique; Rollinger, Francois; Lheureux, Yves; Lizot, Marie-Therese; Kerdelhue, M.; Py, M.E.; Leroyer, Veronique; Pultier, Marc; Kassiotis, Christophe; Chambrette, Pierre; Devaux, Pascal; Baron, Yves; Collinet, Jacques

    2013-12-01

    This document contains Power Point presentations which, within the perspective created by the Fukushima accident, address various aspects of safety issues for installations other than currently operated EDF reactors. These contributions propose: an agenda of additional safety assessments (ECS) performed on these installations and an examination of responses made to prescriptions made on the 16 June 2012; a presentation by the IRSN of ECS performed in Areva plants; a presentation by Areva of arrangements related to these ECS; a presentation of the Manche local information commissions (CLI) and a presentation of their approach according to a white paper for the safety of civil nuclear installations located in the Manche department; a presentation by the IRSN on ECS concerning various basic nuclear installations such as laboratories, experimental reactors and stopped reactors; a presentation by the CEA of ECS of its installations (context, approach, execution and conclusions); a presentation by the ANCCLI about ASN decision and decision projects about the hard core according to ECS (example of the High flux reactor in the ILL in Grenoble)

  19. Installation of remote-handling typed EBSD-OIM analyzer for heavy irradiated reactor materials

    International Nuclear Information System (INIS)

    Kato, Yoshiaki; Takada, Fumiki; Ohmi, Masao; Nakagawa, Tetsuya; Miwa, Yukio

    2008-06-01

    The remote-handling typed EBSD-OIM analyzer for heavy irradiated reactor materials was installed in the JMTR hot laboratory at the first time in the world. The analyzer is used to study on IASCC (irradiation assisted stress corrosion cracking) or IGSCC (inter granular stress corrosion cracking) in reactor materials. This report describes the measurement procedure, the measured results and the operating experiences on the analyzer in the JMTR hot laboratory. (author)

  20. Safety management at nuclear installations with research reactors. A comparison of five European installations

    International Nuclear Information System (INIS)

    Troen, H.; Lauridsen, B.

    1997-11-01

    Five European institutions with nuclear research reactors were visited to compare safety management among institutions similar to Risoe. Risoe is a National Laboratory and the main activities are research and development. In 1996 it was decided to look into safety management at Risoe again; the last revision was in 1972. The purpose was to make it more efficient and to emphasise, that the responsibility lies in the operating organisation. Information such as nuclear facilities at the institutions, the safety management organisation, emergency preparedness, and lists of radiation doses to the employees from the years 1995 and 1996 is given in the report. Also international requirements and recommendations are given in short. Furthermore the report contains some reflections on the development in safety management organisations in resent years and the conclusions drawn from the information gathered

  1. Change of nuclear reactor installation in the first nuclear ship of Japan Nuclear Ship Development Agency

    International Nuclear Information System (INIS)

    1979-01-01

    The written application concerning the change of nuclear reactor installation in the first nuclear ship was presented from the JNSDA to the prime minister on January 10, 1979. The contents of the change are the repair of the primary and secondary shields of the reactor, the additional installation of a storage tank for liquid wastes, and the extension of the period to stop the reactor in cold state. The inquiry from the prime minister to the Nuclear Safety Commission was made on June 9, 1979, through the examination of safety in the Nuclear Safety Bureau, Science and Technology Agency. The Nuclear Safety Commission instructed to the Committee for the Examination of Nuclear Reactor Safety on June 11, 1979, about the application of criteria stipulated in the law. The relevant letters and the drafts of examination papers concerning the technical capability and the safety in case of the change of nuclear reactor installation in the first nuclear ship are cited. The JNSDA and Sasebo Heavy Industries, Ltd. seem to have the sufficient technical capability to carry out this change. As the result of examination, it is recognized that the application presented by the JNSDA is in compliance with the criteria stipulated in the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors. (Kako, I.)

  2. Decontamination of Belarus research reactor installation by strippable coatings

    International Nuclear Information System (INIS)

    Voronik, N.I.; Shatilo, N.N.

    2002-01-01

    The goal of this study was to develop new strippable coatings using water-based solutions of polyvinyl alcohol and active additives for decontamination of research reactor equipment. The employment of strippable coatings makes it possible to minimize the quantity of liquid radioactive waste. The selection of strippable decontaminating coatings was carried out on the basis of general requirements to decontaminating solutions: successfully dissolve corrosion deposits; ensure the desorption of radionuclides from the surfaces and the absence of resorption; introduce minimal corrosion effect of construction materials; to be relatively cheap and available in reagents. The decontaminating ability and adhesion properties of these coatings depending on metal and deposit sorts were investigated. Research on the chemical stability of solid wastes was carried out. The data obtained were the base for recommendations on waste management procedure for used films and pastes. A full-scale case-study analysis was performed for comparing strippable coatings with decontaminating solutions. (author)

  3. Installation method for the steel container and vessel of the nuclear heating reactor

    International Nuclear Information System (INIS)

    Chen Liying; Guo Jilin; Liu Wei

    2000-01-01

    The Nuclear Heating Reactor (NHR) has the advantages of inherent safety and better economics, integrated arrangement, full power natural circulation and dual vessel structure. However, the large thin container presents a new and difficult problem. The characteristics of the dual vessel installation method are analyzed with system engineering theory. Since there is no foreign or domestic experience, a new method was developed for the dual vessel installation for the 5 MW NHR. The result shows that the installation method is safe and reliable. The research on the dual vessel installation method has important significance for the design, manufacture and installation of the NHR dual vessel, as well as the industrialization and standardization of the NHR

  4. Wiring installation for electric devices above the roof slab of a nuclear reactor

    International Nuclear Information System (INIS)

    Jahnke, S.

    1986-01-01

    The wiring installation is situated inside the nuclear reactor building. It includes, associated to electric devices, a first cable which extends from the device to a fixed connector arranged above the cover. A second cable is connected to the said fixed connector and to a connector fixed on a plate situated out of the reactor. According to the present invention each second cable has several sections. A first section can be connected to the said fixed connector situated above the cover and to a fixed lead-in connector of a fluid-tight conduit above the reactor core. A second section is inside the conduit. A third section can be connected to a lead-out connector fixed on the plate which is out of the reactor. The invention applies more particularly to pressurized water nuclear reactors [fr

  5. Installation of a new type of nuclear reactor in Mexico: advantages and disadvantages; Instalacion de un nuevo tipo de reactor nuclear en Mexico: ventajas y desventajas

    Energy Technology Data Exchange (ETDEWEB)

    Jurado P, M.; Martin del Campo M, C. [FI-UNAM, 04510 Mexico D.F. (Mexico)]. e-mail: mjp_green@hotmail.com

    2005-07-01

    In this work the main advantages and disadvantages of the installation of a new type of nuclear reactor different to the BWR type reactor in Mexico are presented. A revision of the advanced reactors is made that are at the moment in operation and of the advanced reactors that are in construction or one has already planned its construction in the short term. Specifically the A BWR and EPR reactors are analyzed. (Author)

  6. Concept of an accelerator-driven subcritical research reactor within the TESLA accelerator installation

    International Nuclear Information System (INIS)

    Pesic, Milan; Neskovic, Nebojsa

    2006-01-01

    Study of a small accelerator-driven subcritical research reactor in the Vinca Institute of Nuclear Sciences was initiated in 1999. The idea was to extract a beam of medium-energy protons or deuterons from the TESLA accelerator installation, and to transport and inject it into the reactor. The reactor core was to be composed of the highly enriched uranium fuel elements. The reactor was designated as ADSRR-H. Since the use of this type of fuel elements was not recommended any more, the study of a small accelerator-driven subcritical research reactor employing the low-enriched uranium fuel elements began in 2004. The reactor was designated as ADSRR-L. We compare here the results of the initial computer simulations of ADSRR-H and ADSRR-L. The results have confirmed that our concept could be the basis for designing and construction of a low neutron flux model of the proposed accelerator-driven subcritical power reactor to be moderated and cooled by lead. Our objective is to study the physics and technologies necessary to design and construct ADSRR-L. The reactor would be used for development of nuclear techniques and technologies, and for basic and applied research in neutron physics, metrology, radiation protection and radiobiology

  7. Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations; Rapport de surete du reacteur pegase - tome 1 - Description des installations - tome 2 - Surete des installations

    Energy Technology Data Exchange (ETDEWEB)

    Lacour, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legoin, P. [S.E.M. Hispano-Suiza, 92 - Colombes (France)

    1964-07-01

    In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [French] Dans le volume 1: Ce rapport est une description du reacteur Pegase, afin d'examiner la surete des installations. Le site de CADARACHE ou elles sont situees, a ete sommairement decrit, en particulier, a cause des consequences sur les techniques mises en oeuvre pour la realisation de Pegase. Nous nous sommes egalement attache a decrire les aspects originaux du reacteur. Les boucles autonomes destinees a tester en vraie grandeur des elements combustibles de la filiere uranium naturel graphite-gaz, ainsi que leurs dispositifs de controle et d'exploitation, figurent egalement dans ce rapport. Dans le volume 2: Dans le present rapport, nous examinons des accidents pouvant endommager des installations du reacteur Pegase. Les origines d'accidents examines

  8. Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations; Rapport de surete du reacteur pegase - tome 1 - Description des installations - tome 2 - Surete des installations

    Energy Technology Data Exchange (ETDEWEB)

    Lacour, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legoin, P [S.E.M. Hispano-Suiza, 92 - Colombes (France)

    1964-07-01

    In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [French] Dans le volume 1: Ce rapport est une description du reacteur Pegase, afin d'examiner la surete des installations. Le site de CADARACHE ou elles sont situees, a ete sommairement decrit, en particulier, a cause des consequences sur les techniques mises en oeuvre pour la realisation de Pegase. Nous nous sommes egalement attache a decrire les aspects originaux du reacteur. Les boucles autonomes destinees a tester en vraie grandeur des elements combustibles de la filiere uranium naturel graphite-gaz, ainsi que leurs dispositifs de controle et d'exploitation, figurent egalement dans ce rapport. Dans le volume 2: Dans le present rapport, nous examinons des accidents pouvant endommager des installations du reacteur Pegase. Les origines d'accidents examines comprennent la seismicite

  9. Installation and evaluation of a nitrogen-16 detector in the Ford nuclear reactor

    International Nuclear Information System (INIS)

    Burn, R.R.

    1995-01-01

    Core differential temperature is the final measure of steady-state power at the Ford nuclear reactor. During some evolutions, such as changing the number of cooling-tower fans in operation, differential temperature undergoes a transient and does not provide an accurate measure of true power. A 16 N detector was installed to provide a more stable measure of power, even under transient conditions

  10. Guideline for examination concerning the evaluation of safety in light water power reactor installations

    International Nuclear Information System (INIS)

    1978-01-01

    This guideline was drawn up as the guide for examination when the safety evaluation of nuclear reactors is carried out at the time of approving the installation of light water power reactors. Accordingly in case of the examination of safety, it must be confirmed that the contents of application are in conformity with this guideline. If they are in conformity, it is judged that the safety evaluation of the policy in the basic design of a reactor facility is adequate, and also that the evaluation concerning the separation from the public in surroundings is adequate as the condition of location of the reactor facility. This guideline is concerned with light water power reactors now in use, but the basic concept may be the reference for the examination of the other types of reactors. If such a case occurs that the safety evaluation does not conform to this guideline, it is not excluded when the appropriate reason is clarified. The purpose of safety evaluation, the scope to be evaluated, the selection of the events to be evaluated, the criteria for judgement, the matters taken into consideration at the time of analysis, the concrete events of abnormal transient change and accident in operation, and the concrete events of serious accident and hypothetic accident are stipulated. The explanation and two appendices are attached. (Kako, I.)

  11. User requirements in the area of safety of innovative nuclear reactors and fuel cycle installations

    International Nuclear Information System (INIS)

    Kuczera, B.; Juhn, P.E.; Fukuda, K.; )

    2002-01-01

    Full text: Against the background of already existing IAEA and INSAC publications in the area of safety, in the framework of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) a set of user requirements for the safety of future nuclear installations has been established. Five top-level requirements are expected to apply to any type of innovative design. They should foster an increased level of safety that is transparent to and fully accepted by the general public. The approach to future reactor safety includes two complementary strategies: increased emphasis on inherent safety characteristics and enhancement of defense in depth. As compared to existing plants, the effectiveness of preventing measures should be highly enhanced, resulting in fewer mitigation measures. The targets and possible approaches of each of the five levels of defense developed for innovative reactor designs are outlined in the paper

  12. Safety analysis for K reactor and impact of cooling tower installation

    International Nuclear Information System (INIS)

    Fields, C.C.; Wooten, L.A.; Geeting, M.W.; Morgan, C.E.; Buczek, J.A.; Smith, D.C.

    1993-01-01

    This paper describes the safety analysis of the Savannah River site K-reactor loss-of-cooling-water-supply (LOCWS) event and the impact on the analysis of a natural-draft cooling tower, which was installed in 1992. Historically (1954 to 1992), the K-reactor secondary cooling system [called the cooling water system (CWS)] used water from the Savannah River pumped to a 25-million-gal basin adjacent to the reactor. Approximately 170 000 gal/min were pumped from the basin through heat exchangers to remove heat from the primary cooling system. This water then entered a smaller basin, where it flowed over a weir and eventually returned to the Savannah River. The 25-million-gal basin is at a higher elevation than the heat exchangers and the smaller basin to supply cooling by gravity flow (which is sufficient to remove decay heat) if power to the CWS pumps is interrupted. Small amounts of cooling water are also used for other essential equipment such as diesels, motors, and oil coolers. With the cooling tower installed, ∼85% of the cooling water flows from the small basin by gravity to the cooling tower instead of returning to the Savannah River. After being cooled, it is pumped back to the 25-million-gal basin. River water is supplied only to make up for evaporation and the blowdown stream

  13. The economic potential of a cassette-type-reactor-installed nuclear ice-breaking container ship

    International Nuclear Information System (INIS)

    Kondo, Koichi; Takamasa, Tomoji

    1999-01-01

    An improved cassette-type marine reactor MRX (Marine Reactor X) which is currently researched and developed by the Japan Atomic Energy Research Institute is designed to be easily removed and transferred to another ship. If the reactor in a nuclear-powered ship, which is the reason for its higher cost, were replaced by the cassette-type-MRX, the reusability of the MRX would reduce the cost difference between nuclear-powered and diesel ships. As an investigation of one aspect of a cassette-type MRX, we attempted in this study to do an economic review of an MRX-installed nuclear-powered ice-breaking container ship sailing via the Arctic Ocean. The transportation cost between the Far East and Europe to carry one TEU (twenty-foot-equivalent container unit) over the entire life of the ship for an MRX (which is used for a 20-year period)-installed container ship sailing via the Arctic Ocean is about 70% higher than the Suez Canal diesel ship, carrying 8,000 TEU and sailing at 25 knots, and about 10% higher than the Suez Canal diesel ship carrying 4,000 TEU and sailing at 34 knots. The cost for a cassette-type-MRX (which is used for a 40-year period, removed and transferred to a second ship after being used for 20 years in the first ship)-installed nuclear-powered container ship is about 7% lower than that for the one operated for 20 years. Considering any loss or reduction in sales opportunities through the extension of the transportation period, the nuclear-powered container ship via the Arctic Sea is a more suitable means of transportation than a diesel ship sailing at 25 knots via the Suez Canal when the value of the commodities carried exceeds 2,800 dollars per freight ton. (author)

  14. Nuclear reactor installation with outer shell enclosing a primary pressure vessel

    International Nuclear Information System (INIS)

    1975-01-01

    The high temperature nuclear reactor installation described includes a fluid cooled nuclear heat source, a primary pressure vessel and outer shell around the primary pressure vessel and acting as a protection for it against outside projectiles. A floor is provided internally dividing the outside shell into two upper and lower sections and an inside wall dividing the lower section into one part containing the primary pressure vessel and a second part, both made pressure tight with respect to each other and with the outside shell and forming with the latter a secondary means of containment [fr

  15. Control Rod Drive Mechanism Installed in the Internal of Reactor Pressure Vessel

    Energy Technology Data Exchange (ETDEWEB)

    Choi, M. H.; Choi, S.; Park, J. S.; Lee, J. S.; Kim, D. O.; Hur, N. S.; Hur, H.; Yu, J. Y

    2008-09-15

    This report describes the review results and important technologies related to the in-vessel type control rod drive mechanism. Generally, most of the CRDMs used in the PWR are attached outside of the reactor pressure vessel, and the pernetration of the vessel head can not avoid. However, in-vessel type CRDMs, which are installed inside the reactor vessel, can eliminate the possibility of rod ejection accidents and the penetration of the vessel head, and provide a compact design of the reactor vessel and containment. There are two kinds of in-vessel type CRDM concerning the driving force-driven by a driving motor and by a hydraulic force. Motor driven CRDMs have been mainly investigated in Japan(MRX, IMR, DRX, next generation BWR etc.), and developed the key components such as a canned motor, an integrated rod position indicator, a separating ball-nut and a ball bearing that can operate under the water conditions of a high temperature and pressure. The concept of hydraulically driven CRDMs have been first reported by KWU and Siemens for KWU 200 reactor, and Argentina(CAREM) and China(NHR-5, NHR-200) have been developed the internal CRDM with the piston and cylinder of slightly different geometries. These systems are driven by the hydraulic force which is produced by pumps outside of the reactor vessel and transmitted through a pipe penetrating the reactor vessel, and needs complicated control and piping systems including pumps, valves and pipes etc.. IRIS has been recently decided the internal CRDMs as the reference design, and an analytical and experimental investigations of the hydraulic drive concept are performed by POLIMI in Italy. Also, a small French company, MP98 has been developed a new type of control rods, called 'liquid control rods', where reactivity is controlled by the movement of a liquid absorber in a manometer type device.

  16. Design, manufacture and installation of measuring and control equipments for the advanced thermal prototype reactor 'Fugen'

    International Nuclear Information System (INIS)

    Hirota, Shigeo; Kawabata, Yoshinori

    1979-01-01

    The advanced thermal prototype reactor ''Fugen'' attained the criticality on March 20, 1978, and 100% output operation on November 13, 1978. On March 20, 1979, it passed the final inspection, and since then, it has continued the smooth operation up to now. The measuring and control equipments are provided for grasping the operational conditions of the plant and operating it safely and efficiently. At the time of designing, manufacturing and installing the measuring and control equipments for Fugen, it was required to clarify the requirements of the plant design, to secure the sufficient functions, and to improve the operational process, maintainability and the reliability and accuracy of the equipments. Many design guidelines and criteria were decided in order to coordinate the conditions among five manufacturers and give the unified state as one plant. The outline of the instrumentations for neutrons, radiation monitoring and process data, the control systems for reactivity, reactor output, pressure and water supply, the safety protection system, and the process computer are described. Finally, the installations and tests of the measuring and control equipments are explained. The aseismatic capability of the equipments was confirmed. (Kako, I.)

  17. Considerations about decommissioning of the IEA-R1 research reactor and the future of its installations after shutdown

    International Nuclear Information System (INIS)

    Frajndlich, Roberto

    2014-01-01

    The IEA-R1 Nuclear Research Reactor, in operation since 1957, in the Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), is one of the oldest research reactors in the world. However at some point in time in the future, as example of the other reactors, it will be shutdown definitively. Before that time actually arrives, the operational organization needs to plan the future of its installations and define the final destination of equipment and radioactive as well as non-radioactive material contained inside the installations. These and other questions should be addressed in the so called Preliminary decommissioning plan of the installation, which is the subject of this work. The work initially presents an over view about the theme and defines the general and specific objectives describing, in succession, the directions that the operating organization should consider for the formulation of a decommissioning plan. The present structure of the Brazilian nuclear sector emphasizing principally the norms utilized in the management of radioactive waste is also presented. A description of principle equipment of the IEA-R1 reactor which constitutes its inventory of radioactive and non-radioactive material is given. The work emphasizes the experience of the reactor technicians, acquired during several reforms and modifications of the reactor installations realized during its useful life time. This experience may be of great help for the decommissioning in the future. An experiment using the high resolution gamma spectrometric method and computer calculation using Monte Carlo theory were performed with the objective of obtaining an estimate of the radioactive waste produced from dismantling of the reactor pool walls. The cost of reactor decommissioning for different choices of strategies was determined using the CERREX code. Finally, a discussion about different strategies is presented. On the basis of these discussions it is concluded that the most advantageous

  18. Upgrading of the triple axis neutron spectrometer TKSN-400 installed at Pakistan research reactor-1

    International Nuclear Information System (INIS)

    Bashir, J; Khan, R.T.A.; Khan, M.M.; Iqbal, N.; Waheed, A.; Hussain, A.; Khan, A.U.; Zaman, Q.

    2000-01-01

    The triple axis neutron spectrometer TKSN-400 installed at 10MW Pakistan Research Reactor has been upgraded. The upgrading included the development of a multi-counter assembly, a PC based spectrometer control and data acquisition system. The multi-counter assembly consists of an embankment of 8 pairs of /sup 3/He counter and 40' collimator. This system is more auspicious than the original arrangement because each of the collimator/counter pair is virtually identical, permitting automatic addition of the intensities and consequently a single high resolution profile as obtained with single counter machine. With these modifications, it has now become possible to measure the complete diffraction pattern in about 24 hours. Finally, the results obtained from the latest system are compared with the results reported in literature. (author)

  19. Installation and commissioning of operation nuclear power plant reactor protection system modernization project

    International Nuclear Information System (INIS)

    Lu Weiwei

    2010-01-01

    Qinshan Nuclear Power Plant is the first nuclear power plant in mainland China; it is also the first one which realizes the modernization of analog technology based Reactor Protection System in the operation nuclear power plant of China. The implementation schedule is the shortest one which use same digital technology platform (TELEPERM XS of AREVA NP) to modifying the safety class I and C system in the world, the whole project spent 28 months from equipment contract signed to putting system into operation. It open up a era for operation nuclear power plant using mature digital technology to make safety class I and C system modernization in China. The important practical significance of this successful project is very obvious. This article focus on two important project stage--equipment installation and system commissioning, it is based on a large number of engineering implementation fact, it covers the problems and solutions happened during the installation and commission. The purpose of the article is to share the experience and lessons of safety I and C system modernization for other operation nuclear power plant. (authors)

  20. Regulations concerning licensing of nuclear reactor facilities and other nuclear installations, Decree No 7/9141, 6 January 1975

    International Nuclear Information System (INIS)

    1975-01-01

    This Decree lays down the licensing system for nuclear installations in Turkey and also sets up a Nuclear Safety Committee whose duty is to ensure that the requirements of this Decree are met. The Committee is made up of members of the Atomic Energy Commission specialized in reactors, nuclear safety, health physics, reactor physics as well as two experts respectively appointed by the Ministry of Health and Social Welfare and the Ministry of Energy and National Resources. (NEA) [fr

  1. The design and installation of a core discharge monitor for CANDU-type reactors

    International Nuclear Information System (INIS)

    Halbig, J.K.; Monticone, A.C.; Ksiezak, L.; Smiltnieks, V.

    1990-01-01

    A new type of surveillance systems that monitors neutron and gamma radiation in a reactor containment is being installed at the Ontario Hydro Darlington Nuclear Generating Station A, Unit 2. Unlike video or film surveillance that monitors mechanical motion, this system measures fuel-specific radiation emanating from irradiated fuel as it is pushed from the core of CANDU-type reactors. Proof-of-principle measurements have been carried out at Bruce Nuclear Generating Station A, Unit 3. The system uses (γ,n) threshold detectors and ionization detectors. A microprocessor-based electronics package, GRAND-II (Gamma Ray and Neutron Detector electronics package), provides detector bias, preamplifier power, and signal processing. Firmware in the GRAND-2 controls the surveillance activities, including data acquisition and a level of detector authentication, and it handles authenticated communication with a central data logging computer. Data from the GRAND-II are transferred to an MS-DOS-compatible computer and stored. These data are collected and reviewed for fuel-specific radiation signatures from the primary detector and proper ratios of signals from secondary detectors. 5 figs

  2. Nuclear reactor installation with outer shell enclosing a primary pressure vessel

    International Nuclear Information System (INIS)

    1975-01-01

    The high temperature nuclear reactor installation described includes a fluid cooled nuclear heat source, a primary pressure vessel containing the heat source, an outer shell enclosing the primary pressure vessel and acting as a secondary means of containment for this vessel against outside projectiles. Multiple auxiliary equipment points are arranged outside the outer shell which comprises a part of a lower wall around the primary pressure vessel, an annular part integrated in the lower wall and extending outwards as from this wall and an upper part integrated in the annular part and extending above this annular part and above the primary pressure vessel. The annular part and the primary pressure vessel are formed with vertical penetrations which can be closed communicating respectively with the auxiliary equipment points and with inside the pressure vessel whilst handling gear is provided in the upper part for vertically raising reactor components through these penetrations and for transporting them over the annular part and over the primary pressure vessel [fr

  3. Installation, performance, safety aspects and technical data of the triple axis Spectrometer at TRIGA Reactor of AERE

    International Nuclear Information System (INIS)

    Yunus, S. M.; Kamal, I.; Datta, T. K.; Zakaria, A. K. M.; Ahmed, F. U.

    2004-02-01

    The technical data of the Triple Axis Neutro Spectrometer installed at the 3 MW TRIGA Mark II research reactor has been described. These are the reference data required for the operation, maintenance and use of the spectrometer. The detail information of the installation of the spectrometer has been given. Radiation safety features of the spectrometer and around the radial piercing beam port (where the spectrometer is installed) are described elaborately. The quality test experiments and the performance of the spectrometer as found from these tests are also described

  4. Membrane bio-reactor - Research, pilot installation and measurement campaign; Membranbioreaktor (MBR) - Forschung, Pilotanlage und Messkampagne - Schlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Hersener, J -L [Ingenieurbuero Hersener, Wiesendangen (Switzerland); Meier, U [Meritec GmbH, Guntershausen (Switzerland)

    2007-07-01

    This report for the Swiss Federal Office of Energy (SFOE), takes a look at a project involving a fermenter installation in Eastern Switzerland. Research work is noted, the pilot installation is described and the results of a measurement campaign are presented and commented on. The plant is able to handle about 20,000-25,000 tonnes of slurry and organic waste. The plant is built as a membrane bio-reactor and allows the separation of the digested biomass into fractions of solid and liquid fertilisers and useful water. Furthermore, a part of the separated and digested liquid is returned to the fermenter in order to improve the digestion process. For the production of electricity a 1.1 MW generator is installed. The adaptations made during the measurement period are noted and commented on. According to the authors, the results - although difficult to interpret - show that the concept of a membrane bio-reactor can work successfully.

  5. Neutron field characterization in the installation for BNCT study in the IEA-R1 reactor

    International Nuclear Information System (INIS)

    Carneiro Junior, Valdeci

    2008-01-01

    This work aims to characterize the mixed neutron and gamma field, in the sample irradiation position, in a research installation for Boron Neutron Capture Therapy (BNCT), in the IPEN IEA-R1 reactor. The BNCT technique has been studied as a safe and selective option in the treatment of resistant cancerigenous tumors or considered non-curable by the conventional techniques, for example, the Glioblastoma Multiform - a brain cancerigenous tumor. Neutron flux measurements were carried out: thermal, resonance and fast, as well as neutron and gamma rays doses, in the sample position, using activation foils detectors and thermoluminescent dosimeters. For the determination of the neutron spectrum and intensity, a set of different threshold activation foils and gold foils covered and uncovered with cadmium irradiated in the installation was used, analyzed by a high Pure Germanium semiconductor detector, coupled to an electronic system suitable for gamma spectrometry. The results were processed with the SAND-BP code. The doses due to gamma and neutron rays were determined using thermoluminescent dosimeters TLD 400 and TLD 700 sensitive to gamma and TLD 600, sensitive to neutrons. The TLDs were selected and used for obtaining the calibration curves - dosimeter answer versus dose - from each of the TLD three types, which were necessary to calculate the doses due to neutron and gamma, in the sample position. The radiation field, in the sample irradiation position, was characterized flux for thermal neutrons of 1.39.10 8 ± 0,12.10 8 n/cm 2 s the doses due to thermal neutrons are three times higher than those due to gamma radiation and confirm the reproducibility and consistency of the experimental findings obtained. Considering these results, the neutron field and gamma radiation showed to be appropriated for research in BNCT. (author)

  6. Evaluation of organic endocrine disruptors in water at Brazilian Multipurpose Reactor - RMB installation area

    International Nuclear Information System (INIS)

    Silva, Larissa L.; Martins, Elâine A.J.; Cotrim, Marycel E.B.; Pires, Maria A.F.

    2017-01-01

    The study of pollutants with organic and inorganic characteristics in groundwater and surface waters of a given region is an important tool in the assessment of pollution. Endocrine interferers are synthetic or natural chemicals that have the ability to act on the endocrine system of humans and animals by mimetizing natural hormones and may produce adverse effects on organisms, even in low concentrations (μg or ng.L -1 ). Anthropic activities are the major source of input of endocrine disruptors into the environment. The Brazilian government has a project to construct a multipurpose reactor, Brazilian Multipurpose Reactor (RMB), at the Iperó city, to improve the nuclear research Brazilian capacity. The object of this research in to analyze 14 organic compounds that may be present in the groundwater and surface waters of the RMB installation area. This is an unprecedented and extremely important study for the evaluated region; since it will provide guidance on the degree of contamination of the local waters before the construction begins. The study will also make it possible to verify if the construction of the RMB will offer environmental issues to the place. For the determination of the compounds of interest, a developed and validated analytical method was used. This methodology consists of the concentration of the samples by solid phase extraction (SPE) followed by quantification by gas chromatography coupled to the mass spectrometry detector (GC/MS). The water column particulate was also evaluated by ultrasonic extraction, followed by quantification by GC/MS. The results reveal that some of the compounds were found and it was due to anthropic activities in the vicinity of the regions. By initial analysis it was possible verify river that cross the RMB area present values below 0.05 μg L -1 . (author)

  7. Evaluation of organic endocrine disruptors in water at Brazilian Multipurpose Reactor - RMB installation area

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Larissa L.; Martins, Elâine A.J.; Cotrim, Marycel E.B.; Pires, Maria A.F., E-mail: larissa.limeira07@gmail.com, E-mail: elaine@ipen.br, E-mail: mecotrim@ipen.br, E-mail: mapires@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The study of pollutants with organic and inorganic characteristics in groundwater and surface waters of a given region is an important tool in the assessment of pollution. Endocrine interferers are synthetic or natural chemicals that have the ability to act on the endocrine system of humans and animals by mimetizing natural hormones and may produce adverse effects on organisms, even in low concentrations (μg or ng.L{sup -1}). Anthropic activities are the major source of input of endocrine disruptors into the environment. The Brazilian government has a project to construct a multipurpose reactor, Brazilian Multipurpose Reactor (RMB), at the Iperó city, to improve the nuclear research Brazilian capacity. The object of this research in to analyze 14 organic compounds that may be present in the groundwater and surface waters of the RMB installation area. This is an unprecedented and extremely important study for the evaluated region; since it will provide guidance on the degree of contamination of the local waters before the construction begins. The study will also make it possible to verify if the construction of the RMB will offer environmental issues to the place. For the determination of the compounds of interest, a developed and validated analytical method was used. This methodology consists of the concentration of the samples by solid phase extraction (SPE) followed by quantification by gas chromatography coupled to the mass spectrometry detector (GC/MS). The water column particulate was also evaluated by ultrasonic extraction, followed by quantification by GC/MS. The results reveal that some of the compounds were found and it was due to anthropic activities in the vicinity of the regions. By initial analysis it was possible verify river that cross the RMB area present values below 0.05 μg L{sup -1}. (author)

  8. Installation and testing of an optimized epithermal neutron beam at the Brookhaven Medical Research Reactor (BMRR)

    Energy Technology Data Exchange (ETDEWEB)

    Fairchild, R.G.; Kalef-Ezra, J.; Saraf, S.K.; Fiarman, S.; Ramsey, E.; Wielopolski, L.; Laster, B.; Wheeler, F. (Brookhaven National Lab., Upton, NY (USA); Ioannina Univ. (Greece); Brookhaven National Lab., Upton, NY (USA); State Univ. of New York, Stony Brook, NY (USA). Health Science Center; Brookhaven National Lab., Upton, NY (USA); EG and G Idaho, Inc., Idaho Falls, ID (USA))

    1989-01-01

    Various calculations indicate that an optimized epithermal neutron beam can be produced by moderating fission neutrons either with a combination of Al and D{sub 2}O, or with Al{sub 2}O{sub 3}. We have designed, installed and tested an Al{sub 2}O{sub 3} moderated epithermal neutron beam at the Brookhaven Medical Research Reactor (BMRR). The epithermal neutron fluence rate of 1.8 {times} 10{sup 9} n/cm{sup 2}-sec produces a peak thermal neutron fluence rate of 1.9 to 2.8 {times} 10{sup 9} n/cm{sup 2}-sec in a tissue equivalent (TE) phantom head, depending on the configuration. Thus a single therapy treatment of 5 {times} 10{sup 12} n/cm{sup 2} can be delivered in 30--45 minutes. All irradiation times are given for a BMRR power of 3 MW, which is the highest power which can be delivered continuously. 18 refs., 8 figs., 4 tabs.

  9. Determination of polycyclic aromatic hydrocarbons (PAHs) in sediment samples of Brazilian Multipurpose Reactor (RMB) installation area

    International Nuclear Information System (INIS)

    Silva, Juliana C.; Martins, Elâine A.J.; Cotrim, Marycel E.B.; Pires, Maria A.F.

    2017-01-01

    RMB will be a nuclear reactor for research and production of radioisotopes. Its applications extend to agriculture, industry and the environment. With the changes that will occur in the study area by its construction, the flow of vehicles will increase. It is known that one of the largest anthropogenic sources of PAHs is from the burning of fossil fuels and biomass. The aim of this research was to identify and quantify 14 of the 16 majorities PAHs in the sediment samples at RMB installations area in a period before the enterprise construction, June 2017, using the methodology developed and validated by Brito, 2009. It was observed individual concentrations from 0.05 to 1.11 μg g -1 in this first evaluation indicating that, although were found some PAHs concentrations above the established values by CONAMA and CETESB, this area still remains preserved. Pyrene was the compound that had the highest concentrations at different collecting points (1.11±0.03 and 1.09±0.02 μg g -1 ). Although were observed some PAHs concentrations above the established values by CONAMA and CETESB, the area is preserved. The study will provide previous information on PAHs concentrations in the area of the enterprise, providing information for the environmental impact study after the construction of the enterprise. (author)

  10. Determination of polycyclic aromatic hydrocarbons (PAHs) in sediment samples of Brazilian Multipurpose Reactor (RMB) installation area

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Juliana C.; Martins, Elâine A.J.; Cotrim, Marycel E.B.; Pires, Maria A.F., E-mail: elaine@ipen.br, E-mail: mecotrim@ipen.br, E-mail: mapires@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    RMB will be a nuclear reactor for research and production of radioisotopes. Its applications extend to agriculture, industry and the environment. With the changes that will occur in the study area by its construction, the flow of vehicles will increase. It is known that one of the largest anthropogenic sources of PAHs is from the burning of fossil fuels and biomass. The aim of this research was to identify and quantify 14 of the 16 majorities PAHs in the sediment samples at RMB installations area in a period before the enterprise construction, June 2017, using the methodology developed and validated by Brito, 2009. It was observed individual concentrations from 0.05 to 1.11 μg g{sup -1} in this first evaluation indicating that, although were found some PAHs concentrations above the established values by CONAMA and CETESB, this area still remains preserved. Pyrene was the compound that had the highest concentrations at different collecting points (1.11±0.03 and 1.09±0.02 μg g{sup -1}). Although were observed some PAHs concentrations above the established values by CONAMA and CETESB, the area is preserved. The study will provide previous information on PAHs concentrations in the area of the enterprise, providing information for the environmental impact study after the construction of the enterprise. (author)

  11. Toxic elements in sediment from two water bodies near Brazilian Multipurpose Reactor: RMB installation area

    International Nuclear Information System (INIS)

    Silva, Tatiane B.S.C. da; Stellato, Thamiris B.; Monteiro, Lucilena R.; Marques, Joyce R.; Faustino, Mainara G.; Santos, Camila F.R.T.T.; Oliveira, Cintia C. de; Miranda, Gabrielle S.; Pires, Maria Aparecida F.; Cotrim, Marycel E.B.

    2017-01-01

    Aquatic ecosystems are directly affected by contaminants, such as, toxic elements that do not remain in sediment in a insoluble form. Anthropogenic and natural actions influence sediment dynamics that could lead to a potential contaminant accumulation. Therefore, to evaluate possible environmental impacts is,in many cases, mandatory. Environmental impact assessment studies are a licensing tool that seeks to control degradation activities, taking into account the legal and regulatory provisions and technical standards applicable to the case. The present study aims to evaluate the sediment quality in the area of influence of the Brazilian Multipurpose Nuclear Reactor (RMB) to be installed in the contiguous area of the Experimental Center of Aramar of the Technological Center of the Navy in São Paulo (CTMSP), located in the city of Iperó - SP. The potentially toxic elements As, Cd and Hg were analyzed by Graphite Furnace Atomic Absorption Spectrometry (GFAAS) and Cr, Cu, Ni and Zn by Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES). Results were compared with Canadian Council of Ministers of the Environment (CCME) guideline values (TEL and PEL) and the maximum permitted values of Resolution 454/12. These toxic elements (As, Cd, Hg, Cr, Cu, Ni and Zn) were found below maximum allowed concentrations from national and international legislation. This study provides support for RMB post-completion evaluations, in order to prevent these elements to exceed tolerated levels, ensuring ecological, social and economic values. (author)

  12. Toxic elements in sediment from two water bodies near Brazilian Multipurpose Reactor: RMB installation area

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Tatiane B.S.C. da; Stellato, Thamiris B.; Monteiro, Lucilena R.; Marques, Joyce R.; Faustino, Mainara G.; Santos, Camila F.R.T.T.; Oliveira, Cintia C. de; Miranda, Gabrielle S.; Pires, Maria Aparecida F.; Cotrim, Marycel E.B., E-mail: tatianebscs@live.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2017-07-01

    Aquatic ecosystems are directly affected by contaminants, such as, toxic elements that do not remain in sediment in a insoluble form. Anthropogenic and natural actions influence sediment dynamics that could lead to a potential contaminant accumulation. Therefore, to evaluate possible environmental impacts is,in many cases, mandatory. Environmental impact assessment studies are a licensing tool that seeks to control degradation activities, taking into account the legal and regulatory provisions and technical standards applicable to the case. The present study aims to evaluate the sediment quality in the area of influence of the Brazilian Multipurpose Nuclear Reactor (RMB) to be installed in the contiguous area of the Experimental Center of Aramar of the Technological Center of the Navy in São Paulo (CTMSP), located in the city of Iperó - SP. The potentially toxic elements As, Cd and Hg were analyzed by Graphite Furnace Atomic Absorption Spectrometry (GFAAS) and Cr, Cu, Ni and Zn by Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES). Results were compared with Canadian Council of Ministers of the Environment (CCME) guideline values (TEL and PEL) and the maximum permitted values of Resolution 454/12. These toxic elements (As, Cd, Hg, Cr, Cu, Ni and Zn) were found below maximum allowed concentrations from national and international legislation. This study provides support for RMB post-completion evaluations, in order to prevent these elements to exceed tolerated levels, ensuring ecological, social and economic values. (author)

  13. Concerning installation of reactor at Noto nuclear power plant of Hokuriku Electric Power Co., Inc. (reply to inquiry)

    International Nuclear Information System (INIS)

    1988-01-01

    In response to an inquiry on the conformity of the title issue to the applicable law concerning nuclear material, nuclear fuel and nuclear reactor, the Nuclear Safety Commission ordered the Nuclear Reactor Safety Expert Group to make a study, made an examination after receiving a report from the Group, and submit the findings to the Minister of International Trade and Industry. The study on the site conditions covered the site location, geology, effects or earthquakes, meteorology, hydrology and social environment. The study on the safety design of the reactor covered the design of the facilities as a whole, anti-earthquake design, reactor, instrumentation, reactor shutdown system, reactivity control, protection, cooling system, reactor vessel, fuel handling, fuel storage, and radiation control. The study also included exposure evaluation, abnormal transient state analysis and accident analysis. It is concluded that the relevant company has a technical capability required for the installation and proper operation of the reactor in question, and that the reactor will have adequate safety with no possibility of causing a disaster. (Nogami, K.)

  14. Change in plan for installation of nuclear reactor in No.1 atomic powered vessel of Japan Atomic Energy Research Institute (change in purpose of use and in method for nuclear reactor installation and spent fuel disposal) (report)

    International Nuclear Information System (INIS)

    1987-01-01

    This report, compiled by the Nuclear Safety Commission to be submitted to the Prime Minister, deals with studies concerning some changes in the plan for the installation of a nuclear reactor in the No.1 atomic powered vessel to be constructed under the Japan Atomic Energy Research Institute (changes in the purpose of its use and in the methods for the nuclear reactor installation and spent fuel disposal). The conclusions of and procedures for the examination and evaluation are presented and then detailes of the studies are described. The study on the location requirements for the incidental land facilities at Sekinehama covers various conditions concerning the location, geology, earthquakes, meteorology, hydrology and social environment. The study on the safety design of the nuclear reactor facilities deals with the reactor, fuel handling facilities and other auxiliary facilities, as well as various land facilities to be constructed at Sekinehama including the reactor facilities and other facilities for fuel handling, waste disposal and protection and management of radioactive rays. Evaluation of possible radiation emission is shown and the accident analysis is also addressed. (Nogami, K.)

  15. Apparatus for installing and removing a control rod drive in a nuclear reactor

    International Nuclear Information System (INIS)

    Turner, A.P.L.; Ward, R.

    1989-01-01

    This patent describes an apparatus for installing and removing a control rod drive from beneath the pressure vessel of a nuclear reactor. It consists of elevator carriage for carrying the control rod drive into and out of the region beneath the pressure vessel in a generally horizontal position, an elevator cradle mounted on the carriage for pivotal movement about an axis between horizontal and vertical positions and for vertical movement, when in the vertical position, means for securing the control rod drive to the elevator cradle, and a winch cart movable horizontally between a first position spaced from the pivot axis and a second position near the pivot axis. The cart has a winch cable supporting the lower end of the elevator carriage for moving the elevator carriage and the control rod drive between horizontal and vertical positions on the elevator carriage when the cart is spaced from the pivot axis and for raising and lowering the elevator cradle and the control rod drive when the cart is positioned near the pivot axis. The control rod drive is mounted on the elevator cradle by a bearing permitting rotational and horizontal movement of the control rod drive when the drive is in a vertical position, a swing arm, a pneumatically actuated cylinder in axial alignment with the control rod drive for raising and lowering the control rod drive, and means pivotally mounting the cylinder on the swing arm for movement about an axis spaced from and generally parallel to the vertically extending axis so that the position of the cylinder and the control rod drive can be shifted horizontally about the vertically extending axes

  16. The economic potential of a cassette-type-reactor-installed nuclear ice-breaking container ship

    International Nuclear Information System (INIS)

    Kondo, K.; Takamasa, T.

    2000-01-01

    The design concept of the cassette-type-reactor MRX (Marine Reactor X), being under development in Japan for the nuclear ice-breaker container ship is described. The MRX reactor is the monoblock water-cooled and moderated reactor with passive cooling system of natural circulation. It is shown that application of the reactor being under consideration gives an opportunity to decrease greatly the difference in prices for similar nuclear and diesel ships. Economic estimations for applicability of the nuclear ice-breaker container ship with the MRX reactor in Arctics for transportation of standard containers TEU from Europe to Far East as compared with transportation of the same containers by diesel ships via Suets Canal are made [ru

  17. Installation modification of the reactor No.2 of Ikata nuclear power plant of Shikoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1980-01-01

    The application was made on August 25, 1979, from the president of the Shikoku Electric Power Company, Inc., to the Minister of International Trade and Industry, relating to the installation modification of the reactor No. 2 in the Ikata nuclear power plant. The inquiry was submitted on September 28, 1979, from the Minister of International Trade and Industry to the Nuclear Safety Commission, after the safety evaluation in the Ministry of International Trade and Industry, and the investigation and deliberation were started on October 1, 1979, in the Nuclear Safety Commission. The content of the modification is to add the circuit actuated by the abnormal low pressure signal of the reactor to the actuating circuit of the emergency core cooling system (ECCS) and to increase the new fuel storage capacity from about 1/3 core to about 2/3 core. The additional signal circuit is composed of the logic circuit of ''2 out of 4'' and is multichannel design. The circuit is independent from the reactor control system and the conventional signal circuit of the concurrence of low pressure in the reactor and low level in the pressurizer. With the addition of the circuit of abnormal low pressure signal of the reactor, the countermeasures for preventing ECCS start by mistake are also added. These modifications give no influence to the functions of the reactor control system and reactor protection system. The function and the performance of ECCS were analyzed and evaluated accompanying these modifications assuming the loss of coolant accident. Concerning the new fuel storage capacity, the type of racks is modified from angle type to can type, and the subcriticality is kept even at the time of water flood. (Nakai, Y.)

  18. Design and installation of a hot water layer system at the Tehran research reactor

    Directory of Open Access Journals (Sweden)

    Mirmohammadi Sayedeh Leila

    2013-01-01

    Full Text Available A hot water layer system (HWLS is a novel system for reducing radioactivity under research reactor containment. This system is particularly useful in pool-type research reactors or other light water reactors with an open pool surface. The main purpose of a HWLS is to provide more protection for operators and reactor personnel against undesired doses due to the radio- activity of the primary loop. This radioactivity originates mainly from the induced radioactivity contained within the cooling water or probable minute leaks of fuel elements. More importantly, the bothersome radioactivity is progressively proportional to reactor power and, thus, the HWLS is a partial solution for mitigating such problems when power upgrading is planned. Following a series of tests and checks for different parameters, a HWLS has been built and put into operation at the Tehran research reactor in 2009. It underwent a series of comprehensive tests for a period of 6 months. Within this time-frame, it was realized that the HWLS could provide a better protection for reactor personnel against prevailing radiation under containment. The system is especially suitable in cases of abnormality, e. g. the spread of fission products due to fuel failure, because it prevents the mixing of pollutants developed deep in the pool with the upper layer and thus mitigates widespread leakage of radioactivity.

  19. Hydrodynamic problems of heavy liquid metal coolants technology in loop-type and mono-block-type reactor installations

    International Nuclear Information System (INIS)

    Orlov, Yuri I.; Efanov, Alexander D.; Martynov, Pyotr N.; Gulevsky, Valery A.; Papovyants, Albert K.; Levchenko, Yuri D.; Ulyanov, Vladimir V.

    2007-01-01

    In the report, the influence of hydrodynamics of the loop with heavy liquid metal coolants (Pb and Pb-Bi) on the realization methods and efficiency of the coolant technology for the reactor installations of loop, improved loop and mono-block type of design has been studied. The last two types of installations, as a rule, are characterized by the following features: availability of loop sections with low hydraulic head and low coolant velocities, large squares of coolant free surfaces; absence of stop and regulating valve, auxiliary pumps on the coolant pumping-over lines. Because of the different hydrodynamic conditions in the installation types, the tasks of the coolant technology have specific solutions. The description of the following procedures of coolant technology is given in the report: purification by hydrogen (purification using gas mixture containing hydrogen), regulation of dissolved oxygen concentration in coolant, coolant filtrating, control of dissolved oxygen concentration in coolant. It is shown that change of the loop design made with economic purpose and for improvement of the installation safety cause additional requirements to the procedures and apparatuses of the coolant technology realization

  20. Installation and testing of the ERANOS computer code for fast reactor calculations

    International Nuclear Information System (INIS)

    Gren, Milan

    2010-12-01

    The French ERANOS computer code was acquired and tested by solving benchmark problems. Five problems were calculated: 1D XZ Model, 1D RZ Model, 3D HEX SNR 300 reactor, 2S HEX and 3D HEX VVER 440 reactor. The multi-group diffuse approximation was used. The multiplication coefficients were compared within the first problem, neutron flux density in the calculation points was obtained within the second problem, and powers in the various reactor areas and in the assemblies were calculated within the remaining problems. (P.A.)

  1. First experiences from system integration, installation and commissioning of TELEPERM XS for reactor I and C at the Unterweser NPP

    International Nuclear Information System (INIS)

    Schoerner, O.

    1998-01-01

    The modernization of Reactor I and C, consisting of reactor limitation system, reactor control system and rod control system, at Unterweser NPP is the pilot application of the state-of-the-art safety I and C system TELEPERM XS. The Unterweser system has been integrated and tested from December 1996 to May 1997 in the Siemens Erlangen test field and has been installed at site in July 1997. For the period from July 1997 to Jul 1998 the new TELEPERM XS based Reactor I and C system will be operated online-open-loop in parallel to the existing system, in order to get information about the long term stability of the system and conduct intensive personnel training. For one selected function ''Power distribution control'' the operator has the possibility to choose between the old controller and the new TELEPERM XS function. During the 1998 outage the TELEPERM XS system will be connected to the process and the old I and C system will be dismantled. This document describes the experiences gathered during system integration in the test field. (author)

  2. Method for installing a control rod driving device in a reactor

    International Nuclear Information System (INIS)

    Sato, Haruo; Watanabe, Masatoshi.

    1975-01-01

    Object: To install a device using a wire rope, including individually moving up and down a control rod and a control rod driving device thereby enabling to install them within a low house and to reduce time required for installing operation. Structure: The control rod is temporarily attached to a support structure for the control rod driving device, the control rod driving device is suspended on a crane positioned upwardly of the support structure, a rope connected to the control rod driving device is connected to the control rod, a sagged portion of the rope is then wound about a rotary cylinder, the control rod is disconnected from its temporary attachment, and the wound rope is wound back while the rotary cylinder is rotated to move down the control rod. After the rope has been released from the rotary cylinder, the control rod driving device is moved down by the crane. (Kamimura, M.)

  3. Evaluation of PAHs in groundwater and surface waters at Multipurpose Reactor Installation Area

    International Nuclear Information System (INIS)

    Pereira, Karoline P.; Martins, Elâine A.J.; Cotrim, Marycel E.B.; Pires, Maria A.F.

    2017-01-01

    Brazil has four research reactors in operation, all old and low power. The IEA-R1 reactor of IPEN/CNEN-SP has only limited radioisotope production capacity, materials irradiation, and neutron beam utilization. This reactor has been operating for fifty-nine years and has prospects of operation for a maximum period of ten years. It is necessary to implement a new reactor, which will support nuclear activities, and the national strategic objectives related to technological development in the areas of energy and defense; scientific and technological development; training of human resources and the growing production of radioisotopes for medical application. The Brazilian Multipurpose Reactor (RMB) will be a nuclear reactor for research and will be built in the state of São Paulo, in the municipality of Iperó. Its construction may involve the release of effluents into the environment. With monitoring before, during and after construction, it will be possible to verify if the construction itself will harm the environment. Several organics compounds are released daily in water bodies collaborating for environmental imbalance. Many of them have carcinogenic and mutagenic properties, receiving more attention by the scientific community. Most of the organic compounds are not included in environmental legislation and many of them present high toxicity, especially those classified as endocrine disrupters, as some Polycyclic Aromatic Hydrocarbons (PAHs). Only seven of the thirteen PAHs studied in this project are contemplated in Brazilian legislation, and just one is contained in international legislation. The PAHs studied in this work present, considered hazardous chemical compounds due to their toxicity, persistence in the environment, their bioaccumulative potential and their tendency to biomagnify. For the determination of the PAHs, the samples were concentrated by solid phase extraction (SPE) followed by quantification by High Performance Liquid Chromatography (HPLC). It

  4. Evaluation of PAHs in groundwater and surface waters at Multipurpose Reactor Installation Area

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Karoline P.; Martins, Elâine A.J.; Cotrim, Marycel E.B.; Pires, Maria A.F., E-mail: karolinedepaulapereira@usp.br, E-mail: elaine@ipen.br, E-mail: mecotrim@ipen.br, E-mail: mapires@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    Brazil has four research reactors in operation, all old and low power. The IEA-R1 reactor of IPEN/CNEN-SP has only limited radioisotope production capacity, materials irradiation, and neutron beam utilization. This reactor has been operating for fifty-nine years and has prospects of operation for a maximum period of ten years. It is necessary to implement a new reactor, which will support nuclear activities, and the national strategic objectives related to technological development in the areas of energy and defense; scientific and technological development; training of human resources and the growing production of radioisotopes for medical application. The Brazilian Multipurpose Reactor (RMB) will be a nuclear reactor for research and will be built in the state of São Paulo, in the municipality of Iperó. Its construction may involve the release of effluents into the environment. With monitoring before, during and after construction, it will be possible to verify if the construction itself will harm the environment. Several organics compounds are released daily in water bodies collaborating for environmental imbalance. Many of them have carcinogenic and mutagenic properties, receiving more attention by the scientific community. Most of the organic compounds are not included in environmental legislation and many of them present high toxicity, especially those classified as endocrine disrupters, as some Polycyclic Aromatic Hydrocarbons (PAHs). Only seven of the thirteen PAHs studied in this project are contemplated in Brazilian legislation, and just one is contained in international legislation. The PAHs studied in this work present, considered hazardous chemical compounds due to their toxicity, persistence in the environment, their bioaccumulative potential and their tendency to biomagnify. For the determination of the PAHs, the samples were concentrated by solid phase extraction (SPE) followed by quantification by High Performance Liquid Chromatography (HPLC). It

  5. Operating experience feedback report: Experience with pump seals installed in reactor coolant pumps manufactured by Byron Jackson

    International Nuclear Information System (INIS)

    Bell, L.G.; O'Reilly, P.D.

    1992-09-01

    This report examines the reactor coolant pump (RCP) seal operating experience through August 1990 at plants with Byron Jackson (B-J) RCPs. ne operating experience examined in this analysis included a review of the practice of continuing operation with a degraded seal. Plants with B-J RCPs that have had relatively good experience with their RCP seals attribute this success to a combination of different factors, including: enhanced seal QA efforts, modified/new seal designs, improved maintenance procedures and training, attention to detail, improved seal operating procedures, knowledgeable personnel involved in seal maintenance and operation, reduction in frequency of transients that stress the seals, seal handling and installation equipment designed to the appropriate precision, and maintenance of a clean seal cooling water system. As more plants have implemented corrective measures such as these, the number of B-J RCP seal failures experienced has tended to decrease. This study included a review of the practice of continued operation with a degraded seal in the case of PWR plants with Byron Jackson reactor coolant pumps. Specific factors were identified which should be addressed in order to safety manage operation of a reactor coolant pump with indications of a degrading seal

  6. Modification of reactor installation in the Genkai nuclear power plant No. 1 of Kyushu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    The Nuclear Safety Commission recognized the adequacy concerning the inquiry which was offered from the Minister of International Trade and Industry on July 25, 1979, following the safety evaluation in the Ministry of International Trade and Industry, and decided to submit a report to the Minister of International Trade and Industry on July 26, 1979, about the modification of reactor installation in the Genkai nuclear power plant No. 1 of the Kyushu Electric Power Company, Inc. This is concerned to the application which was made from the president of the Kyushu Electric Power Company, Inc., to the Minister of International Trade and Industry on July 24, 1979. The content of the modification is to add a control circuit which is actuated by the signal of abnormal low pressure in a reactor to the circuit of actuating the emergency core cooling system of the plant. The influences on the safety protection system by the addition of the circuit transmitting safety injection signal and by the additions of an interlock circuit preventing the misoperation of pressurizer spray and of a block circuit of safety injection signal in case of the abnormal low pressure in a reactor were evaluated. The effects on the function and characteristics of the emergency core cooling system due to the addition of the control circuit were investigated, and it was recognized by the analysis that there is no effect in the pipe ruptures of both small and large scales. (Nakai, Y.)

  7. Sealing, especially of dropped ceiling of cubide where main circulating pump of nuclear reactor is installed

    International Nuclear Information System (INIS)

    Paucek, V.

    1980-01-01

    The sealing of the dropped ceiling of the cubicle for main circulating pump installation consists of a reinforcing ring in the space of the pump installation and the top annulus of biological shielding whose inner diameter is smaller than the outer diameter of the bottom biological shielding annulus mounted onto the pump body. The sealing comprises a vertically slidable support ring provided on its underside with an outer ring insert and an outer splice bar for functional gap formation. Slidably mounted in the gap is a guide annular plate tightly attached by means of an inner splice bar and bolts to the bottom biological shielding annulus. Spacers are provided between the reinforcing ring underside and the support ring top surface. (B.S.)

  8. After-installation service, a contribution to enhanced economic efficiency of reactors

    International Nuclear Information System (INIS)

    Bilger, H.

    1996-01-01

    After-installation service agreements are concluded in general for the following plant systems or tasks: power operation, inspection and repair during outages, plant enhancements (retrofitting), instrumentation and control (software). The paper gives various examples selected from power plant practice in Germany, showing that service contracts are a major factor contributing to maintaining economic efficiency, or enhancing it. Examples of nuclear power plant management abroad relying on service contracts are also given (USA, France, Japan). (orig./HP) [de

  9. On-off controller for installation to test the pressurized water reactor material

    International Nuclear Information System (INIS)

    Zauq, M.H.

    1982-05-01

    This report describes the design of an ON-OFF controller based on the 6800 microprocessor in its assembly language and its interfacing with its environment (sensors, periphery, etc). The controller is meant to control the temperature and the pressure inside an experimental chamber in which the material under test is placed. The ''Design basis accident'' conditions (e.g., LOCA) for a pressurized water reactor are simulated in the experimental chamber [fr

  10. Installation and method for handling fuel assemblies of fast nuclear reactors

    International Nuclear Information System (INIS)

    Aubert, Michel; Renaux, Charley.

    1982-01-01

    This invention concerns an installation and a method for handling the assemblies which makes it possible to have a large revolving plug smaller in diameter than that of the presently known solutions. This large, coaxial to the core, revolving plug has a handling arm enabling a fraction of the assemblies to be reached and deposited in a handling well. Through a small offset revolving plug the remainder of the assemblies can be reached and deposited in a pick-up well accessible to the arm of the large revolving plug [fr

  11. Outline of design, manufacturing and installation experience of pressure vessel structure for the prototype heavy water moderated boiling light water cooled reactor 'FUGEN'

    International Nuclear Information System (INIS)

    Shibato, Eizo; Oguchi, Isao; Kishi, Toshikazu; Kitagawa, Yuji

    1977-01-01

    After component installation completed in June 1977 and various functional tests to be conducted later, the prototype heavy water moderated, boiling light water cooled reactor ''FUGEN'' is scheduled to reach first criticality in March 1978. Since the pressure vessel of ''FUGEN'' is completely different from that of a light water reactor in structure and materials, through research and development work was carried out prior to fabrication and construction. Based on these studies, installation of the actual pressure vessel was completed. Functional tests are now under way. This article describes examples in which our research and development results are reflected on design, manufacture, and installation of the pressure vessel. Also it introduces noteworthy achievements relevant to production techniques in manufacture and installation. (auth.)

  12. Remote inspection system for components installed inside a primary containment vessel of a boiling water reactor

    International Nuclear Information System (INIS)

    Shimizu, Katsutoshi; Kawai, Katsumi; Ito, Takahiko; Hashimoto, Yuji; Tomizawa, Fumio.

    1983-01-01

    A remote operation type monitoring system was developed to always enable the watching of the condition of the main equipment installed in the containment vessels of BWRs. It comprises four inspection vehicles suspended by a monorail and pulled with trolley chain, coaxial cables for signal transmission and power supply, and control system. On the inspection vehicles, a television camera, a thermometer, a microphone and a radiation dose rate meter are installed. The performance of the system was confirmed at 60 deg C for several months. Thereafter, the field test was carried out in the Tokai No. 2 Power Station, Japan Atomic Power Co., from December, 1980, to September, 1981. By the continuous monitoring and grasp of operational condition, the preventive maintenance and the improvement of the rate of operation can be expected. Also it is desirable in view of the reduction of radiation exposure of operators. The mechanization of and the labor saving in inspection and maintenance works is necessary because skilled workers will be short. The design and the composition of the system and its tests are reported. (Kako, I.)

  13. Probe-holding apparatus for holding a probe for checking steam generator tubes particularly in a nuclear reactor installation

    International Nuclear Information System (INIS)

    Adamowski, A.; Gagny; Gallet, G.; Lhermitte, J.; Monne, M.; Vautherot, G.

    1984-01-01

    Probe-holding apparatus for holding a probe for checking steam generator tubes particularly in a nuclear reactor installation. The apparatus comprises a telescopic arm supported via a ball and socket joint from a support mounted in or near an access aperture in a chamber at one end of the steam generator. A probe guide is carried by a carriage pivotally mounted at the other end of the telescopic arm. The carriage includes an endless belt having a series of spaced projections which engage into the ends of the tubes, the projections being spaced by a distance equal to the tube pitch or a multiple thereof. The belt is driven by a stepping motor in order to move the carriage and place the probe guide opposite different ones of the tubes

  14. Surface and ground waters evaluation at Brazilian Multiproposed Reactor installation area

    International Nuclear Information System (INIS)

    Stellato, Thamiris B.; Silva, Tatiane B.S.C.da; Soares, Sabrina M.V.; Faustino, Mainara G.; Marques, Joyce R.; Oliveira, Cintia C. de; Monteiro, Lucilena R.; Pires, Maria A.F.; Cotrim, Marycel E.B.

    2017-01-01

    This study evaluates six surface and ground waters physicochemical characteristics on the area of the future Brazilian Multipurpose Reactor (RMB), at Iperó/SP. One of the main goals is to establish reference values for future operation monitoring programs, as well as for environmental permits and regulation. Considering analyzed parameters, all collection points presented values within CONAMA Resolution 396/08 and 357/05 regulation limits, showing similar characteristics among collection points.Only two points groundwater (RMB-005 and RMB-006) presented higher alkalinity, total dissolved solids and conductivity. The studied area was considered in good environmental conservation condition, as far as water quality is concerned. (author)

  15. Inquiry relating to modification of reactor installation of Hamaoka No. 2 nuclear power plant of Chubu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modification of reactor installation of the Hamaoka No. 2 nuclear power plant, Chubu Electric Power Company, Inc., on February 8, 1979, from the president of the company. After the safety evaluation in the Ministry of International Trade and Industry was finished, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on May 25, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on May 28, 1979. The modification of the reactor installation is the increase of spent fuel storage capacity from about 220% of in-core fuel at present to about 325%. The fundamental philosophy of the safety evaluation includes the following items; 1) the storage capacity of spent fuel is adequate, 2) the design is such that the criticality is prevented under any assumed condition, 3) the sufficient cooling capacity is kept for decay heat removal, 4) and others required for the safety. The contents of the safety examination for each philosophical item written above are presented. The increased spent fuel storage capacity is equivalent to the quantity produced in about eight years. The prevention of criticality in the spent fuel storage is carefully practiced by putting fuel assemblies in the stainless steel racks with large neutron absorption cross section and locating spent fuel assemblies at the proper distances. The effective multiplication factor is less than 0.95 at the most severe arrangement in the fuel pool. The water temperature in the pool is less than 65 deg C at about 325% core storage by operating the spent fuel pool water cooling system. The spent fuel storage racks are designed as the A class aseismatic structure. (Nakai, Y.)

  16. Concerning partial revision of regulations on installation, operation, etc., of nuclear reactor, etc., for test and research

    International Nuclear Information System (INIS)

    1989-01-01

    To enforce the rules relating to nuclear material protection at nuclear power facilities as covered by the Nuclear Reactor Control Law, which was revised in May last year, orders should be issued by the Prime Minister's Office (or Ministry of International Trade and Industry) to specify the following matters: (1) measures to be carried out by the operators of nuclear facilities to ensure the protection of specially designated nuclear fuel materials, (2) procedures for the application for permission as covered by nuclear material protection rules, and (3) requirements for managers in charge of nuclear material protection. The new regulations should cover the following: (1) rules relating to the business of refining of nuclear fuels, and raw materials for nuclear substances, (2) rules relating to the business of processing of nuclear fuels, (3) rules relating to the installation, operation, etc., of nuclear reactor, etc., for test and research, (4) rules relating to the business of reprocessing of spent fules, (5) rules relating to the business of management of nuclear fuels or waste contaminated with nuclear fuels, and (6) rules relating to the application of nuclear fuels. (N.K)

  17. The cryogenic installations for irradiation in the reactors Melusine and Siloe; Les installations cryogeniques pour irradiations des reacteurs Melusine et Siloe

    Energy Technology Data Exchange (ETDEWEB)

    Bochirol, L; Le Calvez, J; Doulat, J; Verdier, J; Lacaze, A; Weil, L [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    The study of defects created in solids by irradiation is of considerable fundamental and practical interest. Low temperature irradiation allows defects to be obtained in their simplest 'primary' state, not being then annihilated or rearranged by thermal motion. In-pile irradiation at low temperature raises a number of technical problems connected to 1) the necessary refrigeration power which may be considerable, 2) chemical processes which may occur under irradiation, 3) the lack of space in a reactor. Furthermore the necessity that all the irradiation and subsequent measurements be done without reheating the samples demands continuous and reliable working of the irradiation device and its being designed so as to permit removal of the samples in the cold condition or their measurement and controlled annealing 'in situ'. The way in which these problems have been solved in Grenoble for irradiation devices at 78 deg. K, 28 deg. K and 4 deg. K in the swimming-pool reactors Melusine and Siloe is described. Some operation results are given about the liquid nitrogen rig, called mark A, which has worked for several years in Melusine. In particular certain observations about chemical reactions which may occur in impure liquid nitrogen under radiation are made. The liquid nitrogen rig, called mark B, which has just been installed in the Siloe reactor, is described with some detail. The essential features of this apparatus are that irradiation can be performed in higher fluxes with it than with the former one, and that its operation is made much easier by a design which allows the samples to be introduced and removed without any disconnection of the apparatus. A liquid hydrogen loop, which has worked for one year in the Melusine reactor, is then analysed. An entirely closed hydrogen refrigerating circuit provides the coldness to the irradiation enclosure, which contains neon. Owing to this solution, the samples may be recovered in the cold condition without hydrogen being

  18. Determination of permissible doses under the provisions of the regulations on installation and operation of reactors for power generation

    International Nuclear Information System (INIS)

    1979-01-01

    The determination is defined under the regulations on installation and operation of reactors for power generation. In the controlled area exterior radiation dose shall be 30 mili-rem for a week by the Minister of International Trade and Industry. The concentrations of radioactive materials in the air or under the water shall be permissible concentrations specified for the employees multiplied by 0.75 in average for a week. The densities of radioactive materials on the surface of the things contaminated by such materials shall be 1/10 of permissible surface densities stipulated in the table attached. Permissible exposure dose outside the inspected surrounding area is 0.5 rem for a year. Permissible surface densities are included in the table attached. Permissible accumulative dose for the employees is the figure (unit rem) calculated by the formula D = 5(N-18), when D means permissible accumulative dose and N number of the age. Permissible exposure dose is 3 rem for 3 months for the employees, 1.5 rem for a year for persons other than the employees and 12 rem for the urgent work. Permissible concentrations are defined in detail for the employees and outside the inspected surrounding area. Calculation of exposure dose in the case of interior exposure is particularly provided for. (Okada, K.)

  19. RELAP5-3D version 4.0.3: installation and tests for applications to space reactors

    Energy Technology Data Exchange (ETDEWEB)

    Lobo, Paulo D.C.; Braz Filho, Francisco A.; Borges, Eduardo M.; Guimaraes, Lamartine N.F., E-mail: plobo.a@uol.com.br, E-mail: fbraz@ieav.cta.br, E-mail: eduardo@ieav.cta.br, E-mail: guimarae@ieav.cta.br [Instituto de Estudos Avancados (IEAv), Sao Jose dos Campos, SP (Brazil); Sabundjian, Gaiane, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    To attend the TERRA project (Tecnologia de Reatores Rapidos Avancados), currently conducted by the Nuclear Energy Division (ENU) of the IEAv, this work presents the RELAP5-3D, Version 4.0.3, prepared in July 12, 2012, also known as r3d403is, received recently by the IEAv from the Idaho National Laboratory (INL). This version of RELAP5-3D is configured for the International User Group source Code Group and is developed and maintained at the INL for the US Department of Energy. RELAP5-3D, the latest in the series of RELAP5 codes, is a highly generic code that, in addition to calculating the behavior of a reactor coolant system during a transient, can be used for simulation of a wide variety of hydraulic and thermal transients in both nuclear and nonnuclear systems involving mixtures of vapor, liquid, noncondensable gases, and nonvolatile solute. Enhancements include all features and models previously available in the ATHENA configuration version of the code which are as follows: addition of new work fluids and a magneto-hydrodynamic mode. Following the instructions from the README file, the RELAP5-3D, version 4.0.3 was installed creating the necessaries subdirectories, by using the LINUX platform and applying both Intel Fortran 95 and C-language compilers. Many input examples were executed and the same results were observed as compared to the received documentation. A sample of the Edwards-O'Brien test was evaluated to verify if the code could simulate a LOCA type accident properly. The test executed by the RELAP5-3D demonstrated good agreement with test data including a new output involving the mass flow during the test. (author)

  20. RELAP5-3D version 4.0.3: installation and tests for applications to space reactors

    International Nuclear Information System (INIS)

    Lobo, Paulo D.C.; Braz Filho, Francisco A.; Borges, Eduardo M.; Guimaraes, Lamartine N.F.; Sabundjian, Gaiane

    2013-01-01

    To attend the TERRA project (Tecnologia de Reatores Rapidos Avancados), currently conducted by the Nuclear Energy Division (ENU) of the IEAv, this work presents the RELAP5-3D, Version 4.0.3, prepared in July 12, 2012, also known as r3d403is, received recently by the IEAv from the Idaho National Laboratory (INL). This version of RELAP5-3D is configured for the International User Group source Code Group and is developed and maintained at the INL for the US Department of Energy. RELAP5-3D, the latest in the series of RELAP5 codes, is a highly generic code that, in addition to calculating the behavior of a reactor coolant system during a transient, can be used for simulation of a wide variety of hydraulic and thermal transients in both nuclear and nonnuclear systems involving mixtures of vapor, liquid, noncondensable gases, and nonvolatile solute. Enhancements include all features and models previously available in the ATHENA configuration version of the code which are as follows: addition of new work fluids and a magneto-hydrodynamic mode. Following the instructions from the README file, the RELAP5-3D, version 4.0.3 was installed creating the necessaries subdirectories, by using the LINUX platform and applying both Intel Fortran 95 and C-language compilers. Many input examples were executed and the same results were observed as compared to the received documentation. A sample of the Edwards-O'Brien test was evaluated to verify if the code could simulate a LOCA type accident properly. The test executed by the RELAP5-3D demonstrated good agreement with test data including a new output involving the mass flow during the test. (author)

  1. CSNI collective statement on support facilities for existing and advanced reactors. The function of OECD/Nea joint projects Nea committee on the safety of nuclear installations (CSNI)

    International Nuclear Information System (INIS)

    2008-01-01

    The NEA Committee on the Safety of Nuclear Installations (CSNI) has recently completed a study on the availability and utilisation of facilities supporting safety studies for current and advanced nuclear power reactors. The study showed that significant steps had been undertaken in the past several years in support of safety test facilities, mainly by conducting multinational joint projects centered on the capability of unique test facilities worldwide. Given the positive experience of the safety research projects, it has been recommended that efforts be made to prioritize technical issues associated with advanced (Generation IV) reactor designs and to develop options on how to efficiently obtain the necessary data through internationally co-ordinated research, preparing a gradual extension of safety research beyond the needs set by currently operating reactors. This statement constitutes a reference for future CSNI activities and for safety authorities, R and D centres and industry for internationally co-ordinated research initiatives in the nuclear safety research area. (author)

  2. Nuclear steam supply system and method of installation

    International Nuclear Information System (INIS)

    Tower, S.N.; Christenson, J.A.; Braun, H.E.

    1989-01-01

    This patent describes a method of providing a nuclear reactor power plant at a predetermined use site accessible by predetermined navigable waterways. The method is practiced with apparatus including a nuclear reactor system. The system has a nuclear steam-supply section. The method consists of: constructing a nuclear reactor system at a manufacturing site remote from the predetermined use site but accessible to the predetermined waterways for transportation from the manufacturing site to the predetermined use site, the nuclear reactor system including a barge with the nuclear steam supply section constructed integrally with the barge. Simultaneously with the construction of the nuclear reactor system, constructing facilities at the use site to be integrated with the nuclear reactor system to form the nuclear-reactor power plant; transporting the nuclear reactor system along the waterways to the predetermined use site; at the use site joining the removal parts of the altered nuclear reactor system to the remainder of the altered nuclear reactor system to complete the nuclear reactor system; and installing the nuclear reactor system at the predetermined use site and integrating the nuclear reactor system to interact with the facilities constructed at the predetermined use site to form the nuclear-reactor power plant

  3. Flow measurements in the core of the FRJ-2 research reactor after the installation of flow regulators in the locating bushes in the grid and investigation of the consequences for the safety of reactor operation

    International Nuclear Information System (INIS)

    Wolters, J.P.

    1975-04-01

    Early in June, 1974, radial flow regulators were installed in the locating bushes in the grid of the FRJ-2 reactor in order to reduce the flow irregularities in certain positions and thus to mobilize additional safety reserves. The success of these measures was tested by flow measurements in all 25 fuel element positions. The results are presented in this paper, their consequences for safety engineering are analyzed, and a flexible inlet temperature is proposed. (orig./AK) [de

  4. Modular nuclear reactor for a land-based power plant and method for the fabrication installation and operation thereof

    International Nuclear Information System (INIS)

    Craig, E. R.; Blumberg, B. Jr.

    1985-01-01

    A self-contained modular nuclear reactor which can be prefabricated at a factory location, nuclear-certified at the factory, transported to a field location for final assembly and connection to a large-scale electric-power generating facility. The modular reactor includes a prefabricated nuclear heat supply module and a plurality of shell segments which can be assembled about the heat supply module and which provide a form for the pouring and curing of a cementatious biological shield about the heat supply module. The modular reactor includes passive shutdown heat removal systems sufficient to render the reactor safe in an emergency. A large-scale power plant arrangement is disclosed which incorporates a plurality of the modular reactors

  5. Procedure for qualification of electric equipment installed in containments for pressurized water reactors subject to accident conditions

    International Nuclear Information System (INIS)

    1991-11-01

    This generic norm is usable for electrical equipment installed in containment building of PWR subject to accidental conditions. She defines the qualification methods and the general rules usable for the test specifications of qualification for these materials

  6. Reliability database of IEA-R1 Brazilian research reactor: Applications to the improvement of installation safety

    International Nuclear Information System (INIS)

    Oliveira, P.S.P.; Tondin, J.B.M.; Martins, M.O.; Yovanovich, M.; Ricci Filho, W.

    2010-01-01

    In this paper the main features of the reliability database being developed at Ipen-Cnen/SP for IEA-R1 reactor are briefly described. Besides that, the process for collection and updating of data regarding operation, failure and maintenance of IEA-R1 reactor components is presented. These activities have been conducted by the reactor personnel under the supervision of specialists in Probabilistic Safety Analysis (PSA). The compilation of data and subsequent calculation are based on the procedures defined during an IAEA Coordinated Research Project which Brazil took part in the period from 2001 to 2004. In addition to component reliability data, the database stores data on accident initiating events and human errors. Furthermore, this work discusses the experience acquired through the development of the reliability database covering aspects like improvements in the reactor records as well as the application of the results to the optimization of operation and maintenance procedures and to the PSA carried out for IEA-R1 reactor. (author)

  7. Patterns identification in supervisory systems of nuclear reactors installations and gas pipelines systems using self-organizing maps

    International Nuclear Information System (INIS)

    Doraskevicius Junior, Waldemar

    2005-01-01

    Self-Organizing Maps, SOM, of Kohonen were studied, implemented and tested with the aim of developing, for the energy branch, an effective tool especially for transient identification in nuclear reactors and for gas pipelines networks logistic supervision, by classifying operations and identifying transients or abnormalities. The digital system for the test was developed in Java platform, for the portability and scalability, and for belonging to free development platforms. The system, executed in personal computers, showed satisfactory results to aid in decision taking, by classifying IRIS (International Reactor Innovative and Secure) reactor operation conditions (data from simulator) and by classifying Southeast (owner: TRANSPETRO - Brazil) gas pipeline network. Various adaptations were needed for such business, as new topologies for the output layer of artificial neural network and particular preparation for the input data. (author)

  8. Inquiry relating to modifications of reactor installation in Ikata No. 1 and 2 nuclear power plants of Shikoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Ikata No. 1 and 2 nuclear power plants of the Shikoku Electric Power Company, Inc., on February 13, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the Atomic Energy Safety Commission (AESC) on June 15, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for No. 1 plant and the modification of driving mechanism from the roller nut type to the magnetic jack type for the control rod cluster for adjusting power distribution in the No. 2 plant. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. Relating to the driving mechanism for the control rod cluster adjusting power distribution, the driving speed is not modified and the reliability is kept by carrying out the continuous operation test and the electric power black out test as the demonstration test. The magnetic jack type mechanism has the locking device to prevent reactor tripping at the time of electric power black out, and the cluster is held at the location where the cluster existed at the time of black out. (Nakai, Y.)

  9. Evaluating usability of the Halden Reactor Large Screen Display. Is the Information Rich Design concept suitable for real-world installations?

    International Nuclear Information System (INIS)

    Braseth, Alf Ove

    2013-01-01

    Large Screen Displays (LSDs) are beginning to supplement desktop displays in modern control rooms, having the potential to display the big picture of complex processes. Information Rich Design (IRD) is a LSD concept used in many real-life installations in the petroleum domain, and more recently in nuclear research applications. The objectives of IRD are to provide the big picture, avoiding keyhole related problems while supporting fast visual perception of larger data sets. Two LSDs based on the IRD concept have been developed for large-scale nuclear simulators for research purposes; they have however suffered from unsatisfying user experience. The new Halden Reactor LSD, used to monitor a nuclear research reactor, was designed according to recent proposed Design Principles compiled in this paper to mitigate previously experienced problems. This paper evaluates the usability of the Halden Reactor LSD, comparing usability data with the replaced analogue panel, and data for an older IRD large screen display. The results suggest that the IRD concept is suitable for use in real-life applications from a user experience point of view, and that the recently proposed Design Principles have had a positive effect on usability. (author)

  10. Modification of reactor installation in the Takahama nuclear power plants No.1 and No.2 of Kansai Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    The Nuclear Safety Commission recognized the adequacy concerning the inquiry which was offered from the Minister of International Trade and Industry on July 24, 1979, following the safety evaluation in the Ministry of International Trade and Industry, and decided to submit a report to the Minister of International Trade and Industry on July 26, 1979, about the modification of reactor installation in the Takahama nuclear power plants No. 1 and No. 2 of the Kansai Electric Power Company, Inc. This is concerned to the application which was made from the president of the Kansai Electric Power Company, Inc., to the Minister of International Trade and Industry on July 23, 1979. The content of the modification is to add a control circuit which is actuated by the signal of abnormal low pressure in a reactor to the circuit of actuating the emergency core cooling system of the plant. The influences on the safety protection system by the addition of the circuit for transmitting safety injection signal and by the additions of an interlock circuit preventing the misoperation of pressurizer spray and of a block circuit of safety injection signal in case of the abnormal low pressure in a reactor were evaluated. The effects on the function and characteristics of the emergency core cooling system due to the addition of the control circuit were investigated, and it was recognized by the analysis that there is no effect in the pipe ruptures of both small and large scales. (Nakai, Y.)

  11. Examination policy concerning the additional installation of No. 3 and No. 4 reactors in Takahama Nuclear Power Station and No. 3 and No. 4 reactors in Fukushima No. 2 Nuclear Power Station

    International Nuclear Information System (INIS)

    1980-01-01

    The Nuclear Safety Commission decided the annual examination policy on the modification of reactor installation in Takahama Nuclear Power Station to construct No. 3 and No. 4 reactors inquired under date of November 26, 1979, by the Minister of International Trade and Industry, so that the examination results of the accident in Three Mile Island nuclear power station are reflected to the examination for the purpose of improving reactor safety. The examination results of the accident in Three Mile Island power station are being investigated by the Committee on Examination of Reactor Safety, based on the policy shown in ''On the second report of the special committee examining the accident in a nuclear power station in the U.S.'' determined by the Nuclear Safety Commission under date of September 13, 1979. Though the Committee will further clarify the past guideline about the items concerning the criteria, design and operation management, the Committee decided the tentative policy to reflect it to safety examination. Further, a table is attached, in which 52 items to be reflected to the security measures are classified from the viewpoint of necessity to reflect them to the final examination. This table includes 13 items of criteria and examination, 7 items related to design, 10 items related to operation management, 10 antidisaster items, and 12 items related to safety research. (Wakatsuki, Y.)

  12. Installation and development of neutron radiography in the nuclear reactor (IEAR-1) of the Instituto de Energia Atomica, Brazil

    International Nuclear Information System (INIS)

    Fuga, R.

    1979-01-01

    Investigations on the field of Neutron Radiography have been performed at the IEAR-1, swimming pool reactor utilizing a collimated neutron beam and the so-called photographic transfer method as a mean of detection. The test object (sample) is placed between the neutron source (reactor core) and the gold foil. The acitivity of its different points is the inverse measure of the neutrons absorbed in the test sample at the corresponding points. The activity distribution on the gold foil is determined again by exposing it to an X-ray film. A multichannel type collimator consisting of an assemblage of stainless steel tubes inside an aluminium mantle (tube) was used as a direction beam selector. Improvements have been introduced in respect to the reduction of angular divergence and neutron scattering. To improve further the quality of the radiographs another collimator type has been developed using boric acid as a neutron absorber and moderator. Flux measurements by means of gold foil activation at reactor positions of interest were necessary to eliminate errors originating of different neutron flux values. The dependence of film darkening upon the neutron flux and other factors have been discussed. Finally neutron-and gama-radiographs of the same objects were evaluated in comparison. (author) [pt

  13. Considerations about decommissioning of the IEA-R1 research reactor and the future of its installations after shutdown; Consideracoes sobre o descomissionamento do reator de pesquisa IEA-R1 e futuro de suas instalacoes apos o seu desligamento

    Energy Technology Data Exchange (ETDEWEB)

    Frajndlich, Roberto

    2014-07-01

    The IEA-R1 Nuclear Research Reactor, in operation since 1957, in the Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), is one of the oldest research reactors in the world. However at some point in time in the future, as example of the other reactors, it will be shutdown definitively. Before that time actually arrives, the operational organization needs to plan the future of its installations and define the final destination of equipment and radioactive as well as non-radioactive material contained inside the installations. These and other questions should be addressed in the so called Preliminary decommissioning plan of the installation, which is the subject of this work. The work initially presents an over view about the theme and defines the general and specific objectives describing, in succession, the directions that the operating organization should consider for the formulation of a decommissioning plan. The present structure of the Brazilian nuclear sector emphasizing principally the norms utilized in the management of radioactive waste is also presented. A description of principle equipment of the IEA-R1 reactor which constitutes its inventory of radioactive and non-radioactive material is given. The work emphasizes the experience of the reactor technicians, acquired during several reforms and modifications of the reactor installations realized during its useful life time. This experience may be of great help for the decommissioning in the future. An experiment using the high resolution gamma spectrometric method and computer calculation using Monte Carlo theory were performed with the objective of obtaining an estimate of the radioactive waste produced from dismantling of the reactor pool walls. The cost of reactor decommissioning for different choices of strategies was determined using the CERREX code. Finally, a discussion about different strategies is presented. On the basis of these discussions it is concluded that the most advantageous

  14. Inquiry relating to modifications of reactor installation in Genkai No. 1 and 2 nuclear power plants of Kyushu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Genkai No. 1 and 2 nuclear power plants, Kyushu Electric Power Company, Inc., on February 27, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on June 15, 1979 from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for each plant, the new establishment of a miscellaneous solid waste incinerator which is common to both plants, and the enlargement of a solid waste storage which is also common to both plants. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. The miscellaneous solid waste incinerator building is designed as the B class aseismatic structure and also as the controlled area with adequate shielding and ventilating facilities. The decontamination factor of the incinerator facility is more than 10 5 , and the necessary monitoring system is provided in the building. Concerning the solid waste storage, the additional storage area is about 1600 m 2 , and the storage capacity is about ten years quantity. This building is designed as the B class aseismatic structure. (Nakai, Y.)

  15. Experimental optimization of temperature distribution in the hot-gas duct through the installation of internals in the hot-gas plenum of a high-temperature reactor

    International Nuclear Information System (INIS)

    Henssen, J.; Mauersberger, R.

    1990-01-01

    The flow conditions in the hot-gas plenum and in the adjacent hot-gas ducts and hot-gas pipes for the high-temperature reactor project PNP-1000 (nuclear process heat project for 1000 MW thermal output) have been examined experimentally. The experiments were performed in a closed loop in which the flow model to be analyzed, representing a 60deg sector of the core bottom of the PNP-1000 with connecting hot-gas piping and diverting arrangements, was installed. The model scale was approx. 1:5.6. The temperature and flow velocity distribution in the hot-gas duct was registered by means of 14 dual hot-wire flowmeters. Through structural changes and/or the installation of internals into the hot-gas plenum of the core bottom offering little flow resistance coolant gas temperature differentials produced in the core could be reduced to such an extent that a degree of mixture amounting to over 80% was achieved at the entrance of the connected heat exchanger systems. Thereby the desired goal of an adequate degree of mixture of the hot gas involving an acceptable pressure loss was reached. (orig.)

  16. Preliminary Assessment of the Impact on Reactor Vessel dpa Rates Due to Installation of a Proposed Low Enriched Uranium (LEU) Core in the High Flux Isotope Reactor (HFIR)

    Energy Technology Data Exchange (ETDEWEB)

    Daily, Charles R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-10-01

    An assessment of the impact on the High Flux Isotope Reactor (HFIR) reactor vessel (RV) displacements-per-atom (dpa) rates due to operations with the proposed low enriched uranium (LEU) core described by Ilas and Primm has been performed and is presented herein. The analyses documented herein support the conclusion that conversion of HFIR to low-enriched uranium (LEU) core operations using the LEU core design of Ilas and Primm will have no negative impact on HFIR RV dpa rates. Since its inception, HFIR has been operated with highly enriched uranium (HEU) cores. As part of an effort sponsored by the National Nuclear Security Administration (NNSA), conversion to LEU cores is being considered for future HFIR operations. The HFIR LEU configurations analyzed are consistent with the LEU core models used by Ilas and Primm and the HEU balance-of-plant models used by Risner and Blakeman in the latest analyses performed to support the HFIR materials surveillance program. The Risner and Blakeman analyses, as well as the studies documented herein, are the first to apply the hybrid transport methods available in the Automated Variance reduction Generator (ADVANTG) code to HFIR RV dpa rate calculations. These calculations have been performed on the Oak Ridge National Laboratory (ORNL) Institutional Cluster (OIC) with version 1.60 of the Monte Carlo N-Particle 5 (MCNP5) computer code.

  17. Change in plan for installation of nuclear reactor in Genkai Nuclear Power Plant of Kyushu Electric Power Co., Inc. (change in plan for No.3 and No.4 nuclear reactor facilities) (report)

    International Nuclear Information System (INIS)

    1987-01-01

    This report, compiled by the Nuclear Safety Commission to be submitted to the Minister of International Trade and Industry, deals with studies on a proposed change in the plan for the installation of nuclear reactors in the Genkai Nuclear Power Plant of Kyushu Electric Power Co., Inc. (change in the plan for the No.3 and No.4 nuclear reactor facilities). The conclusions of and principles for the examination and evaluation are described first. The studies carried out are focused on the safety of the facilities, and it is concluded that part of the proposed change is appropriate with respect to the required technical capability and that part of the change will not have adverse effects on the safety design of the facilities. The examination of the safety design of the reactor facilities cover the reactivity control, new material for the steam generator, design of chemical and volume control systems, design of liquid waste treatment facilities, integration of all confinement vessel spray rings, and design of the diesel power generator. It is confirmed that all of them can meet the safety requirements. Studies and analyses are also made of the emission of radiations to the surrounding environment, abnormal transient changes during operations, and possible accidents. (Nogami, K.)

  18. Characterization of the neutron flow for the implementation of an experimental analysis installation for rapid gamma activation in the Argentine Research Reactor RA-6

    International Nuclear Information System (INIS)

    Henriquez, C.; Gennuso, G.

    2000-01-01

    This is the final work to obtain a Diploma on Specialization in Application of Nuclear Technological Energy, carried out at the Research Reactor RA-6, from March to December 1999. Different work has been realized on the Tangential Tube N of the 500 KW Argentine RA-6 research reactor, in order to add a new technique to the present existing analytical methods. This Prompt Gamma Neutron Activation Analysis technique (PGNAA) requires a beam of collimated thermal neutrons, a lowest possible gamma radiation, and a thermal component of the biggest possible cadmium rate. It also must have a high resolution detection system for the measurement of the gamma radiation emitted after the capture of the neutron produced in the study sample. Continuing with the facility's technical requirements, a collimator was installed inside the N passing tube, in order to concentrate the neutrons coming from the nuclear core and also to compensate possible losses during the path. This collimator is 440mm long and 200 mm in diameter and consists of lead and steel cylinders with different size holes on the inside, so that it can deliver a 50 mm diameter beam of thermal collimated neutrons. Two 100 mm thick bismuth filters are inside the passing tube, to reduce the gamma component inside de beam, coming from the reactor core. This work aims to the characterization of the thermal and epithermal component of the neutron beam in the collimator and at the exit of it , and also to prove experimentally that the collimator achieves the technical specifications for which it was designed and built, specifically by verifying its functioning (degree of convergence of the beam obtained). On the other hand, it is necessary to learn about the PGNAA technique in order to define the technical requirements for its adequate operation. (author)

  19. Project, installation and operational tests of a pneumatic system for the IEA-R1 reactor materials

    International Nuclear Information System (INIS)

    Fernando, Alberto de Jesus; Madi Filho, Tufic

    2009-01-01

    Pneumatic Transfer Systems (PTS) are equipment broadly and world widely used for the transport, movement and transfer of diverse types of materials, objects and cargo between two or more environments, near or distant from each other [1]. Due to their flexibility and quickness, the system application is present in several areas, such as medicine (hospitals and clinic analyses laboratories); industry (automobile, metallurgy, iron-making. chemical, food production) commerce (gasoline stations, cinemas, supermarkets, banks, tolls, on-line commerce, casinos); public service (public institutions, courts). In the nuclear field, the PTS has, also, a vast application, highlighting its use in the radioisotope and radiopharmaceuticals of short half life production, such as 67 Ga, 201 Tl, 18F and 123 I-ultra pure. The development of this work is directed to the application of the Pneumatic Transfer System in transport and transfer of materials that will be irradiated in the IEA-R1 reactor, located in the Institute of Energetic and Nuclear Research, IPEN/CNEN-SP, for application of the Neutron Activation Analysis (NAA). (author)

  20. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

    Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

  1. Reactor

    International Nuclear Information System (INIS)

    Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

    1979-01-01

    Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

  2. Concerning modification of plan for installation of reactors (addition of No.4 reactor and modification of No.1, No.2 and No.3 reactor facilities) at Hamaoka nuclear power plant of Chubu Electric Power Co., Ltd. (reply to inquiry)

    International Nuclear Information System (INIS)

    1988-01-01

    The Nuclear Safety Commission on Oct. 22, 1987 directed the Nuclear Reactor Safety Expert Group to carry out a study on it, made deliberations after receiving a report from the Group on Jun. 28, and submitted the findings to the Minister of International Trade and Industry on Jul. 14. The study and deliberations were intended to determine the conformity of the modifications to the applicable laws relating to control of nuclear material, nuclear fuel and nuclear reactor. The investigation on the location covered the site conditions, geology, seismic environment, meteorology, hydrology, and social environment. The investigations on the safety design of the reactor facilities addressed the design of the overall reactor facilities, anti-earthquake design, and design of other equipment including reactor core, fuel equipment, monitors, reactivity controllers, safety protection equipment, and emergency core cooler. Other investigations included exposure evaluation and accident analysis. It was concluded that the modifications would not have adverse effects on the safety of the reactor facilities. (Nogami, K.)

  3. Civilian protection and Britain's commercial nuclear installations

    International Nuclear Information System (INIS)

    1981-01-01

    The subject is treated as follows: initial conclusions (major nuclear attack on military installations; nuclear attack including civil nuclear targets; conventional attack on civil nuclear installations); nature of nuclear weapons explosions and power reactor releases (general; dose effects and biologically significant isotopes; nuclear weapon effects; effect of reactors and other fuel-cycle installations in a thermonuclear area; implications of reactor releases due to conventional attack, sabotage, civil disorder or major accident). (U.K.)

  4. Bio-alteration of metallurgical wastes by Pseudomonas aeruginosa in a semi flow-through reactor.

    Science.gov (United States)

    van Hullebusch, Eric D; Yin, Nang-Htay; Seignez, Nicolas; Labanowski, Jérôme; Gauthier, Arnaud; Lens, Piet N L; Avril, Caroline; Sivry, Yann

    2015-01-01

    Metallurgical activities can generate a huge amount of partially vitrified waste products which are either landfilled or recycled. Lead Blast Furnace (LBF) slags are often disposed of in the vicinity of metallurgical plants, and are prone to weathering, releasing potentially toxic chemical components into the local environment. To simulate natural weathering in a slag heap, bioweathering of these LBF slags was studied in the presence of a pure heterotrophic bacterial strain (Pseudomonas aeruginosa) and in a semi-flow through reactor with intermittent leachate renewal. The evolution of water chemistry, slag composition and texture were monitored during the experiments. The cumulative bulk release of dissolved Fe, Si, Ca and Mg doubled in the presence of bacteria, probably due to the release of soluble complexing organic molecules (e.g. siderophores). In addition, bacterial biomass served as the bioadsorbent for Pb, Fe and Zn as 70-80% of Pb and Fe, 40-60% of Zn released are attached to and immobilized by the bacterial biomass. Copyright © 2014 Elsevier Ltd. All rights reserved.

  5. The insurance of nuclear installations

    International Nuclear Information System (INIS)

    Francis, H.W.

    1977-01-01

    A brief account is given of the development of nuclear insurance. The subject is dealt with under the following headings: the need for nuclear insurance, nuclear insurance pools, international co-operation, nuclear installations which may be insured, international conventions relating to the liability of operators of nuclear installations, classes of nuclear insurance, nuclear reactor hazards and their assessment, future developments. (U.K.)

  6. Decommissioning nuclear installations

    International Nuclear Information System (INIS)

    Dadoumont, J.

    2010-01-01

    When a nuclear installation is permanently shut down, it is crucial to completely dismantle and decontaminate it on account of radiological safety. The expertise that SCK-CEN has built up in the decommissioning operation of its own BR3 reactor is now available nationally and internationally. Last year SCK-CEN played an important role in the newly started dismantling and decontamination of the MOX plant (Mixed Oxide) of Belgonucleaire in Dessel, and the decommissioning of the university research reactor Thetis in Ghent.

  7. Questions for the nuclear installations inspectorate

    International Nuclear Information System (INIS)

    Conroy, C.; Flood, M.; MacRory, R.; Patterson, W.C.

    1976-01-01

    The responsibilities of the Nuclear Installations Inspectorate are considered, and the responsibilities of other bodies for (a) reprocessing and enrichment, and (b) security. Questions for the Nuclear Installations Inspectorate are then set out under the following heads: general (on such topics as vandalism, sabotage, threats, security, reactor incidents); magnox reactors; corrosion; advanced gas-cooled reactor; steam generating heavy water reactor; fast breeder reactor; reproces-sing and waste. Most of the questions are concerned with technical problems that have been reported or might possibly arise during construction or operation, affecting the safety of the reactor or process. (U.K.)

  8. Reactors

    DEFF Research Database (Denmark)

    Shah, Vivek; Vaz Salles, Marcos António

    2018-01-01

    The requirements for OLTP database systems are becoming ever more demanding. Domains such as finance and computer games increasingly mandate that developers be able to encode complex application logic and control transaction latencies in in-memory databases. At the same time, infrastructure...... engineers in these domains need to experiment with and deploy OLTP database architectures that ensure application scalability and maximize resource utilization in modern machines. In this paper, we propose a relational actor programming model for in-memory databases as a novel, holistic approach towards......-level function calls. In contrast to classic transactional models, however, reactors allow developers to take advantage of intra-transaction parallelism and state encapsulation in their applications to reduce latency and improve locality. Moreover, reactors enable a new degree of flexibility in database...

  9. Installing Omeka

    Directory of Open Access Journals (Sweden)

    Jonathan Reeve

    2016-07-01

    Full Text Available Omeka.net is a useful service for Omeka beginners, but there are a few reasons why you might want to install your own copy of Omeka. Reasons include: * Upgrades. By installing Omeka yourself, you can use the latest versions of Omeka as soon as they’re released, without having to wait for Omeka.net to upgrade their system. * Plugins and themes. You can install any plugin or theme you want, without being restricted to those provided by Omeka.net. * Customizations. You can buy a custom domain name, and customize your code to achieve your desired functionality. * Control. You have control over your own backups, and you can update the server yourself so that its security is always up-to-date. * Price. There are many low-cost Virtual Private Servers (VPSs now, some of which cost only $5 per month. * Storage. Many shared hosting providers now offer unlimited storage. This is useful if you have a large media library. In this tutorial, we’ll be entering a few commands on the command line. This tutorial assumes no prior knowledge of the command line, but if you want a concise primer, consult the Programming Historian introduction to BASH. There are other ways of installing Omeka, of course, some using exclusively GUI tools. Some hosting providers even offer “one-click installs” via their control panels. Many of those methods, however, will install older versions of Omeka which are then harder to upgrade and maintain. The method outlined below may not be the easiest way to install Omeka, but it will give you some good practice with using the command line, which is a skill that will be useful if you want to manually upgrade your install, or manually install other web frameworks. (For example, this installation method is very similar to WordPress’s “Five-Minute Install”. There are four steps to this process, and it should take about an hour.

  10. Fuel followed control rod installation at AFRRI

    International Nuclear Information System (INIS)

    Moore, Mark; Owens, Chris; Forsbacka, Matt

    1992-01-01

    Fuel Followed Control Rods (FFCRs) were installed at the Armed Forces Radiobiology Research Institute's 1 MW TRIGA Reactor. The procedures for obtaining, shipping, and installing the FFCRs is described. As part of the FFCR installation, the transient rod drive was relocated. Core performance due to the addition of the fuel followed control rods is discussed. (author)

  11. Extending reactor time-to-poison and reducing poison shutdown time by pre-shutdown power alterations

    Energy Technology Data Exchange (ETDEWEB)

    Kerr, Edward

    1963-10-15

    Manipulation of reactor power prior to shutdown and increasing the time- to-poison a sufficient amount to enable the required maintenance work to be completed and the reactor immediately restarted are discussed. The method employed in the NRU Reactor to gain the maximum timeto-poison with the least production loss is outlined. The method is based on intuition and is described by means of an analog of the iodine--xenon equations rather than the equations themselves. (C.E.S.)

  12. Modular reactor head shielding system

    International Nuclear Information System (INIS)

    Jacobson, E. B.

    1985-01-01

    An improved modular reactor head shielding system is provided that includes a frame which is removably assembled on a reactor head such that no structural or mechanical alteration of the head is required. The shielding system also includes hanging assemblies to mount flexible shielding pads on trolleys which can be moved along the frame. The assemblies allow individual pivoting movement of the pads. The pivoting movement along with the movement allowed by the trolleys provides ease of access to any point on the reactor head. The assemblies also facilitate safe and efficient mounting of the pads directly to and from storage containers such that workers have additional shielding throughout virtually the entire installation and removal process. The flexible shielding pads are designed to interleave with one another when assembled around the reactor head for substantially improved containment of radiation leakage

  13. Installation Art

    DEFF Research Database (Denmark)

    Petersen, Anne Ring

    Despite its large and growing popularity – to say nothing of its near-ubiquity in the world’s art scenes and international exhibitions of contemporary art –installation art remains a form whose artistic vocabulary and conceptual basis have rarely been subjected to thorough critical examination....... In Installation Art: Between Image and Stage, Anne Ring Petersen aims to change that. She begins by exploring how installation art developed into an interdisciplinary genre in the 1960s, and how its intertwining of the visual and the performative has acted as a catalyst for the generation of new artistic...... phenomena. It investigates how it became one of today’s most widely used art forms, increasingly expanding into consumer, popular and urban cultures, where installation’s often spectacular appearance ensures that it meets contemporary demands for sense-provoking and immersive cultural experiences. The main...

  14. Installation Art

    DEFF Research Database (Denmark)

    Petersen, Anne Ring

    . In Installation Art: Between Image and Stage, Anne Ring Petersen aims to change that. She begins by exploring how installation art developed into an interdisciplinary genre in the 1960s, and how its intertwining of the visual and the performative has acted as a catalyst for the generation of new artistic......Despite its large and growing popularity – to say nothing of its near-ubiquity in the world’s art scenes and international exhibitions of contemporary art –installation art remains a form whose artistic vocabulary and conceptual basis have rarely been subjected to thorough critical examination...... phenomena. It investigates how it became one of today’s most widely used art forms, increasingly expanding into consumer, popular and urban cultures, where installation’s often spectacular appearance ensures that it meets contemporary demands for sense-provoking and immersive cultural experiences. The main...

  15. Border installations

    International Nuclear Information System (INIS)

    Lenaerts, Koen

    1988-01-01

    Border installations cover all nuclear plants located near the border with a neighbouring state. However, the actual distance depends on the context. The distance can vary considerably. Also the prohibition on siting near a heavily populated area also defines the actual distance variably. The distance criteria may be modified by other factors of topography, prevailing climate and so on. Various examples which illustrate the problems are given. For example, the Creys-Melville nuclear power plant is 80km from Geneva and the Cattonam installation is 12km from the French border with Luxembourg and Germany. The Cattenom case is explained and the legal position within the European Institutions is discussed. The French licensing procedures for nuclear power stations are described with special reference to the Cattenom power plant. Border installations are discussed in the context of European Community Law and Public International Law. (U.K.)

  16. The programme of OECD-Nuclear Energy Agency Committee on the safety of nuclear installations principal working group no. 3 on reactor component integrity

    International Nuclear Information System (INIS)

    Schulz, H.; Miller, A.

    1995-01-01

    The programme of the OECD-NEA Principal Working Group No.3 on reactor component integrity is described including the following issues: regular Committee meetings; non-destructive testing; fracture analysis; aging; related activities

  17. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

    Object: To provide a boiling water reactor which can enhance a quake resisting strength and flatten power distribution. Structure: At least more than four fuel bundles, in which a plurality of fuel rods are arranged in lattice fashion which upper and lower portions are supported by tie-plates, are bundled and then covered by a square channel box. The control rod is movably arranged within a space formed by adjoining channel boxes. A spacer of trapezoidal section is disposed in the central portion on the side of the channel box over substantially full length in height direction, and a neutron instrumented tube is disposed in the central portion inside the channel box. Thus, where a horizontal load is exerted due to earthquake or the like, the spacers come into contact with each other to support the channel box and prevent it from abnormal vibrations. (Furukawa, Y.)

  18. Nuclear installations

    International Nuclear Information System (INIS)

    2001-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  19. Nuclear installations

    International Nuclear Information System (INIS)

    1998-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  20. Temperature increases from 55 to 75 C in a two-phase biogas reactor result in fundamental alterations within the bacterial and archaeal community structure

    Energy Technology Data Exchange (ETDEWEB)

    Rademacher, Antje [Leibniz-Institut fuer Agrartechnik Potsdam-Bornim e.V. (ATB), Potsdam (Germany). Abt. Bioverfahrenstechnik; Technische Univ. Berlin (Germany). Inst. fuer Technischen Umweltschutz; Nolte, Christine; Schoenberg, Mandy; Klocke, Michael [Leibniz-Institut fuer Agrartechnik Potsdam-Bornim e.V. (ATB), Potsdam (Germany). Abt. Bioverfahrenstechnik

    2012-10-15

    Agricultural biogas plants were operated in most cases below their optimal performance. An increase in the fermentation temperature and a spatial separation of hydrolysis/acetogenesis and methanogenesis are known strategies in improving and stabilizing biogas production. In this study, the dynamic variability of the bacterial and archaeal community was monitored within a two-phase leach bed biogas reactor supplied with rye silage and straw during a stepwise temperature increase from 55 to 75 C within the leach bed reactor (LBR), using TRFLP analyses. To identify the terminal restriction fragments that were obtained, bacterial and archaeal 16S rRNA gene libraries were constructed. Above 65 C, the bacterial community structure changed from being Clostridiales-dominated toward being dominated by members of the Bacteroidales, Clostridiales, and Thermotogales orders. Simultaneously, several changes occurred, including a decrease in the total cell count, degradation rate, and biogas yield along with alterations in the intermediate production. A bioaugmentation with compost at 70 C led to slight improvements in the reactor performance; these did not persist at 75 C. However, the archaeal community within the downstream anaerobic filter reactor (AF), operated constantly at 55 C, altered by the temperature increase in the LBR. At an LBR temperature of 55 C, members of the Methanobacteriales order were prevalent in the AF, whereas at higher LBR temperatures Methanosarcinales prevailed. Altogether, the best performance of this two-phase reactor was achieved at an LBR temperature of below 65 C, which indicates that this temperature range has a favorable effect on the microbial community responsible for the production of biogas. (orig.)

  1. Post-Fukushima additional safety assessments: behaviour of French nuclear installations in case of extreme situations and relevance of propositions of improvement. Summary of the IRSN report Nr 679 which has been used as a reference for the permanent Group of experts for reactors and plants held on the 8, 9 and 10 November

    International Nuclear Information System (INIS)

    2011-01-01

    This document summarizes the content of a report made by the IRSN and analysing the additional safety assessments performed and transmitted by operators in September 2011. It evokes the international context after the Fukushima-accident, addresses the analysis approach followed by the IRSN, discusses and comments the installation conditions, the robustness of installations with respect to high level risks and to those retained for their sizing, the behaviour of installations in the case of a total loss of cooling sources or of a long duration loss of energy supplies affecting several installations within a same site (case of EDF reactors, of the high flux reactor of the Laue Langevin Institute, CEA installations, Areva laboratories and plants), the capacity of operators to handle a crisis situation in such conditions, appeal to subcontracting

  2. Contributions to the research programs in nuclear and industrial electronics, domestic production of instrumentation, safety and control systems and equipment for nuclear reactors and auxiliary installations

    International Nuclear Information System (INIS)

    Talpariu, C; Talpariu, J.; Matei, C.

    2001-01-01

    Domestic production of component system and equipment for the control and safety of nuclear facilities was one of the priority objective of the Nuclear Research Institute Pitesti. The problems addressed were particularly related to design and production of analog and digital equipment for measurements, triggering and display of the values of process parameters as well as to regulating complex functions of this equipment. Associated to this effort were the research works concerning: - reliability and in-service life-time of the electronic components and equipment in the safety and control systems for nuclear processes; - radiation endurance of industrial electronic components; utilization of whirling currents in calandria tube testing; - expert systems and applications in nuclear reactor control and safety; design and testing methods of process real time software packages for safety in control critical systems for nuclear domain. There are presented characteristics of the following equipment: 1. amplifier for ionization chambers with triggering comparator circuits for the CANDU 600 reactor shut down system; 2. amplifier for ionization chambers without triggering comparator circuits for power regulating system; 3. safety and regulating computerized system for C9 and C5 cans; 4. acquisition system for dosimetric data in nuclear facilities; 5. program able digital comparator for the reactor shut down system; 6. stationary gamma areal monitors for CANDU 600 reactors and other nuclear facilities

  3. Reactors 2000: consultation on the technical and economical requirements connected with the possible realization of nuclear installations in Switzerland after the year 2000

    International Nuclear Information System (INIS)

    Haldi, P.A.

    1992-07-01

    In 1989 the OECD started a consultation on the development of nuclear reactors of small and medium size (SMR). The present study is part of the Swiss contribution to this international work. Beyond this primary goal, without being limited solely to SMRs, but exclusively in the Swiss framework, the study attempts to determine a profile for reactors which could be built in Switzerland after the year 2000. The study ''Reactors 2000'' is based on two polls which were conducted among about 70 persons from concerned professional circles (industry, utilities, scientific groups, energy policy makers, safety authorities, public organizations) in June 1990 and February 1991. A large majority of the persons interviewed think that - Switzerland should not jeopardize its energetic future by phasing out all activity in the nuclear field, based on circumstances which could be only temporary, - Switzerland should continue its activities in the nuclear field in order to maintain the necessary know-how and a sufficient number of highly qualified specialists both for the safe operation of the existing plants and for the continuation of the development of nuclear technology, - for future plants the goal of an even higher safety level should be aimed for, although, according to the explicit comments of many interviews, today's reactors are considered to be sufficiently safe, - future nuclear power plants should be designed in such a way that the possibility of a severe accident necessitating an evacuation of the Swiss population could be excluded, - Switzerland should participate in international projects, in order to maintain contact to the international development of nuclear technology; on the other hand, it should avoid any single-handed effort (including in the domain of small heating reactors). (author)

  4. Final report for the 1st ex-vessel neutron dosimetry installations and evaluations for Kori unit 2 reactor pressure vessel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Chul; Yoo, Choon Sung; Lee, Sam Lai; Chang, Kee Ok; Gong, Un Sik; Choi, Kwon Jae; Chang, Jong Hwa; Lim, Nam Jin; Hong, Joon Wha; Cheon, Byeong Jin

    2006-11-15

    This report describes a neutron fluence assessment performed for the Kori unit 2 pressure vessel belt line region based on the guidance specified in regulatory guide 1.190. In this assessment, maximum fast neutron exposures expressed in terms of fast neutron fluence (E>1 MeV) and iron atom displacements (dpa) were established for the belt line region of the pressure vessel. During cycle 20 of reactor operation, an ex-vessel neutron dosimetry program was instituted at Kori unit 2 to provide continuous monitoring of the belt line region of the reactor vessel. The use of the ex-vessel neutron dosimetry program coupled with available surveillance capsule measurements provides a plant specific data base that enables the evaluation of the vessel exposure and the uncertainty associated with that exposure over the service life of the unit. Ex-vessel neutron dosimetry has been evaluated at the conclusion of cycle 20.

  5. Final Report of the 2nd Ex-Vessel Neutron Dosimetry Installation And Evaluations for Yonggwang Unit 1 Reactor Pressure Vessel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Chul; Yoo, Choon Sung; Lee, Sam Lai; Chang, Kee Ok; Gong, Un Sik; Choi, Kwon Jae; Chang, Jong Hwa; Li, Nam Jin; Hong, Joon Wha

    2007-01-15

    This report describes a neutron fluence assessment performed for the Yonggwang Unit 1 pressure vessel belt line region based on the guidance specified in Regulatory Guide 1.190. In this assessment, maximum fast neutron exposures expressed in terms of fast neutron fluence (E>1 MeV) and iron atom displacements (dpa) were established for the belt line region of the pressure vessel. During Cycle 16 of reactor operation, 2nd Ex-Vessel Neutron Dosimetry Program was instituted at Yonggwang Unit 1 to provide continuous monitoring of the belt line region of the reactor vessel. The use of the Ex-Vessel Neutron Dosimetry Program coupled with available surveillance capsule measurements provides a plant specific data base that enables the evaluation of the vessel exposure and the uncertainty associated with that exposure over the service life of the unit. Ex-Vessel Neutron Dosimetry has been evaluated at the conclusion of Cycle 16.

  6. Final Report of the 2nd Ex-Vessel Neutron Dosimetry Installation And Evaluations for Yonggwang Unit 1 Reactor Pressure Vessel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Chul; Yoo, Choon Sung; Lee, Sam Lai; Gong, Un Sik; Choi, Kwon Jae; Chung, Kyoung Ki; Kim, Kwan Hyun; Chang, Jong Hwa; Ha, Jea Ju

    2008-01-15

    This report describes a neutron fluence assessment performed for the Kori Unit 2 pressure vessel belt line region based on the guidance specified in Regulatory Guide 1.190. In this assessment, maximum fast neutron exposures expressed in terms of fast neutron fluence (E>1 MeV) and iron atom displacements (dpa) were established for the belt line region of the pressure vessel. During Cycle 21 of reactor operation, an Ex-Vessel Neutron Dosimetry Program was instituted at Kori Unit 2 to provide continuous monitoring of the belt line region of the reactor vessel. The use of the Ex-Vessel Neutron Dosimetry Program coupled with available surveillance capsule measurements provides a plant specific data base that enables the evaluation of the vessel exposure and the uncertainty associated with that exposure over the service life of the unit. Ex-Vessel Neutron Dosimetry has been evaluated at the conclusion of Cycle 21.

  7. Final report for the 1st ex-vessel neutron dosimetry installation and evaluations for Kori unit 4 reactor pressure vessel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Chul; Yoo, Choon Sung; Lee, Sam Lai; Chang, Kee Ok; Gong, Un Sik; Choi, Kwon Jae; Chang, Jong Hwa; Lim, Nam Jin; Hong, Joon Wha; Cheon, Byeong Jin

    2006-11-15

    This report describes a neutron fluence assessment performed for the Kori unit 4 pressure vessel belt line region based on the guidance specified in regulatory guide 1.190. In this assessment, maximum fast neutron exposures expressed in terms of fast neutron fluence (E>1 MeV) and iron atom displacements (dpa) were established for the belt line region of the pressure vessel. During cycle 16 of reactor operation, an ex-vessel neutron dosimetry program was instituted at Kori unit 4 to provide continuous monitoring of the belt line region of the reactor vessel. The use of the ex-vessel neutron dosimetry program coupled with available surveillance capsule measurements provides a plant specific data base that enables the evaluation of the vessel exposure and the uncertainty associated with that exposure over the service life of the unit. Ex-vessel neutron dosimetry has been evaluated at the conclusion of cycle 16.

  8. Final report for the 2nd Ex-Vessel Neutron Dosimetry Installations and Evaluations for Yonggwang Unit 2 Reactor Pressure Vessel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Chul; Yoo, Choon Sung; Lee, Sam Lai; Gong, Un Sik; Choi, Kwon Jae; Chung, Kyoung Ki; Kim, Kwan Hyun; Chang, Jong Hwa; Ha, Jea Ju

    2008-01-15

    This report describes a neutron fluence assessment performed for the Yonggwang Unit 2 pressure vessel beltline region based on the guidance specified in Regulatory Guide 1.190. In this assessment, maximum fast neutron exposures expressed in terms of fast neutron fluence (E>1 MeV) and iron atom displacements (dpa) were established for the beltline region of the pressure vessel. During Cycle 16 of reactor operation, an Ex-Vessel Neutron Dosimetry Program was instituted at Yonggwang Unit 2 to provide continuous monitoring of the beltline region of the reactor vessel. The use of the Ex-Vessel Neutron Dosimetry Program coupled with available surveillance capsule measurements provides a plant specific data base that enables the evaluation of the vessel exposure and the uncertainty associated with that exposure over the service life of the unit. Ex-Vessel Neutron Dosimetry has been evaluated at the conclusion of Cycle 16.

  9. Results of water chemistry control in the in-pile ''Callisto'' loop (an experimental PWR rig installed in the BR2 reactor)

    International Nuclear Information System (INIS)

    Weber, M.; Benoit, P.; Dekeyser, J.; Verwimp, A.

    1994-01-01

    Since June 1992, a new experimental facility, called CALLISTO, is being irradiated in the BR2 materials testing reactor at Mol, Belgium. The main objective of the present test campaign is to study the behaviour of advanced fuel to high burn-up rates in a realistic PWR environment. Three in-pile sections, containing each 9 fuel rods, are loaded inside the reactor vessel and are connected to a common out-of-pile pressurized water circulation loop (ref.1). The later is branched-off into a purification circuit (feed-bleed concept) and further equipped with safety and auxiliary systems. To cope with the test programme, the equipments are designed so that the guidelines of a PWR primary water chemistry can be followed (ref.2). Real steady-state conditions cannot be observed because the typical BR2 cycle (3 weeks running/3 weeks shut-down) is much shorter and because the rig is cooled down during each reactor shut-down. The purpose of this poster is to provide results of chemical parameters recorded during the cycling behaviour of the CALLISTO primary water. (authors). 4 figs., 1 tab., 2 refs

  10. Border installations

    International Nuclear Information System (INIS)

    Lenaerts, K.

    1988-01-01

    This chapter highlights the legal problems raised by the concept of a border installation. Using the Cattenom nuclear power plant as an example, the author describes the different stages of the legal conflict raised by construction of the plant and analyses the relationship between French administrative law and some provisions of the Euratom Treaty. Based on the Treaty, the Community institutions have adopted directives to strengthen inter-State co-operation and consultation between neighbouring countries. He observes that these principles of co-operation, consultation and vigilance already exist in public international law; however, international case law has not yet made it possible to establish the strict liability of the constructing state in case of a nuclear accident (NEA) [fr

  11. Installation of a three-dimensional simulation method for core-physical description of pebble bed reactors with multiple recycling process at the example of the AVR

    International Nuclear Information System (INIS)

    Grotkamp, T.

    1984-01-01

    To describe the core-physical behaviour of pebble bed reactors simulation models are used, which reproduce the burn-up/recycling and - resulting - calculate criticality and neutron spectrum as well as neutron flux and temperature distribution. Modelling the AVR-reactor requires a three-dimensional treating for detailed considerations because of the graphite noses extending into the core. Such a system is built up in the present work and compared with the results of the two-dimensional model standardizated from operational side. The agreement is so good that the latter one is sufficient for the calculations accompanying the operation. The comparison with results of measurement is very satisfying in regard to fuel element distribution and temperature coefficient. As in all theoretical investigations there stays a discrepance of a little more than 1 nile against the measurement at the reactivity equivalence of the AVR rod-bank. On the other hand it is possible to reproduce the rod-bank curve resulting of the calibration very exactly with the present model. (orig.) [de

  12. Track 2: business outlook and the significance of safety - safety of nuclear power reactor installations in a deregulated environment. Panel Discussion

    International Nuclear Information System (INIS)

    Schultz, Stephen P.; Floyd, Stephen; Berkow, Herbert N.; Quinn, Edward L.; Hagen, Ronald E.; Esselman, Thomas C.

    2001-01-01

    Full text of publication follows: Deregulation in the nuclear industry sets the stage for a new production environment with cost and profit-based competition. This not only affects the commercial reactor sector but also is a key element of the U.S. Department of Energy's (DoE's) strategy for facility deployment and commercialization. This panel is designed to explore how these transitions are being made with the assurance of the principle of safety in operations. Panelists have been assembled from industry, the U.S. Nuclear Regulatory Commission (NRC), and DOE to explore these challenges and opportunities in the deregulated operational environment from a variety of perspectives. Presentations by each panelist will be followed by a panel session that will explore both technical and process elements of these major transitions. Success in a deregulated environment requires both safety and economic operation of facilities. With respect to each of these attributes, competition may be expected to result in substantially higher levels of performance. This panel will examine how these expectations are likely to be set, how they will be measured, and what will constitute success. The baseline for evaluation begins with assessment of past performance. The panelists have examined this for both the commercial nuclear reactor sector, as well as for the DOE complex. The Nuclear Energy Institute and the NRC have been working over the past few years on a program to establish new performance indicators for monitoring safety of reactor operation. The session participants will first examine the effectiveness of this system as it is designed to measure performance in today's environment. Second, the panelists will project the capabilities and attributes of this system in monitoring safety in transition to a deregulated, consolidated market. Will these systems have the capability to identify trends that will be significant in this new environment? Will today's system and metrics be

  13. Concerning modification of installation plan for reactor (modification of No.3 and No.4 reactor facilities) at Genkai nuclear power plant of Kyushu Electric Power Co., Ltd. (reply to inquiry)

    International Nuclear Information System (INIS)

    1988-01-01

    In response to an inquiry on the title issue, the Nuclear Safety Commission made an examination and submitted the findings to the Minister of International Trade and Industry. The modifications include the construction of combustion facilities for volume reduction of miscellaneous solid wastes. In the facilities, miscellaneous solid wastes will be combusted for volume reduction, and the combustion residue will be cooled with water and processed into glass-like granules, which will be stored in drums in the solid waste storage facilities. It is confirmed that the release of radioactive substances into the environment will be negligible, that the facilities have been designed to the Class B anti-earthquake standards, and that radiation monitors will be installed. The modifications also include the installation of an improved cement solidification system to replace a conventional-type system and a change in the capacity of the solid waste storage facilities. It is concluded that all proposed modifications should be approved. (Nogami, K.)

  14. Feasibility study for the installation of a nuclear reactor in thermal stimulation processes in heavy oil extraction from Orinoco oil belt

    International Nuclear Information System (INIS)

    Munoz, A.; Sanchez, R.

    1982-01-01

    Due to strategic need in the exploitation of heavy and extraheavy oil wells of Orinoco oil belt, technical and economical studies have been carried out to determine an optimal method for oil production and exploitation. So far, studies indicate thermal stimulation is the most adequate technique. Experience shows that stimulation cost is high when traditional methods (boilers) are used. The profit is due to the high price of oil in international market. Due to actual oil price trends, evaluation of nontraditional methods to generate steam in thermal stimulation processes (steam injection) is in order. A nuclear reactor as steam generator was evaluated. It was found economical feasibility and saving in fuel cost between 31.08% and 72.63% depending on oil prices

  15. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

    Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

  16. Installation of foundation fieldbus to KUR

    International Nuclear Information System (INIS)

    Ishihara, Shinji; Fujita, Yoshiaki

    1999-11-01

    The instrumentation and control system for the research reactor in Research Reactor Institute, Kyoto University has been used for the safe and steady operation since the initial critical attainment in 1964. It has been modified and added many devices in the chance of increasing the reactor power from 1 MW to 5 MW, installing new experimental facilities or fitting to modified nuclear regulations. In order to avoid the unscheduled shutdown of the research reactor by cause the failure of the devices, most of instrumentation system was renewed in 1999. Operating the research reactor more safely and reliably, Supervisory Control Automation and Data Acquisition System which employed personal computers with the Windows NT operating system was added to the conventional instrumentation system, and the fieldbus system called Foundation Fieldbus was installed. Compared with conventional instrumentation system, each fieldbus system has some advantages. Many kinds of fieldbus systems have been developed and sold on the markets in some countries. Foundation Fieldbus standardizing international, which was able to use the devices made by multi-vendor was tentatively installed to study particular techniques about Foundation Fieldbus. The primary coolant flow rate, the temperature difference between the reactor tank inlet and outlet temperatures, the calorimetric power and the reactor power in nuclear instrumentation are monitored on human-machine interface devices on the fieldbus. The programmable logic controller is employed to control the information system for the reactor. This paper introduces Foundation Fieldbus installed. (author)

  17. Promoting safety in nuclear installations. The IAEA has established safety standards for nuclear reactors and provides expert review and safety services to assist Member States in their application

    International Nuclear Information System (INIS)

    2002-01-01

    More than 430 nuclear power plants (NPPs) are currently operating in 30 countries around the world. The nuclear share of total electricity production ranges from about 20 percent in the Czech Republic and United States to nearly 78 percent in France and Lithuania. Worldwide, nuclear power generates about 16% of the total electricity. The safety of such nuclear installations is fundamental. Every aspect of a power plant must be closely supervised and scrutinized by national regulatory bodies to ensure safety at every phase. These aspects include design, construction, commissioning, trial operation, commercial operation, repair and maintenance, plant upgrades, radiation doses to workers, radioactive waste management and, ultimately, plant decommissioning. Safety fundamentals comprise defence-in-depth, which means having in place multiple levels of protection. nuclear facilities; regulatory responsibility; communicating with the public; adoption of the international convention on nuclear safety including implementation of IAEA nuclear safety standards. This publication covers topics of designing for safety (including safety concepts, design principles, and human factors); operating safety (including safety culture and advance in operational safety); risk assessment and management

  18. Decree no. 96-978 from October 31, 1996 giving permission to the French atomic energy Commission (CEA) to create a basic nuclear installation intended to maintain under supervision and in an intermediate dismantling state the old basic nuclear installation no. 28, named Monts d'Arree-EL 4 nuclear power plant (a decommissioned reactor), in the Monts d'Arree site of the Loqueffret town (Finistere, Brittany)

    International Nuclear Information System (INIS)

    Borotra, F.; Lepage, C.

    1996-01-01

    This decree from the French ministry of industry and postal services gives permission to the CEA to create a new basic nuclear installation, named EL 4D, which is devoted to the storage of materials from the partially dismantled Monts d'Arree EL 4 reactor. Thus, the CEA is allowed to carry out confining works on the reactor building with the closure of all apertures with the exception of the personnel entry sieve, on the circuits and equipments of the reactor vessel with the plugging of fuel channels, heavy water, helium and demineralized water pipes and of the heads of control rod drive mechanisms and other channels, and on the primary coolant circuit outside the reactor vessel and the steam generators with the installation of welded hatches. The irradiated fuels building, the solid wastes repository, the ventilation building, the heavy water and helium circuits, the fuel handling systems and the effluents treatment plant will be completely dismantled. The other buildings will be pulled down. The rest of the decree enumerates the general technical and safety prescriptions which have to be followed in order to ensure the protection of the personnel against ionizing radiations and of the environment against radioactive pollution. (J.S.)

  19. Industrial installation surveillance acoustic device

    International Nuclear Information System (INIS)

    Marini, Jean; Audenard, Bernard.

    1981-01-01

    The purpose of this invention is the detection of possible impacts of bodies migrating inside the installation, using acoustic sensors of the waves emitted at the time of impact of the migrating bodies. This device makes it possible to take into account only those acoustic signals relating to the impacts of bodies migrating in the area under surveillance, to the exclusion of any other acoustic or electric perturbing phenomenon. The invention has a preferential use in the case of a linear shape installation in which a fluid flows at high rate, such as a section of the primary system of a pressurized water nuclear reactor [fr

  20. Heating equipment installation system

    International Nuclear Information System (INIS)

    Meuschke, R.E.; Pomaibo, P.P.

    1991-01-01

    Disclosed is a method for installing a heater unit assembly in a reactor pressure vessel for performance of an annealing treatment on the vessel, the vessel having a vertical axis, being open at the top, being provided at the top with a flange having a horizontal surface, and being provided internally, at a location below the flange, with orientation elements which are asymmetrical with respect to the vertical axis, by the steps of: providing an orientation fixture having an upwardly extending guide member and orientation elements and installing the orientation fixture in the vessel so that the orientation elements of the orientation fixture mate with the orientation elements of the pressure vessel in order to establish a defined position of the orientation fixture in the pressure vessel, and so that the guide member projects above the pressure vessel flange; placing a seal ring in a defined position on the pressure vessel flange with the aid of the guide member; mounting at least one vertical, upwardly extending guide stud upon the seal ring; withdrawing the orientation fixture from the pressure vessel; and moving the heater unit assembly vertically downwardly into the pressure vessel while guiding the heater unit assembly along a path with the aid of the guide stud. 5 figures

  1. Seismic evaluation of nuclear installations

    International Nuclear Information System (INIS)

    Mattar Neto, Miguel

    1997-01-01

    Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs

  2. Neutron field characterization in the installation for BNCT study in the IEA-R1 reactor; Caracterizacao do campo de neutrons na instalacao para estudo em BNCT no reator IEA-R1

    Energy Technology Data Exchange (ETDEWEB)

    Carneiro Junior, Valdeci

    2008-07-01

    This work aims to characterize the mixed neutron and gamma field, in the sample irradiation position, in a research installation for Boron Neutron Capture Therapy (BNCT), in the IPEN IEA-R1 reactor. The BNCT technique has been studied as a safe and selective option in the treatment of resistant cancerigenous tumors or considered non-curable by the conventional techniques, for example, the Glioblastoma Multiform - a brain cancerigenous tumor. Neutron flux measurements were carried out: thermal, resonance and fast, as well as neutron and gamma rays doses, in the sample position, using activation foils detectors and thermoluminescent dosimeters. For the determination of the neutron spectrum and intensity, a set of different threshold activation foils and gold foils covered and uncovered with cadmium irradiated in the installation was used, analyzed by a high Pure Germanium semiconductor detector, coupled to an electronic system suitable for gamma spectrometry. The results were processed with the SAND-BP code. The doses due to gamma and neutron rays were determined using thermoluminescent dosimeters TLD 400 and TLD 700 sensitive to gamma and TLD 600, sensitive to neutrons. The TLDs were selected and used for obtaining the calibration curves - dosimeter answer versus dose - from each of the TLD three types, which were necessary to calculate the doses due to neutron and gamma, in the sample position. The radiation field, in the sample irradiation position, was characterized flux for thermal neutrons of 1.39.10{sup 8} {+-} 0,12.10{sup 8} n/cm{sup 2}s the doses due to thermal neutrons are three times higher than those due to gamma radiation and confirm the reproducibility and consistency of the experimental findings obtained. Considering these results, the neutron field and gamma radiation showed to be appropriated for research in BNCT. (author)

  3. Improvements in or relating to nuclear reactors

    International Nuclear Information System (INIS)

    Timofeev, A.V.; Batjukov, V.I.; Fadeev, A.I.; Shapkin, A.F.; Shikhiyan, T.G.; Ordynsky, G.V.; Drachev, V.P.; Pogodin, E.N.

    1980-01-01

    A refuelling installation for nuclear reactor complexes is described for recharging the reactor vessels of such complexes with new fuel assemblies and for removing spent fuel assemblies from the reactor vessel. (U.K.)

  4. The safety of nuclear installations

    International Nuclear Information System (INIS)

    1993-01-01

    This Safety Fundamental publication sets out basic objectives, concepts and principles for ensuring safety that can be used both by the IAEA in its international assistance operations and by Member States in their national nuclear programmes. These Safety Fundamentals apply primarily to those nuclear installations in which the stored energy developed in certain situations could potentially results in the release of radioactive material from its designated location with the consequent risk of radiation exposure of people. These principles are applicable to a broad range of nuclear installations, but their detailed application will depend on the particular technology and the risks posed by it. In addition to nuclear power plants, such installations may include: research reactors and facilities, fuel enrichment, manufacturing and reprocessing plants; and certain facilities for radioactive waste treatment and storage

  5. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

    It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

  6. 46 CFR 176.702 - Installation tests and inspections.

    Science.gov (United States)

    2010-10-01

    ..., machinery, fuel tank, or pressure vessel is installed aboard a vessel after completion of the initial... 100 GROSS TONS) INSPECTION AND CERTIFICATION Repairs and Alterations § 176.702 Installation tests and...

  7. Radiological protection in nucleus reactor; Perlindungan radiologi di reaktor nukleus

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-31

    The chapter briefly discussed the following subjects: radiological protection problems of reactor 1. in operation 2. types of reactor i.e. power reactors, research reactors, etc. 3. during maintenance and installation of fuels. 4. nuclear fuels.

  8. Some suggestions based on the instrumentation installation experience at RAPP

    International Nuclear Information System (INIS)

    Raghunath, M.R.; Singh, S.; Jain, V.K.

    1977-01-01

    Suggestions regarding installation of reactor instrumentation have been made based on the instrumentation installation experience at the Rajasthan Atomic Power Plant. It has been mentioned that the instrumentation installation work has to proceed simultaneously with that of the heavy equipment and piping errection work, to meet the commissioning target dates. (S.K.K.)

  9. Reactor console replacement at Washington State University

    International Nuclear Information System (INIS)

    Lovas, Thomas A.

    1978-01-01

    A replacement reactor console was installed in 1977 at the W.S.U. 1 MW TRIGA-fueled reactor as the final step in an instrumentation upgrade program. The program was begun circa 1972 with the design, construction and installation of various systems and equipment. Major instruments were installed in the existing console and tested in the course of reactor operation. The culmination of the program was the installation of a cubicle designed and constructed to house the updated instrumentation. (author)

  10. Preparing the construction of a school reactor

    International Nuclear Information System (INIS)

    Matejka, K.

    1977-01-01

    The possibilities are discussed of teaching and training nuclear reactor operation and control, teaching experimental reactor physics and investigating reactor lattice parameters using a training reactor to be installed at the Faculty of Nuclear Science and Physical Engineering in Prague. Requirements are indicated for the reactor's technical design and the Faculty's possibilities to contribute to its construction. (J.B.)

  11. Reactor Physics Training

    International Nuclear Information System (INIS)

    Baeten, P.

    2007-01-01

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  12. Nuclear installations: decommissioning and dismantling

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    This document is a compilation of seven talks given during the 1995 EUROFORUM conference about decommissioning and dismantling of Nuclear installations in the European Community. The first two papers give a detailed description of the legal, financial and regulatory framework of decommissioning and dismantling of nuclear facilities in the European Union and a review of the currently available decommissioning techniques for inventory, disassembly, decontamination, remote operations and management of wastes. Other papers describe some legal and technical aspects of reactor and plants dismantling in UK, Germany, Spain and France. (J.S.)

  13. Nuclear Installations Act 1965

    International Nuclear Information System (INIS)

    1965-01-01

    This Act governs all activities related to nuclear installations in the United Kingdom. It provides for the licensing procedure for nuclear installations, the duties of licensees, the competent authorities and carriers of nuclear material in respect of nuclear occurrences, as well as for the system of third party liability and compensation for nuclear damage. The Act repeals the Nuclear Installations (Licensing and Insurance) Act 1959 and the Nuclear Installations (Amendment Act) 1965 except for its Section 17(2). (NEA) [fr

  14. Installation report - Lidar

    DEFF Research Database (Denmark)

    Georgieva Yankova, Ginka; Villanueva, Héctor

    The report describes the installation, configuration and data transfer for the ground-based lidar. The unit is provided by a customer but is installed and operated by DTU while in this project.......The report describes the installation, configuration and data transfer for the ground-based lidar. The unit is provided by a customer but is installed and operated by DTU while in this project....

  15. The Upgraded Plasma Focus Installation > - The Installation >

    International Nuclear Information System (INIS)

    Krokhin, O.N.; Nikulin, V.Ya.; Babenko, B.A.; Gorbunov, D.N.; Gurei, A.E.; Kalachev, N.V.; Kozlova, T.A.; Malafeev, Yu.S.; Polukhin, S.N.; Sychev, A.A.; Tikhomirov, A.A.; Tsybenko, S.P.; Volobuev, I.V.

    1999-01-01

    The paper presents the upgraded plasma focus installation > - the installation > and some preliminary experimental results. The total energy stored in capacity bank is now 400 kJ, current - 5 MA with the rise time 3.5 μs. The investigation is targeted on the study of near electrode processes and its influence on plasma dynamics in a special operating regime of Filippov type PF - Hard X-ray regime. (author)

  16. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported.

  17. Reactor BR2

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported

  18. Reactor System Design

    International Nuclear Information System (INIS)

    Chi, S. K.; Kim, G. K.; Yeo, J. W.

    2006-08-01

    SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

  19. Reactor vessel sealing plug

    International Nuclear Information System (INIS)

    Dooley, R.A.

    1986-01-01

    This invention relates to an apparatus and method for sealing the cold leg nozzles of a nuclear reactor pressure vessel from a remote location during maintenance and inspection of associated steam generators and pumps while the pressure vessel and refueling canal are filled with water. The apparatus includes a sealing plug for mechanically sealing the cold leg nozzle from the inside of a reactor pressure vessel. The sealing plugs include a primary and a secondary O-ring. An installation tool is suspended within the reactor vessel and carries the sealing plug. The tool telescopes to insert the sealing plug within the cold leg nozzle, and to subsequently remove the plug. Hydraulic means are used to activate the sealing plug, and support means serve to suspend the installation tool within the reactor vessel during installation and removal of the sealing plug

  20. Installation Test of Cold Neutron Soruce In-pool Assembly

    International Nuclear Information System (INIS)

    Lee, Kye Hong; Choi, J.; Wu, S. I.; Kim, Y. K.; Cho, Y. G.; Lee, C. H.; Kim, K. R.

    2006-04-01

    Before installation of the final cold neutron source in-pool assembly (IPA) in the vertical CN hole at the HANARO, the research reactor, the installation test of IPA has been conducted in the CN hole of the reactor using a full-scaled mock-up in-pool assembly. The well-known cold neutron sources, being safely operated or being now constructed, had been constructed together with each research reactor; therefore, there was little limitation to obtain the optimal cold neutron source since a cold neutron source had been decided to be installed in the reactor from the beginning of the design for the reactor construction. Unlikely, the HANARO has been operated for 10 years so that we have got lots of design limitation in terms of the decisions in the optimal shape, size, minimal light-water gap, and adhesion degree to the CN beam tube, IPA installation tools, etc. for the construction of the CNS. Accordingly, the main objective of this test is to understand any potential problem or interference happened inside the reactor by installing the mock-up IPA and installation bracket. The outcomes from this test is reflected on the finalizing process of the IPA detail design

  1. Design, fabrication and installation of irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yong Sung; Lee, C. Y.; Kim, J. Y.; Chi, D. Y.; Kim, S. H.; Ahn, S. H.; Kim, S. J.; Kim, J. K.; Yang, S. H.; Yang, S. Y.; Kim, H. R.; Kim, H.; Lee, K. H.; Lee, B. C.; Park, C.; Lee, C. T.; Cho, S. W.; Kwak, K. K.; Suk, H. C. [and others

    1997-07-01

    The principle contents of this project are to design, fabricate and install the steady-state fuel test loop and non-instrumented capsule in HANARO for nuclear technology development. This project will be completed in 1999, the basic and detail design, safety analysis, and procurement of main equipment for fuel test loop have been performed and also the piping in gallery and the support for IPS piping in reactor pool have been installed in 1994. In the area of non-instrumented capsule for material irradiation test, the fabrication of capsule has been completed. Procurement, fabrication and installation of the fuel test loop will be implemented continuously till 1999. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and safety analysis report has been submitted to KINS to get a license and review of HANARO interface have been performed respectively. (author). 39 refs., 28 tabs., 21 figs.

  2. Design, fabrication and installation of irradiation facilities

    International Nuclear Information System (INIS)

    Kim, Yong Sung; Lee, C. Y.; Kim, J. Y.; Chi, D. Y.; Kim, S. H.; Ahn, S. H.; Kim, S. J.; Kim, J. K.; Yang, S. H.; Yang, S. Y.; Kim, H. R.; Kim, H.; Lee, K. H.; Lee, B. C.; Park, C.; Lee, C. T.; Cho, S. W.; Kwak, K. K.; Suk, H. C.

    1997-07-01

    The principle contents of this project are to design, fabricate and install the steady-state fuel test loop and non-instrumented capsule in HANARO for nuclear technology development. This project will be completed in 1999, the basic and detail design, safety analysis, and procurement of main equipment for fuel test loop have been performed and also the piping in gallery and the support for IPS piping in reactor pool have been installed in 1994. In the area of non-instrumented capsule for material irradiation test, the fabrication of capsule has been completed. Procurement, fabrication and installation of the fuel test loop will be implemented continuously till 1999. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and safety analysis report has been submitted to KINS to get a license and review of HANARO interface have been performed respectively. (author). 39 refs., 28 tabs., 21 figs

  3. Advanced Measuring (Instrumentation Methods for Nuclear Installations: A Review

    Directory of Open Access Journals (Sweden)

    Wang Qiu-kuan

    2012-01-01

    Full Text Available The nuclear technology has been widely used in the world. The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. In last decades, many advanced measuring devices and techniques have been widely applied in nuclear installations. This paper mainly introduces the development of the measuring (instrumentation methods for nuclear installations and the applications of these instruments and methods.

  4. Installation of a second trip system

    International Nuclear Information System (INIS)

    Bessada, E.

    1997-01-01

    Since its first criticality in 1957, the NRU reactor has been operating safely and efficiently supporting the CANDU reactor's research and development programs and producing radioisotopes for medical use. To ensure that the reactor continues to operate safely and effectively, Atomic Energy of Canada Limited (AECL) commissioned a team in 1989 to conduct a systematic review and assessment of the reactor condition. The outcome of the study indicated that the overall condition of the reactor is good and that it is being operated safely. The study also produced recommendations as to where safety can be improved. These recommendations are the basis of the upgrade program currently being implemented in the reactor. The Second Trip System (STS) is part of the upgrade program. It is a stand alone seismically qualified trip system that operates independently from the existing first trip system (FST) to shutdown the reactor. This paper discusses the design, installation and the inactive commissioning of the system, and the process used to ensure that the system can be retrofitted to the reactor without affecting its safety or its operational requirements. (author)

  5. LHC installation planning

    CERN Document Server

    Weisz, S

    2005-01-01

    installation of the general services, the installation of the cryogenic line (QRL), the installation of the machine elements and the hardware commissioning. While the installation of the general services is now almost finished (see presentation by Katy Foraz and Serge Grillot), several problems and delays with the QRL made it unavoidable to revise the installation strategy and to schedule a number tasks in parallel. A new compressed installation planning has been issued, that fulfils the strategic objectives and allows starting new activities with minimal delays in sectors 7-8 and 8-1. However, the shortcuts that are introduced increase the level of risk that we will have to face and the coordination of such a large and complex variety of simultaneous activities makes the project even more challenging. The document will describe how the input from the different equipment groups is taken into account by the master schedule planning team with respect to equipment availability and production as well as logistics...

  6. Electrical installation calculations basic

    CERN Document Server

    Kitcher, Christopher

    2013-01-01

    All the essential calculations required for basic electrical installation workThe Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike. The book provides a step-by-step guide to the successful application of electrical installation calculations required in day-to-day electrical engineering practice. A step-by-step guide to everyday calculations used on the job An essential aid to the City & Guilds certificates at Levels 2 and 3Fo

  7. Electrical installation calculations advanced

    CERN Document Server

    Kitcher, Christopher

    2013-01-01

    All the essential calculations required for advanced electrical installation workThe Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike. The book provides a step-by-step guide to the successful application of electrical installation calculations required in day-to-day electrical engineering practiceA step-by-step guide to everyday calculations used on the job An essential aid to the City & Guilds certificates at Levels 2 and 3For apprentices and electrical installatio

  8. Electrical installations and regulations

    CERN Document Server

    Whitfield, J F

    1966-01-01

    Electrical Installations and Regulations focuses on the regulations that apply to electrical installations and the reasons for them. Topics covered range from electrical science to alternating and direct current supplies, as well as equipment for providing protection against excess current. Cables, wiring systems, and final subcircuits are also considered, along with earthing, discharge lighting, and testing and inspection.Comprised of 12 chapters, this book begins with an overview of electrical installation work, traits of a good electrician, and the regulations governing installations. The r

  9. One piece reactor removal

    International Nuclear Information System (INIS)

    Chia, Wei-Min; Wang, Song-Feng

    1993-01-01

    The strategy of Taiwan Research Reactor Renewal plan is to remove the old reactor block with One Piece Reactor Removal (OPRR) method for installing a new research reactor in original building. In this paper, the engineering design of each transportation works including the work method, the major equipments, the design policy and design criteria is described and discussed. In addition, to ensure the reactor block is safety transported for storage and to guarantee the integrity of reactor base mat is maintained for new reactor, operation safety is drawn special attention, particularly under seismic condition, to warrant safe operation of OPRR. ALARA principle and Below Regulatory Concern (BRC) practice were also incorporated in the planning to minimize the collective dose and the total amount of radioactive wastes. All these activities are introduced in this paper. (J.P.N.)

  10. The Swiss nuclear installations annual report 1992

    International Nuclear Information System (INIS)

    1993-06-01

    This report concerns the safety of the Swiss nuclear installations in the period of 1992. Surveillance of these installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). In Switzerland five nuclear power plants are operational: Beznau I and II, Muehleberg, Goesgen and Leibstadt. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basle. Further subject to HSK's supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut down experimental reactor of Lucens, the exploration in Switzerland of final disposal facilities for radwaste and the interim radwaste storage facilities. The present report first deals with the nuclear power plants and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK (chapters 1-4). In chapter 5, the corresponding information is given for the research installations. Chapter 6 on radwaste disposal is dedicated to the waste treatment, waste from reprocessing, interim storage and exploration by the NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants' vicinity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into some general questions relating to the safety of nuclear installations, and in particular covers important events in nuclear installations abroad. In all, the operation of the Swiss nuclear installations in the period of 1992 is rated safe by HSK. (author) 7 figs., 13 tabs

  11. Research and materials irradiation reactors

    International Nuclear Information System (INIS)

    Ballagny, A.; Guigon, B.

    2004-01-01

    Devoted to the fundamental and applied research on materials irradiation, research reactors are nuclear installations where high neutrons flux are maintained. After a general presentation of the research reactors in the world and more specifically in France, this document presents the heavy water cooled reactors and the water cooled reactors. The third part explains the technical characteristics, thermal power, neutron flux, operating and details the Osiris, the RHF (high flux reactor), the Orphee and the Jules Horowitz reactors. The last part deals with the possible utilizations. (A.L.B.)

  12. Mimic of OSU research reactor

    International Nuclear Information System (INIS)

    Lu, Hong; Miller, D.W.

    1991-01-01

    The Ohio State University research reactor (OSURR) is undergoing improvements in its research and educational capabilities. A computer-based digital data acquisition system, including a reactor system mimic, will be installed as part of these improvements. The system will monitor the reactor system parameters available to the reactor operator either in digital parameters available to the reactor operator either in digital or analog form. The system includes two computers. All the signals are sent to computer 1, which processes the data and sends the data through a serial port to computer 2 with a video graphics array VGA monitor, which is utilized to display the mimic system of the reactor

  13. Reactor power measuring device

    International Nuclear Information System (INIS)

    Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

    1993-01-01

    The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

  14. 3D Projection Installations

    DEFF Research Database (Denmark)

    Halskov, Kim; Johansen, Stine Liv; Bach Mikkelsen, Michelle

    2014-01-01

    Three-dimensional projection installations are particular kinds of augmented spaces in which a digital 3-D model is projected onto a physical three-dimensional object, thereby fusing the digital content and the physical object. Based on interaction design research and media studies, this article ...... Fingerplan to Loop City, is a 3-D projection installation presenting the history and future of city planning for the Copenhagen area in Denmark. The installation was presented as part of the 12th Architecture Biennale in Venice in 2010....

  15. TESLA accelerator installation

    International Nuclear Information System (INIS)

    Neskovic, N.; Ostojic, R.; Susini, A.; Milinkovic, Lj.; Ciric, D.; Dobrosavljevic, A.; Brajuskovic, B.; Cirkovic, S.; Bojovic, B.; Josipovic, M.

    1992-01-01

    The TESLA accelerator Installation is described. Its main parts are the VINCY Cyclotron, the multiply charged heavy-ion mVINIS Ion Source, and the negative light-ion pVINIS Ion Source. The Installation should be the principal installation of a regional center for basic and applied research in nuclear physics, atomic physics, surface physics and solid state physics, for production of radioisotopes, for research and therapy in nuclear medicine. The first extraction of the ion beam from the Cyclotron is planned for 1995. (R.P.) 3 refs.; 1 fig

  16. The Swiss nuclear installations. Annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    Surveillance of the Swiss nuclear installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). Five nuclear power plants are operational in Switzerland: the three units Beznau I and II and Muehleberg with electrical capacities in the range of 300 to 400 MWe, and the two units Goesgen and Leibstadt with capacities between 900 and 1200 MWe. These are light water reactors; at Beznau and Goesgen of the PWR type, and at Muehleberg and Leibstadt of the BWR type. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basel. Further subject to HSK`s supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut-down experimental reactor of Lucens, the exploration, in Switzerland, of final disposal facilities for radwaste and the interim radwaste storage facilities. The report first deals with the nuclear power and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK. In chapter 5, the corresponding information is given for research installations. Chapter 6, on radwaste disposal, is dedicated to the treatment of waste, waste from reprocessing, interim storage and exploration by NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants` proximity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into general questions relating to the safety of nuclear installations. All in all, the safety of operation of the Swiss nuclear installations, in the period of 1994, is judged as good by HSK. (author) 11 figs., 13 tabs.

  17. The Swiss nuclear installations. Annual report 1993

    International Nuclear Information System (INIS)

    1994-08-01

    Surveillance of the Swiss nuclear installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). Five nuclear power plants are operational in Switzerland: the three units Beznau I and II and Muehleberg with electrical capacities in the range of 300 to 400 MWe, and the two units Goesgen and Leibstadt with capacities between 900 and 1200 MWe. These are light water reactors; at Beznau and Goesgen of the PWR type, and at Muehleberg and Leibstadt of the BWR type. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basel. Further subject to HSK's supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut-down experimental reactor of Lucens, the exploration of final disposal facilities for radwaste and the interim radwaste storage facilities in Switzerland. The report first deals with the nuclear power and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK. In chapter 5, the corresponding information is given for research installations. Chapter 6, on radwaste disposal, is dedicated to the treatment of waste, waste from reprocessing, interim storage and exploration by NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants' proximity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into general questions relating to the safety of nuclear installations. All in all, the safety of operation of the Swiss nuclear installations, in the period of 1993, is judged as good by HSK. (author) 10 figs., 11 tabs

  18. Development regulation regarding with licensing of nuclear installation

    International Nuclear Information System (INIS)

    Bambang Riyono; Yudi Pramono; Dahlia Cakrawati Sinaga

    2011-01-01

    Provisions of Article 17 paragraph (3) of Law Number 10 Year 1997 on Nuclear cleary mandates for the establishment of government regulations (GR) on Nuclear licensing containing the requirements and procedure, both from the standpoint of their utilization and installation. To use has been rising GR No.29 Year 2008 on the Use of Ionizing Radiation Sources and Nuclear Materials, while for the installation has been published PP No.43 Year 2006 on Nuclear Reactor Licensing, and BAPETEN Chairman Decree No.3 Year 2006 on Non-reactor Nuclear Installation Licensing. Based on the background of the preparation of both the aforementioned are just regulate the reactor and utilization, not yet fully meet the mandate of Article 17 paragraph (3) of Law No.10 of 1997 on Nuclear, including other nuclear installations. For these reasons, it initiated the need for a separate regulation containing provisions concerning licensing of non-reactor nuclear installations. On the other side from the understanding the legal aspects and interpretations of the Law No.10 of 2004 on the Establishment Regulation Legislation, should be in single mandate of Article 17 paragraph (3) of Law No.10 of 1997 on Nuclear would only produce one of the requirements and procedure for the use or installation, or a maximum of two (2) GR related licensing the use and installation. This is encourages conducted the assessing or studies related to how possible it is according to the legal aspect is justified to combine in one Nuclear licensing regulations regarding both the use and installation, by looking at the complexity of installation and wide scope of utilization of nuclear energy in Indonesia. The results of this paper is expected to provide input in the preparation of GR on licensing of nuclear installations. (author)

  19. Patterns identification in supervisory systems of nuclear reactors installations and gas pipelines systems using self-organizing maps; Identificacao de padroes em sistemas supervisorios de instalacoes de reatores nucleares e em sistemas de gasodutos utilizando mapas auto-organizaveis

    Energy Technology Data Exchange (ETDEWEB)

    Doraskevicius Junior, Waldemar

    2005-07-01

    Self-Organizing Maps, SOM, of Kohonen were studied, implemented and tested with the aim of developing, for the energy branch, an effective tool especially for transient identification in nuclear reactors and for gas pipelines networks logistic supervision, by classifying operations and identifying transients or abnormalities. The digital system for the test was developed in Java platform, for the portability and scalability, and for belonging to free development platforms. The system, executed in personal computers, showed satisfactory results to aid in decision taking, by classifying IRIS (International Reactor Innovative and Secure) reactor operation conditions (data from simulator) and by classifying Southeast (owner: TRANSPETRO - Brazil) gas pipeline network. Various adaptations were needed for such business, as new topologies for the output layer of artificial neural network and particular preparation for the input data. (author)

  20. The program of reactors and nuclear power plants; Programa de reactores y centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

    2001-07-01

    Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined.

  1. Installations having pressurised fluid circuits

    International Nuclear Information System (INIS)

    Rigg, S.; Grant, J.

    1977-01-01

    Reference is made to nuclear installations having pressurised coolant flow circuits. Breaches in such circuits may quickly result in much damage to the plant. Devices such as non-return valves, orifice plates, and automatically operated shut-off valves have been provided to prevent or reduce fluid flow through a breached pipe line, but such devices have several disadvantages; they may present large restrictions to normal flow of coolant, and may depend on the operation of ancillary equipment, with consequent delay in bringing them into operation in an emergency. Other expedients that have been adopted to prevent or reduce reverse flow through an upstream breach comprise various forms of hydraulic counter flow brakes. The arrangement described has at least one variable fluid brake comprising a fluidic device connected into a duct in the pressurised circuit, the device having an inlet, an outlet, a vortex chamber between the inlet and outlet, a control jet for introducing fluid into the vortex chamber, connections communicating the inlet and the outlet into one part of the circuit and the control jet into another region at a complementary pressure so that, in the event of a breach in the circuit in one region, fluid passes from the other region to enter the vortex chamber to stimulate pressure to create a flow restricting vortex in the chamber that reduces flow through the breach. The system finds particular application to stream generating pressure tube reactors, such as the steam generating heavy water reactor at UKAEA, Winfrith. (U.K.)

  2. Construction, fabrication, and installation

    International Nuclear Information System (INIS)

    1992-05-01

    This standard specifies the construction, fabrication, and installation requirements that apply to concrete containment structures of a containment system designated as class containment components, parts and appurtenances for nuclear power plants

  3. Visiting the SPS installation

    CERN Multimedia

    1975-01-01

    ...., Guenther Loehr, Hans Horisberger walk along the SPS tunnel: here, on the right, an absorber block of 22 tons for beam dumping in the external beam lines. The chariot serves for the installation of the block.

  4. Biggest semiconductor installed

    CERN Multimedia

    2008-01-01

    Scientists and technicians at the European Laboratory for Particle Physics, commonly known by its French acronym CERN (Centre Europen pour la Recherche Nuclaire), have completed the installation of the largest semiconductor silicon detector.

  5. Sizewell 'B' cable installation

    International Nuclear Information System (INIS)

    Gemmell, D.R.

    1992-01-01

    N G Bailey and Co. Ltd., UK were awarded the contract for the procurement, manufacture, works testing, works finishing, supply, delivery, off-loading, storage, installation, site finishing, preservation, setting to work and site testing of the following; the main cable installation throughout the Station including the addition of the Radioactive Waste Building, earthing and lightning protection installation, cable supporting steelwork and carriers and glanding and termination of cables. The cabling installation comprises power distribution, control and instrumentation cabling including all the associated cabling accessories, terminal boxes and similar components. The way that the contract was set-up, awarded and is now being carried out is described. Planning and industrial relations have been key features of the contract. (Author)

  6. Synthesis of the IRSN report on arrangements proposed by AREVA, the CEA and the ILL about the implementation of a 'hard core' for installations related to the fuel cycle and for research reactors falling within batch 1

    International Nuclear Information System (INIS)

    2013-01-01

    After additional safety assessments performed by operators of French nuclear installations, the ASN ask them to implement a 'hard core' of material and organisational arrangements to prevent any severe accident or its propagation, to limit massive releases within a scenario of accident which could not have been controlled, and to allow the operator to ensure its assigned missions in crisis management, to present an organisation and means of crisis management which would remain operational in case of extreme aggressions, and to foresee transient arrangements before the implementation of the crisis management hard core. This report proposes a synthesis of the assessment performed by the IRSN on these issues. It addresses issues on which hard cores are defined (earthquakes, flooding, other climatic aggressions, effects induced by an extreme aggression), requirements associated with material arrangements of hard cores. The content of these hard cores is then discussed for AREVA installations (La Hague, MELOX, Romans-sur-Isere, Tricastin), CEA installations and the high flow reactor of the Laue Langevin Institute. Measures concerning crisis management and, for AREVA, the taking of human and organisational factors into account by these operators are also discussed

  7. 46 CFR 115.702 - Installation tests and inspections.

    Science.gov (United States)

    2010-10-01

    ... CERTIFICATION Repairs and Alterations § 115.702 Installation tests and inspections. Whenever a launching appliance, survival craft, rescue boat, fixed gas fire extinguishing system, machinery, fuel tank, or...

  8. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2001-01-01

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given

  9. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2001-04-01

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given.

  10. Installation of the sag compensator for HANARO

    International Nuclear Information System (INIS)

    Kim, Hyungkyoo; Jung, Hoansung; Lim, Incheol; Ahn, Gukhoon

    2008-01-01

    Electric power is essential for all industrial plants and also for nuclear facilities. HANARO is a research reactor which produces a 30 MW thermal power. HANARO is designed to be tripped automatically when interruptions or some extent of sags occur. HANARO has the reactor regulation system(RRS) and reactor protection system(RPS). HANARO is designed so as to be tripped automatically by insertion of control absorber rods(CAR) and shut-off rods(SOR). When voltage sag or momentary interruption occurs, the reactor has an unwanted trip by insertion of CARs and SORs even though the process systems are still in operation. HANARO was experienced in a nuisance trip as often as the unexpected voltage sag and/or momentary interruption occurs. We installed the voltage sag compensator on the power supply for CARs and SORs so as to prevent an unwanted trip. We undertook voltage sag assessment of the AC coil contactor which is a component of the power supply unit for the SORs. The compensation time is determined to be less than 1 sec in consideration of the reactor safety. This paper is concerned with the impact of the momentary interruption on the reactor and the effect of the voltage sag compensator. (author)

  11. Installation of the sag compensator for HANARO

    International Nuclear Information System (INIS)

    Kim, H. K.; Jung, H. S.; Ahn, G. H.; Lim, I. C.

    2008-01-01

    Electric power is essential for all industrial plants and also for nuclear facilities. HANARO is a research reactor which produces a 30MW thermal power. HANARO is designed to be tripped automatically when interruptions or some extents of sags occur. HANARO has the reactor regulation system (RRS) and reactor protection system (RPS). HANARO is designed so as to tripped automatically by insertion of control absorber rods (CAR) and shut-off rods (SOR). When voltage or momentary interruption occurs, the reactor has an unwanted trip by insertion of CARs and SORs even though the process systems are still in operation. HANARO was experienced in a nuisance trip as often as the unexpected voltage sag and/or momentary interruption occurs. We installed the voltage sag compensator on the power supply for CARs and SORs so as to prevent an unwanted trip. We undertook voltage sag assessment of the AC coil contactor which is a component of the power supply unit for the SORs. The compensation time is determined to be less than 1 sec in consideration of the reactor safety. This paper is concerned with the impact of the momentary interruption on the reactor and the effect of the voltage sag compensator

  12. Installation of the sag compensator for HANARO

    International Nuclear Information System (INIS)

    Kim, Hyung Kyoo; Jung, Hoan Sung; Lim, In Cheol; Ahn, Guk Hoon

    2008-01-01

    Electric power is essential for all industrial plants and also for nuclear facilities. HANARO is a research reactor which produces a 30MW thermal power. HANARO is designed to be tripped automatically when interruptions or some extent of sags occur. HANARO has the reactor regulation system(RRs) and reactor protection system(RPS). HANARO is designed so as to be tripped automatically by insertion of control absorber rods(CAR) and shut off rods(SOR). When voltage sag or momentary interruption occurs, the reactor has an unwanted trip by insertion of CARs and SORs even though the process systems are still in operation. HANARO was experienced in a nuisance trip as often as the unexpected voltage sag and/or momentary interruption occurs. We installed the voltage sag compensator voltage sag assessment of the AC coil contactor which is a component of the power supply unit for the SORs. The compensation time is determined to be less than 1 sec in consideration of the reactor safety. This paper is concerned with the impact of the momentary interruption on the reactor and the effect of the voltage sag compensator

  13. KS-150 reactor control

    International Nuclear Information System (INIS)

    Wagner, K.

    1974-01-01

    A thorough description is presented of the control and protection system of the Bohunice A-1 reactor. The system including auxiliary facilities was developed, manufactured and installed at the reactor by the SKODA Works, Plzen. The system parameters are listed and a brief account is also given of the development efforts and of the physical and power start-up of the A-1 nuclear power plant. (L.O.)

  14. Safety of nuclear installations

    International Nuclear Information System (INIS)

    Esteves, R.G.

    1987-01-01

    The safety philosophy of a PWR type reactor distinguishing three levels of safety, is presented. At the first level, the concept of reactivity defining coefficients which measure the reactivity variation is introduced. At the second level, the reactor protection system establishing the design criteria to assure the high reliability, is defined. At the third level, the protection barriers to contain the consequences of accident evolution, are defined. (M.C.K.) [pt

  15. Backfitting of the FRG reactors

    International Nuclear Information System (INIS)

    Krull, W.

    1990-01-01

    The FRG-research reactors The GKSS-research centre is operating two research reactors of the pool type fueled with MTR-type type fuel elements. The research reactors FRG-1 and FRG-2 having power levels of 5 MW and 15 MW are in operation for 31 year and 27 years respectively. They are comparably old like other research reactors. The reactors are operating at present at approximately 180 days (FRG-1) and between 210 and 250 days (FRG-2) per year. Both reactors are located in the same reactor hall in a connecting pool system. Backfitting measures are needed for our and other research reactors to ensure a high level of safety and availability. The main backfitting activities during last ten years were concerned with: comparison of the existing design with today demands (criteria, guidelines, standards etc.); and probability approach for events from outside like aeroplane crashes and earthquakes; the main accidents were rediscussed like startup from low and full power, loss of coolant flow, loss of heat sink, loss of coolant and fuel plate melting; a new reactor protection system had to be installed, following today's demands; a new crane has been installed in the reactor hall. A cold neutron source has been installed to increase the flux of cold neutrons by a factor of 14. The FRG-l is being converted from 93% enriched U with Alx fuel to 20% enriched U with U 3 Si 2 fuel. Both cooling towers were repaired. Replacement of instrumentation is planned

  16. Capping off installation

    CERN Multimedia

    2006-01-01

    Installation of the cathode strip chambers for the muon system on the CMS positive endcap has been completed. Technicians install one of the last muon system cathode strip chambers on the CMS positive endcap. Like successfully putting together the pieces of a giant puzzle, installation of the muon system cathode strip chambers on one of the CMS endcaps has been completed. Total installation of the cathode strip chambers (CSC) is now 91 percent complete; only one ring of chambers needs to be mounted on the remaining endcap to finish installation of the entire system. To guarantee a good fit for the 468 total endcap muon system CSCs, physicists and engineers from the collaboration spent about 10 years carefully planning the design. The endcap muon system's cables, boxes, pipes and other parts were designed and integrated using a 3D computerized model. 'It took a long time to do all the computer modelling, but in the long run it saved us an enormous amount of time because it meant that everything fit together,...

  17. Python Introduction and Installation

    Directory of Open Access Journals (Sweden)

    William J. Turkel

    2012-07-01

    Full Text Available This first lesson in our section on dealing with Online Sources is designed to get you and your computer set up to start programming. We will focus on installing the relevant software – all free and reputable – and finally we will help you to get your toes wet with some simple programming that provides immediate results. In this opening module you will install the Python programming language, the Beautiful Soup HTML/XML parser, and a text editor. Screencaps provided here come from Komodo Edit, but you can use any text editor capable of working with Python. Here’s a list of other options: Python Editors. Once everything is installed, you will write your first programs, “Hello World” in Python and HTML.

  18. Reactor core

    International Nuclear Information System (INIS)

    Matsuura, Tetsuaki; Nomura, Teiji; Tokunaga, Kensuke; Okuda, Shin-ichi

    1990-01-01

    Fuel assemblies in the portions where the gradient of fast neutron fluxes between two opposing faces of a channel box is great are kept loaded at the outermost peripheral position of the reactor core also in the second operation cycle in the order to prevent interference between a control rod and the channel box due to bending deformation of the channel box. Further, the fuel assemblies in the second row from the outer most periphery in the first operation cycle are also kept loaded at the second row in the second operation cycle. Since the gradient of the fast neutrons in the reactor core is especially great at the outer circumference of the reactor core, the channel box at the outer circumference is bent such that the surface facing to the center of the reactor core is convexed and the channel box in the second row is also bent to the identical direction, the insertion of the control rod is not interfered. Further, if the positions for the fuels at the outermost periphery and the fuels in the second row are not altered in the second operation cycle, the gaps are not reduced to prevent the interference between the control rod and the channel box. (N.H.)

  19. Siting of research reactors

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose of this document is to develop criteria for siting and the site-related design basis for research reactors. The concepts presented in this document are intended as recommendations for new reactors and are not suggested for backfitting purposes for facilities already in existence. In siting research reactors serious consideration is given to minimizing the effects of the site on the reactor and the reactor on the site and the potential impact of the reactor on the environment. In this document guidance is first provided on the evaluation of the radiological impact of the installation under normal reactor operation and accident conditions. A classification of research reactors in groups is then proposed, together with a different approach for each group, to take into account the relevant safety problems associated with facilities of different characteristics. Guidance is also provided for both extreme natural events and for man-induced external events which could affect the safe operation of the reactor. Extreme natural events include earthquakes, flooding for river or coastal sites and extreme meteorological phenomena. The feasibility of emergency planning is finally considered for each group of reactors

  20. Python Introduction and Installation

    OpenAIRE

    William J. Turkel; Adam Crymble

    2012-01-01

    This first lesson in our section on dealing with Online Sources is designed to get you and your computer set up to start programming. We will focus on installing the relevant software – all free and reputable – and finally we will help you to get your toes wet with some simple programming that provides immediate results. In this opening module you will install the Python programming language, the Beautiful Soup HTML/XML parser, and a text editor. Screencaps provided here come from Komodo ...

  1. Logistics of LEP installation

    International Nuclear Information System (INIS)

    Genier, C.; Capper, S.

    1988-01-01

    The size of the LEP project, coupled with the tight construction schedules, calls for organized planning, logistics, monitoring and control. This is being carried out at present using tools such as ORACLE the Relational Database Management System, running on a VAX cluster for data storage and transfer, micro-computers for on-site follow-up, and PC's running Professional ORACLE, DOS and XENIX linked to a communications network to receive data feedback concerning transport and handling means. Following over 2 years of installations, this paper presents the methods used for the logistics of installation and their results

  2. Electrical installations technology

    CERN Document Server

    Whitfield, J F

    1968-01-01

    Electrical Installations Technology covers the syllabus of the City and Guilds of London Institute course No. 51, the "Electricians B Certificate”. This book is composed of 15 chapters that deal with basic electrical science and electrical installations. The introductory chapters discuss the fundamentals and basic electrical principles, including the concept of mechanics, heat, magnetic fields, electric currents, power, and energy. These chapters also explore the atomic theory of electric current and the electric circuit, conductors, and insulators. The subsequent chapter focuses on the chemis

  3. Field installation and maintenance

    International Nuclear Information System (INIS)

    Prebble, R.E.

    1981-01-01

    The use of a neutron moisture meter for the determination of the water content of soil necessitates the installation of an access tube down which the probe can be lowered. Errors in neutron count rate will be introduced if water enters the air gap between a loose fitting tube and the soil. Errors may also be caused by changes in the soil structure resulting from the techniques for soil removal and from driving the access hole. Access tube materials and dimensions, methods of installation and maintenance of the site are discussed

  4. Reactor BR2: Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. A safety audit was conduced by the IAEA, the conclusions of which demonstrated the excellent performance of the plant in terms of operational safety. In 1999, the CALLISTO facility was extensively used for various programmes involving LWR pressure vessel materials, IASCC of LWR structural materials, fusion reactor materials and martensic steels for use in ADS systems. In 1999, BR2's commercial programmes were further developed

  5. Reactors of the world

    International Nuclear Information System (INIS)

    1971-01-01

    Basic data relating to 127 power reactors in 15 countries which are expected to be in operation at the end of this year, with a total installed electrical generating capacity of 35 340.15 MW(e), and a listing of 361 research reactors in 46 countries are given in the 1971 edition of the IAEA handbook, Power and Research Reactors in Member States, which has just been published. This edition, the fourth, was prepared especially for the Fourth International Conference on the Peaceful Uses of Atomic Energy. (author)

  6. Sodium cooled fast reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hokkyo, N; Inoue, K; Maeda, H

    1968-11-21

    In a sodium cooled fast neutron reactor, an ultrasonic generator is installed at a fuel assembly hold-down mechanism positioned above a blanket or fission gas reservoir located above the core. During operation of the reactor an ultrsonic wave of frequency 10/sup 3/ - 10/sup 4/ Hz is constantly transmitted to the core to resonantly inject the primary bubble with ultrasonic energy to thereby facilitate its growth. Hence, small bubbles grow gradually to prevent the sudden boiling of sodium if an accident occurs in the cooling system during operation of the reactor.

  7. Reactor Vessel Surveillance Program for Advanced Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyeong-Hoon; Kim, Tae-Wan; Lee, Gyu-Mahn; Kim, Jong-Wook; Park, Keun-Bae; Kim, Keung-Koo

    2008-10-15

    This report provides the design requirements of an integral type reactor vessel surveillance program for an integral type reactor in accordance with the requirements of Korean MEST (Ministry of Education, Science and Technology Development) Notice 2008-18. This report covers the requirements for the design of surveillance capsule assemblies including their test specimens, test block materials, handling tools, and monitors of the surveillance capsule neutron fluence and temperature. In addition, this report provides design requirements for the program for irradiation surveillance of reactor vessel materials, a layout of specimens and monitors in the surveillance capsule, procedures of installation and retrieval of the surveillance capsule assemblies, and the layout of the surveillance capsule assemblies in the reactor.

  8. Burnable absorber for the PIK reactor

    International Nuclear Information System (INIS)

    Gostev, V.V.; Smolskii, S.L.; Tchmshkyan, D.V.; Zakharov, A.S.; Zvezdkin, V.S.; Konoplev, K.A.

    1998-01-01

    In the reactor PIK design a burnable absorber is not used and the cycle duration is limited by the rods weight. Designed cycle time is two weeks and seams to be not enough for the 100 MW power research reactor equipped by many neutron beams and experimental facilities. Relatively frequent reloading reduces the reactor time on full power and in this way increases the maintenance expenses. In the reactor core fuel elements well mastered by practice are used and its modification was not approved. We try to find the possibilities of installation in the core separate burnable elements to avoid poison of the fuel. It is possible to replace a part of the fuel elements by absorbers, since the fuel elements are relatively small (diameter 5.15mm, uranium 235 content 7.14g) and there are more then 3800 elements in the core. Nevertheless, replacing decreases the fuel burnup and its consumption. In the PIK fuel assembles a little part of the volume is occupied by the dumb elements to create a complete package of the assembles shroud, that is necessary in the hydraulic reasons. In the presented report the assessment of such a replacement is done. As a burnable material Gadolinium was selected. The measurements or the beginning of cycle were performed on the critical facility PIK. The burning calculation was confirmed by measurements on the 18MW reactor WWR-M. The results give the opportunity to twice the cycle duration. The proposed modification of the fuel assembles does not lead to alteration in the other reactor systems, but it touch the burned fuel reprocessing technology. (author)

  9. Nuclear Installations Act 1969

    International Nuclear Information System (INIS)

    1969-01-01

    The purpose of this Act is to amend the Nuclear Installations Act 1965 to bring it into full compliance with the international conventions on nuclear third party liability to which the United Kingdom is a Signatory, namely, the Paris Convention, the Brussels Supplementary Convention and the Vienna Convention. (NEA) [fr

  10. Code on the safety of civilian nuclear fuel cycle installations

    International Nuclear Information System (INIS)

    1996-01-01

    The 'Code' was promulgated by the National Nuclear Safety Administration (NSSA) on June 17, 1993, which is applicable to civilian nuclear fuel fabrication, processing, storage and reprocessing installations, not including the safety requirements for the use of nuclear fuel in reactors. The contents of the 'Code' involve siting, design, construction, commissioning, operation and decommissioning of fuel cycle installation. The NNSA shall be responsible for the interpretation of this 'Code'

  11. Holding of the public hearing concerning the alteration in reactor installations (addition of Unit 3 and 4) in the Genkai Nuclear Power Station of Kyushu Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1984-01-01

    The Nuclear Safety Commission held a public hearing concerning the addition of Unit 3 and 4 in Kyushu Electric's Genkai Nuclear Power Station in Karatsu City, Saga prefecture, on June 18th, 1984. The selected persons (and other attendants) expressed opinions etc. and personnel in the Ministry of International Trade and Industry answered them. Results of the public hearing are to be taken into conservation in NSC's safety examination. The following are described concerning the public hearing held: date and place, participants, hearing program, documents distributed, names of the persons expressing opinions etc. and the respective summary items of opinions etc. (Mori, K.)

  12. Reactor core cooling device

    International Nuclear Information System (INIS)

    Kobayashi, Masahiro.

    1986-01-01

    Purpose: To safely and effectively cool down the reactor core after it has been shut down but is still hot due to after-heat. Constitution: Since the coolant extraction nozzle is situated at a location higher than the coolant injection nozzle, the coolant sprayed from the nozzle, is free from sucking immediately from the extraction nozzle and is therefore used effectively to cool the reactor core. As all the portions from the top to the bottom of the reactor are cooled simultaneously, the efficiency of the reactor cooling process is increased. Since the coolant extraction nozzle can be installed at a point considerably higher than the coolant injection nozzle, the distance from the coolant surface to the point of the coolant extraction nozzle can be made large, preventing cavitation near the coolant extraction nozzle. Therefore, without increasing the capacity of the heat exchanger, the reactor can be cooled down after a shutdown safely and efficiently. (Kawakami, Y.)

  13. Influence of temperature measurement accuracy and reliability on WWER-440 reactor operation

    International Nuclear Information System (INIS)

    Petenyi, V.; Ricany, J.

    2001-01-01

    The WWER-440 reactor power is controlled by coolant heat-up measurements installed on hot and cold circulation loops (enthalpy rise). For power distribution determination the thermocouples installed in reactor vessel above the fuel assemblies are mainly utilised. The paper shortly presents some interesting observations of temperature measurements influencing the reactor power operation of revealed changes in reactor core behaviour. (Authors)

  14. The latest electrical installation (I)

    International Nuclear Information System (INIS)

    Won, Jong Su

    1976-04-01

    This book deals with the latest electrical installation. The contents of this book are construction electrical installation, regulations related electrical installation, foundation and principle of wiring, main line feeder, lighting installation, power of wiring, main line feeder, lighting installation, power installation, method to read structure drawing for electrical construct drawing electric lamp wiring diagram, working drawing, material and tools and method of construction of electrical installation on types of wiring construction, metallic conduit, rigid poly-vinyl conduit wiring, bus duct work, cable work and insulation out of metal lathed.

  15. BROOKHAVEN: RHIC installation

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    This summer, the first superconducting magnet was installed in 3.8 kilometre tunnel for Brookhaven's RHIC heavy ion collider (October, page 31). Manufactured by Northrop Grumman's Electronics and System Integration Division, the magnet is the first of RHIC's 373 dipoles. In addition to the dipoles, Northrop Grumman will also provide 432 RHIC quadrupoles. The first quadrupole was delivered on 8 April, a month before the first dipole arrived for onsite testing prior to installation. RHIC will need 1,700 superconducting magnets - dipoles, quadrupoles, sextupoles and correcting magnets, 1,200 of which will be built by industry and the rest built at Brookhaven. The 300 sextupoles are being supplied by Everson Electric

  16. Entropy and Digital Installation

    Directory of Open Access Journals (Sweden)

    Susan Ballard

    2005-01-01

    Full Text Available This paper examines entropy as a process which introduces ideas of distributed materiality to digital installation. Beginning from an analysis of entropy as both force and probability measure within information theory and it’s extension in Ruldof Arnheim’s text ‘Entropy and Art” it develops an argument for the positive rather thannegative forces of entropy. The paper centres on a discussion of two recent works by New Zealand artists Ronnie van Hout (“On the Run”, Wellington City Gallery, NZ, 2004 and Alex Monteith (“Invisible Cities”, Physics Room Contemporary Art Space, Christchurch, NZ, 2004. Ballard suggests that entropy, rather than being a hindrance to understanding or a random chaotic force, discloses a necessary and material politics of noise present in digital installation.

  17. Installation Strategic Planning Guidebook

    Science.gov (United States)

    2012-05-01

    Installation natural resource concerns (for example, wetlands , number of endangered species, water use restrictions, encroachment on training lands...Koehler Publishing, 1994 7. Strategy Safari – A Guided Tour Through the Wilds of Strategic Management by Henry Mintzberg, Bruce Ahlstrand, and...T. (1987). NY: Knopf 36. Shaping Strategic Planning: Frogs, Dragons, Bees and Turkey Tails. Pfeiffer, J. W., Goodstein, L. D. & Nolan, T. M. (1989

  18. Installing the ALICE detector

    CERN Multimedia

    Maximilien Brice

    2006-01-01

    The huge iron yoke in the cavern at Point 2 in the LHC tunnel is prepared for the installation of the ALICE experiment. The yoke is being reused from the previous L3 experiment that was located at the same point during the LEP project from 1989 to 2000. ALICE will be inserted piece by piece into the cradle where it will be used to study collisions between two beams of lead ions.

  19. SNRIU nuclear installation modifications

    International Nuclear Information System (INIS)

    Goroshanskyi, Andrii

    2013-01-01

    Design stages of Nuclear Instalations (NI): NI design is performed in three stages: • Feasibility study: - Feasibility study is developed on the basis of the customer task for production facilities and linear facilities engineering and transport infrastructure that require detailed study of relevant decisions and identify options for and feasibility of construction. • Design: - The design is developed on the basis of design task, initial data and approved the previous stage under three-stage design. • Detailed documentation

  20. Safety of nuclear installations

    International Nuclear Information System (INIS)

    1991-01-01

    In accordance with the Nuclear Energy Act, a Licence may only be issued if the precautions required by the state of the art have been taken to prevent damage resulting from the construction and operation of the installation. The maximum admissible body doses in the area around the installation which must be observed in planning constructional and other technical protective measures to counter accidents in or at a nuclear power station (accident planning values, are established). According to the Radiological Protection Ordinance the Licensing Authority can consider these precautions to have been taken if, in designing the installation against accidents, the applicant has assumed the accidents which, according to the Safety Criteria and Guidelines for Nuclear Power Stations published in the Federal Register by the Federal Minister of the Interior after hearing the competent senior state authorities, must determine the design of a nuclear power station. On the basis of previous experience from safety analysis, assessment and operation of nuclear power stations, the accident guidelines published here define which accidents are determinative for the safety-related design of PWR power stations and what verification -particularly with regard to compliance with the accident planning values of the Radiological Protection Ordinance -must be provided by the applicant. (author)

  1. First ALICE detectors installed!

    CERN Multimedia

    2006-01-01

    Detectors to track down penetrating muon particles are the first to be placed in their final position in the ALICE cavern. The Alice muon spectrometer: in the foreground the trigger chamber is positioned in front of the muon wall, with the dipole magnet in the background. After the impressive transport of its dipole magnet, ALICE has begun to fill the spectrometer with detectors. In mid-July, the ALICE muon spectrometer team achieved important milestones with the installation of the trigger and the tracking chambers of the muon spectrometer. They are the first detectors to be installed in their final position in the cavern. All of the eight half planes of the RPCs (resistive plate chambers) have been installed in their final position behind the muon filter. The role of the trigger detector is to select events containing a muon pair coming, for instance, from the decay of J/ or Y resonances. The selection is made on the transverse momentum of the two individual muons. The internal parts of the RPCs, made o...

  2. Nuclear reactor

    International Nuclear Information System (INIS)

    Irion, L.; Tautz, J.; Ulrych, G.

    1976-01-01

    This additional patent complements the arrangement of non-return valves to prevent loss of cooling water on fracture of external tubes in the main coolant circuit (according to PS 24 24 427.7) by ensuring that the easily movable valves only operate in case of a fault, but do not flutter in operation, because the direction of flow is not the same at each location where they are installed. The remedy for this undesirable effect consists of allocating 1 non-return valve unit with 5 to 10 valves to each (of several) ducts for the cooling water intake. These units are installed in the annular space between the reactor vessel and the pressure vessel below the inlet of the ducts. Due to flow guidance surfaces in the same space, the incoming cooling water is deflected downwards and as the guiding surfaces are closed at the sides, must pass parallel to the valves of the non-return valve unit. On fracture of the external cooling water inlet pipe concerned, all valves of this unit close due to reversal of flow on the outlet side. (TK) [de

  3. The program of reactors and nuclear power plants

    International Nuclear Information System (INIS)

    Calabrese, Carlos R.

    2001-01-01

    Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined

  4. The effect of heavy water reactors and liquid fuel reactors on the long-term development of nuclear energy

    International Nuclear Information System (INIS)

    Brand, P.; Wiechers, W.K.

    1974-01-01

    The effects of the rates at which various combinations of power reactor types are installed on the long-range (to the year 2040) uranium and plutonium inventory requirements are examined. Consideration is given to light water reactors, fast breeder reactors, high temperature gas-cooled reactors, heavy water reactors, and thermal breeder reactors, in various combinations, and assuming alternatively a 3% and a 5% growth in energy demand

  5. Samus Toroid Installation Fixture

    Energy Technology Data Exchange (ETDEWEB)

    Stredde, H.; /Fermilab

    1990-06-27

    The SAMUS (Small Angle Muon System) toroids have been designed and fabricated in the USSR and delivered to D0 ready for installation into the D0 detector. These toroids will be installed into the aperture of the EF's (End Toroids). The aperture in the EF's is 72-inch vertically and 66-inch horizontally. The Samus toroid is 70-inch vertically by 64-inch horizontally by 66-inch long and weighs approximately 38 tons. The Samus toroid has a 20-inch by 20-inch aperture in the center and it is through this aperture that the lift fixture must fit. The toroid must be 'threaded' through the EF aperture. Further, the Samus toroid coils are wound about the vertical portion of the aperture and thus limit the area where a lift fixture can make contact and not damage the coils. The fixture is designed to lift along a surface adjacent to the coils, but with clearance to the coil and with contact to the upper steel block of the toroid. The lift and installation will be done with the 50 ton crane at DO. The fixture was tested by lifting the Samus Toroid 2-inch off the floor and holding the weight for 10 minutes. Deflection was as predicted by the design calculations. Enclosed are sketches of the fixture and it relation to both Toroids (Samus and EF), along with hand calculations and an Finite Element Analysis. The PEA work was done by Kay Weber of the Accelerator Engineering Department.

  6. Fires of sodium installations

    International Nuclear Information System (INIS)

    Hajek, L.; Tlalka, R.

    1984-01-01

    A survey is presented of the literature dealing with fires of sodium installations between 1974 and 1981. Also described are three experimental fires of ca 50 kg of sodium in an open area, monitored by UJV Rez. The experimental conditions of the experiments are described and a phenomenological description is presented of the course of the fires. The experiments showed a relationship between wind velocity in the area surrounding the fire and surface temperature of the sodium flame. Systems analysis methods were applied to sodium area, spray and tube fires. (author)

  7. Worldwide installed geothermal power

    International Nuclear Information System (INIS)

    Laplaige, P.

    1995-01-01

    Worldwide electric energy production data are easy to compile, according to the informations given by individual countries. On the contrary, thermal applications of geothermics are difficult to quantify due to the variety of applications and the number of countries concerned. Exhaustive informations sometimes cannot be obtained from huge countries (China, Russia..) because of data centralization problems or not exploitable data transmission. Therefore, installed power data for geothermal heat production are given for 26 countries over the 57 that have answered the International Geothermal Association questionnaire. (J.S.). 1 fig., 2 tabs., 1 photo

  8. Wireless installation standard

    International Nuclear Information System (INIS)

    Lim, Hwang Bin

    2007-12-01

    This is divided six parts which are radio regulation law on securing of radio resource, use of radio resource, protection of radio resource, radio regulation enforcement ordinance with securing, distribution and assignment of radio regulation, radio regulation enforcement regulation on utility of radio resource and technical qualification examination, a wireless installation regulation of technique standard and safety facility standard, radio regulation such as certification regulation of information communicative machines and regulation of radio station on compliance of signal security, radio equipment in radio station, standard frequency station and emergency communication.

  9. Nuclear installations sites safety

    International Nuclear Information System (INIS)

    Barber, P.; Candes, P.; Duclos, P.; Doumenc, A.; Faure, J.; Hugon, J.; Mohammadioun, B.

    1988-11-01

    This report is divided into ten parts bearing: 1 Safety analysis procedures for Basis Nuclear Installations sites (BNI) in France 2 Site safety for BNI in France 3 Industrial and transport activities risks for BNI in France 4 Demographic characteristics near BNI sites in France 5 Meteorologic characteristics of BNI sites in France 6 Geological aspects near the BNI sites in France 7 Seismic studies for BNI sites in France 8 Hydrogeological aspects near BNI sites in France 9 Hydrological aspects near BNI sites in France 10 Ecological and radioecological studies of BNI sites in France [fr

  10. VG-400 atomic power and technological installation. Possible core design

    International Nuclear Information System (INIS)

    Komarov, E.V.; Laptev, F.V.; Lyubivyj, A.G.; Mitenkov, F.M.; Samojlov, O.B.; Sukhachevskij, Yu.B.

    1979-01-01

    The main characteristics, basic circuit and configuration of equipment of the VG-400 atomic power and technological installation are considered. This installation is intended for supplying with highly-potential heat of thermal electrochemical hydrogen production and for power generation in the steam-turbine cycle. The main installation characteristics: HTGR reactor heat power 1100 MW, electric power 300 MW, helium coolant pressure 50 atm, output temperature 950 deg C, steam pressure in the second contour 175 atm, temperature 535 deg C, core diameter and height 6.4 m and 4 m, respectively, number of spherical fuel elements 8.5x10 5 . The installation can ensure hydrogen production of 10 5 Nxm 3 /h. For the VG-400 reactor block the integral arrangement of the first circuit equipment in the reinforced concrete is chosen. Two versions of the reactor core with prismatic and spherical fuel elements are compared. It is shown that taking into account great potentialities of the spherical zone in a case of further temperature increase and its positive qualities with respect to construction and processing of fuel elements and graphite blocks, the utilization of simplier units and mechanisms in the overloading system and in the process of profiling of energy distribution the choice of the spherical configuration for the VG-400 pilot plant installation seems to be valid

  11. Performance of buried pipe installation.

    Science.gov (United States)

    2010-05-01

    The purpose of this study is to determine the effects of geometric and mechanical parameters : characterizing the soil structure interaction developed in a buried pipe installation located under : roads/highways. The drainage pipes or culverts instal...

  12. Assembly and Installation of the Daya Bay Antineutrino Detectors

    International Nuclear Information System (INIS)

    Band, H R; Heeger, K M; Hinrichs, P; Brown, R L; Gill, R; Carr, R; Dwyer, D A; Chen, X C; Chu, M C; Chen, X H; Heng, Y K; Cherwinka, J J; Greenler, L S; Draeger, E; Edwards, W R; Hoff, M; Goett, J; Gu, W Q; Ho, T H; He, W S

    2013-01-01

    The Daya Bay reactor antineutrino experiment is designed to make a precision measurement of the neutrino mixing angle θ 13 , and recently made the definitive discovery of its non-zero value. It utilizes a set of eight, functionally identical antineutrino detectors to measure the reactor flux and spectrum at baselines of ∼ 300–2000 m from the Daya Bay and Ling Ao Nuclear Power Plants. The Daya Bay antineutrino detectors were built in an above-ground facility and deployed side-by-side at three underground experimental sites near and far from the nuclear reactors. This configuration allows the experiment to make a precision measurement of reactor antineutrino disappearance over km-long baselines and reduces relative systematic uncertainties between detectors and nuclear reactors. This paper describes the assembly and installation of the Daya Bay antineutrino detectors

  13. Backfitting of research reactors

    International Nuclear Information System (INIS)

    Delrue, R.; Noesen, T.

    1985-01-01

    The backfitting of research reactors covers a variety of activities. 1. Instrumentation and control: Control systems have developed rapidly and many reactor operators wish to replace obsolete equipment by new systems. 2. Pool liners: Some pools are lined internally with ceramic tiles. These may become pervious with time necessitating replacement, e.g. by a new stainless steel liner. 3. Heat removal system: Deficiencies can occur in one or more of the cooling system components. Upgrading may require modifications of the system such as addition of primary loops, introduction of deactivation tanks, pump replacement. Recent experience in such work has shown that renewal, backfitting and upgrading of an existing reactor is economically attractive since the related costs and delivery times are substantially lower than those required to install a new research reactor

  14. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2002-01-01

    The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system

  15. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2002-04-01

    The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system.

  16. CNGS Reflector installed

    CERN Multimedia

    2006-01-01

    A major component that will help target the CNGS neutrino beam for its 732km journey through the earth's crust, from CERN to the Gran Sasso laboratory in Italy, has been installed in its final position. The transport of the huge magnetic horn reflector through the CNGS access gallery. A team from CNGS and TS/IC, and the contractors DBS, transported the magnetic horn reflector on 5th December, in a carefully conducted operation that took just under two hours. The reflector is 7m long, 1.6m in diameter and 1.6 tonnes in weight. With only a matter of centimetres to spare on either side, the reflector was transported through the CNGS access gallery, before being installed in the experiment's target chamber. The larger of two magnetic horns, the reflector will help refocus sprays of high energy pions and kaons emitted after a 0.5MW stream of protons from the Super Proton Synchrotron (SPS) strikes nucleons in a graphite target. The horns are toroidal magnetic lenses and work with high pulsed currents: 150 kA f...

  17. Project 'Installation of a stand at the horizontal channel of the MARIA Research Reactor, Otwock-Swierk, Poland, for the research of transmutation of minor actinides and fission products'

    International Nuclear Information System (INIS)

    Szuta, M.

    2006-01-01

    international reputation in the field of energy production and transmutation and reactor physics computations. In order to analyse this topic experimentally, we propose to replace the expensive spallation source requiring accelerator by the neutron source obtained by converting the thermal neutron flux from the horizontal channel of the research reactor MARIA into fast neutron source. Taking into account the large amount of thermal neutrons in the horizontal channel, it is possible to use a fission converter i.e. an arrangement containing 235 U placed in the axis of the horizontal channel mouth. Thermal neutrons cause the fission reactions producing fast neutrons, which will be used instead of the neutrons from the spallation source. Five fuel rods of EK-10 type fuel placed vertically respect the beam of the thermal neutron flux of the used horizontal channel constitutes the converter. From the preliminary calculations it follows that the fast neutron source is approximately equal to 2 x 10 10 neutrons/s. A natural metallic uranium blanket with a moderator island will surround the fast neutron source what will enable us to perform the transmutation investigation of minor actinides (MA) and the long lived fission products (LLFP) in a wide range neutron energy spectrum. In such a system the mass of the 235 U will be deeply sub-critical

  18. Installation for rewetting experiments

    International Nuclear Information System (INIS)

    Rezende, H.C.; Ladeira, L.C.D.

    1986-03-01

    A test facility for rewetting experiments (ITR), has been erected at the Thermalhydraulics Laboratory of Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), with the objective of performing investigation of basic phenomena that occur during the reflood phase of a Loss of Coolant Accident (LOCA), in a Pressurized Water Reactor (PWR), utilizing tubular and annular test sections. The mechanical aspects of the facility, its power supply system and its instrumentation are described. The results of the calibration of the instruments and the description of two typical testes performed to verify the operational conditions are presented. A comparison with calculations using a computer code is also presented. (Author) [pt

  19. Prospects for inherently safe reactors

    International Nuclear Information System (INIS)

    Barkenbus, J.N.

    1988-01-01

    Public fears over nuclear safety have led some within the nuclear community to investigate the possibility of producing inherently safe nuclear reactors; that is, reactors that are transparently incapable of producing a core melt. While several promising designs of such reactors have been produced, support for large-scale research and development efforts has not been forthcoming. The prospects for commercialization of inherently safe reactors, therefore, are problematic; possible events such as further nuclear reactor accidents and superpower summits, could alter the present situation significantly. (author)

  20. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

    After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

  1. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Oeen, Sigrun; Iversen, Per Erik; Stokke, Reidunn; Nielsen, Frantz; Henriksen, Thor; Natvig, Henning; Dretvik, Oeystein; Martinsen, Finn; Bakke, Gunnstein

    2010-07-01

    New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures

  2. Optimised utilisation of existing incinerators by installation of upstream reactors for treatment of waste with high calorifica value - HYBRID waste treatment plants; Optimierte Nutzung bestehender Abfallverbrennungsanlagen durch Errichtung vorgeschalteter Reaktoren zur Behandlung heizwertreicher Abfaelle - HYBRID-Abfallbehandlungsanlagen

    Energy Technology Data Exchange (ETDEWEB)

    El Labani, M

    2000-07-01

    Waste incineration plants are based on the process of thermal waste treatment, i.e. the generation of power from the controlled conversion of organic reactive residue waste. Statutory requirements forced operators to install powerful flue gas cleaning systems into their existing waste incineration plants. This led to a tremendous increase in cost and treatment prices generating pressure to optimize the process. Currently, markets demand additional capacities for the treatment of waste of elevated heating value ({proportional_to}5,0 MWh/Mg). It is possible to treat this type of waste in a conventional waste incineration plant. However, the elevated heating value dictates a reduction in throughput with ever increasing pressure on costs. This is why current concepts consider the treatment of waste of elevated heating value in specific, so called de-centralized plants. These plants are usually of low throughput with accordingly high specific cost of developing the infrastructure. The capacity of existing waste incineration plants has been investigated in order to assess the potential for optimization. Extensive test runs at the Municipal Solid Waste Incineration Plant (MSW) Darmstadt revealed a capacity gap in the flue gas cleaning system even with the incineration unit running at full capacity. This gap could be filled with an additional incineration plant for waste of elevated heating value, whose capacity is matched accordingly. Such additional incineration plant defines in conjunction with the existing waste incineration plant a so called HYBRID Waste Treatment Plant. It is the aim of this treatise to develop an instrument to support the decision making process related to the planning of such plants. (orig.) [German] Abfallverbrennungsanlagen basieren auf dem Verfahren der thermischen Abfallbehandlung; das ist die Energieerzeugung aus der kontrollierten Umwandlung organischer, reaktionsfaehiger Restabfaelle. Aufgrund gesetzlicher Vorgaben mussten bestehende

  3. Reactor PIK construction

    International Nuclear Information System (INIS)

    Konoplev, Kir

    2003-01-01

    The construction work at the 100 MW researches reactor PIK in year 2002 was in progress. The main activity was concentrated on mechanical, ventilation and electrical equipment. Some systems and subsystems are under adjustment. Hydraulic driving gear for beam shutters are finished in installation, rinsing, and adjusting. Regulating rods test assembling was done. On the critical assembly the first reactor fueling was tested to evaluate the starting neutron source intensity and a sufficiency of existing control and instrument board. Mainline of the PIK facility design and neutron parameters are presented. (author)

  4. Backfitting of the FRG reactors

    Energy Technology Data Exchange (ETDEWEB)

    Krull, W [GKSS-Forschungszentrum Geesthacht GmbH, Geesthacht (Germany)

    1990-05-01

    The FRG-research reactors The GKSS-research centre is operating two research reactors of the pool type fueled with MTR-type type fuel elements. The research reactors FRG-1 and FRG-2 having power levels of 5 MW and 15 MW are in operation for 31 year and 27 years respectively. They are comparably old like other research reactors. The reactors are operating at present at approximately 180 days (FRG-1) and between 210 and 250 days (FRG-2) per year. Both reactors are located in the same reactor hall in a connecting pool system. Backfitting measures are needed for our and other research reactors to ensure a high level of safety and availability. The main backfitting activities during last ten years were concerned with: comparison of the existing design with today demands (criteria, guidelines, standards etc.); and probability approach for events from outside like aeroplane crashes and earthquakes; the main accidents were rediscussed like startup from low and full power, loss of coolant flow, loss of heat sink, loss of coolant and fuel plate melting; a new reactor protection system had to be installed, following today's demands; a new crane has been installed in the reactor hall. A cold neutron source has been installed to increase the flux of cold neutrons by a factor of 14. The FRG-l is being converted from 93% enriched U with Alx fuel to 20% enriched U with U{sub 3}Si{sub 2} fuel. Both cooling towers were repaired. Replacement of instrumentation is planned.

  5. Report of the reactor Operators Service - Annex F

    International Nuclear Information System (INIS)

    Zivotic, Z.

    1992-01-01

    RA reactor operators service is organized in two groups: permanent staff (chief operator, chief shift operators and operators) and changeable group which is formed according to the particular operation needs for working in shifts. For continuous training of the existing operator staff the Service has prepared and published eleven booklets: Nuclear reactor; RA reactor primary coolant loop; System for purification of heavy water; reactor helium system; system for technical water; electric power system; control and operation; ventilation system in the reactor building; special sewage system; construction properties of the reactor core; reactor building and installations. During the reporting period there have been no accidents nor incidents that could affect the reactor personnel [sr

  6. Mobile nuclear reactor containment vessel

    International Nuclear Information System (INIS)

    Thompson, R.E.; Spurrier, F.R.; Jones, A.R.

    1978-01-01

    A containment vessel for use in mobile nuclear reactor installations is described. The containment vessel completely surrounds the entire primary system, and is located as close to the reactor primary system components as is possible in order to minimize weight. In addition to being designed to withstand a specified internal pressure, the containment vessel is also designed to maintain integrity as a containment vessel in case of a possible collision accident

  7. H Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The H Reactor was the first reactor to be built at Hanford after World War II.It became operational in October of 1949, and represented the fourth nuclear reactor on...

  8. ROS Installation and Commissioning

    CERN Multimedia

    Gorini, B

    The ATLAS Readout group (a sub-group of TDAQ) has now completed the installation and commissioning of all of the Readout System (ROS) units. Event data from ATLAS is initially handled by detector specific hardware and software, but following a Level 1 Accept the data passes from the detector specific Readout Drivers (RODs) to the ROS, the first stage of the central ATLAS DAQ. Within the final ATLAS TDAQ system the ROS stores the data and on request makes it available to the Level 2 Trigger (L2) processors and to the Event Builder (EB) as required. The ROS is implemented as a large number of PCs housing custom built cards (ROBINs) and running custom multi-threaded software. Each ROBIN card (shown below) contains buffer memories to store the data, plus a field programmable gate array ( FPGA ) and an embedded PowerPC processor for management of the memories and data requests, and is implemented as a 64-bit 66 MHz PCI card. Both the software and the ROBIN cards have been designed and developed by the Readout g...

  9. The health physics of installations for decladding irradiated fuels or for handling radio-elements at Marcoule; La radioprotection des installations de degainage des combustibles irradies et des radio-elements a Marcoule

    Energy Technology Data Exchange (ETDEWEB)

    Chassany, J; Guillermin, P; Mallet, P [Commissariat a l' Energie Atomique, Centre de Production de Plutonium de Marcoule, 30 - Chusclan (France)

    1966-07-01

    Radiation protection practices for handling reactor fuel elements are described. Elements of considerable specific radioactivity are handled under water. A study was made of water filtration and of ventilation in the building. The installations are divided up into zones depending on the radioactive risks, and the radiation level atmospheric contamination are the object of a systematic control at various points. A description is given of all aspects of health physics which have been encountered during six years: storage, transfer of radioactive material; decladding, rolling, waste disposal, specialized operations, installations in operation and at rest, and transport. In spite of the gradual increase in the activity of these installations, the total doses received by the personnel have hardly altered and the number of cases of physical contamination has diminished. (authors) [French] Dans ces installations, se manipulent sous l'eau des elements a radioactivite specifique considerable. La filtration de l'eau, la ventilation ont ete particulierement etudiees. L'ensemble a ete divise en lieux classes en fonction des risques radioactifs et des appareils controlent en permanence l'irradiation et la contamination atmospherique en certains points. Tous les aspects de la radioprotection resultant de six annees d'experience relatifs: au stockage, au deconteneurage, au degainage, au laminage, a l'evacuation des residus, aux travaux particuliers, installations en marche et a l'arret, et aux transports sont successivement decrits. Malgre l'accroissement progressif de l'activite de cet ensemble, les doses integrees par le personnel n'ont pratiquement pas augmente et le nombre des cas de contamination corporelle a diminue. (auteurs)

  10. Installing Python Modules with pip

    OpenAIRE

    Fred Gibbs

    2013-01-01

    This lesson shows you how to download and install Python modules. There are many ways to install external modules, but for the purposes of this lesson, we’re going to use a program called pip. As of Python 2.7.9 and newer, pip is installed by default. This tutorial will be helpful for anyone using older versions of Python (which are still quite common).

  11. Nuclear installations abroad the accident risks and their potential consequences

    International Nuclear Information System (INIS)

    Turvey, F.J.

    1996-01-01

    This paper endeavors to assess the threat to Ireland from severe accidents at civil nuclear installations. Among the various types of nuclear installations worldwide, reactors and reprocessing plants are considered to be the most threatening and so the paper focuses on these. The threat is assumed to be a function of the risk of severe accidents at the above types of installations and the probability of unfavourable weather conditions carrying the radioactive releases to Ireland. Although nuclear installations designed in eastern Europe and Asia are less safe than others, the greatest threat to Ireland arises from nearby installations in the UK. The difficulty of measuring the probabilities and consequences of severe nuclear accidents at nuclear installations in general is explained. In the case of the UK installations, this difficulty is overcome to some degree by using values of 'tolerable' risk adopted by the national nuclear regulator to define the radiotoxic releases from nuclear accidents. These are used as input to atmospheric dispersion models in which unfavourable weather conditions for Ireland are assumed and radiation doses are calculated to members of the Irish public. No countermeasures, such as sheltering, are assumed. In the worst cast scenario no deaths would be expected in Ireland in the immediate aftermath of the accident however, an increase in cancers over a period of 25 years or so would be expected assuming present-day models for the effect of low level radiation are valid

  12. Nuclear installations abroad the accident risks and their potential consequences

    Energy Technology Data Exchange (ETDEWEB)

    Turvey, F J [Radiological Protection Inst. of Ireland (Ireland)

    1996-10-01

    This paper endeavors to assess the threat to Ireland from severe accidents at civil nuclear installations. Among the various types of nuclear installations worldwide, reactors and reprocessing plants are considered to be the most threatening and so the paper focuses on these. The threat is assumed to be a function of the risk of severe accidents at the above types of installations and the probability of unfavourable weather conditions carrying the radioactive releases to Ireland. Although nuclear installations designed in eastern Europe and Asia are less safe than others, the greatest threat to Ireland arises from nearby installations in the UK. The difficulty of measuring the probabilities and consequences of severe nuclear accidents at nuclear installations in general is explained. In the case of the UK installations, this difficulty is overcome to some degree by using values of `tolerable` risk adopted by the national nuclear regulator to define the radiotoxic releases from nuclear accidents. These are used as input to atmospheric dispersion models in which unfavourable weather conditions for Ireland are assumed and radiation doses are calculated to members of the Irish public. No countermeasures, such as sheltering, are assumed. In the worst cast scenario no deaths would be expected in Ireland in the immediate aftermath of the accident however, an increase in cancers over a period of 25 years or so would be expected assuming present-day models for the effect of low level radiation are valid.

  13. The control of base nuclear installations; Le controle des installations nucleaires de base (INB)

    Energy Technology Data Exchange (ETDEWEB)

    Anon

    2009-04-15

    The Authority of Nuclear Safety ( A.S.N). presents in this column the current events of the control of the nuclear base installations during november, december 2008 and january 2009, classified by nuclear site. This information is also available in real-time on the A.S.N. web site, www.asn.fr, in the column 'news'. We can consult all the notices of significant incident published as well as the following letters of inspection, the notices of information about the reactors shutdown, press releases and the A.S.N. information notes. (N.C.)

  14. Results of assembly test of HTTR reactor internals

    International Nuclear Information System (INIS)

    Maruyama, S.; Saikusa, A.; Shiozawa, S.; Tsuji, N.; Miki, T.

    1996-01-01

    The assembly test of the HTTR actual reactor internals had been carried out at the works, prior to their installation in the actual reactor pressure vessel(RPV) at the construction site. The assembly test consists of several items such as examining fabricating precision of each component and alignment of piled-up structures, measuring circumferential coolant velocity profile in the passage between the simulated RPV and the reactor internals as well as under the support plates, measuring by-pass flow rate through gaps between the reactor internals, and measuring the binding force of the core restraint mechanism. Results of the test showed good performance of the HTTR reactor internals. Installation of the reactor internals in the actual RPV was started at the construction site of HTTR in April, 1995. In the installation process, main items of the assembly test at the works were repeated to investigate the reproducibility of installation. (author). 5 refs, 11 figs

  15. The reactor Phenix - cartridge rupture detection

    International Nuclear Information System (INIS)

    Graftieaux, J.

    1967-01-01

    This report defines the role of cartridge rupture detection in the reactor Phenix. It gives the possible methods, their probable performances, their advantages and disadvantages. The final form of the installation will be determined mainly by the degree of safety required, by the technical possibilities of the reactor design and by the operational flexibility wanted. (author) [fr

  16. Nuclear reactor containment device

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu.

    1980-01-01

    Purpose: To reduce the volume of a containment shell and decrease the size of a containment equipment for BWR type reactors by connecting the containment shell and a suppression pool with slanted vent tubes to thereby shorten the vent tubes. Constitution: A pressure vessel containing a reactor core is installed at the center of a building and a containment vessel for the nuclear reactor that contains the pressure vessel forms a cabin. To a building situated below the containment shell, is provided a suppression chamber in which cooling water is charged to form a suppression pool. The suppression pool is communicated with vent tubes that pass through the partition wall of the containment vessel. The vent tubes are slanted and their lower openings are immersed in coolants. Therefore, if accident is resulted and fluid at high temperature and high pressure is jetted from the pressure vessel, the jetting fluid is injected and condensated in the cooling water. (Moriyama, K.)

  17. Reactor safety analysis

    International Nuclear Information System (INIS)

    Arien, B.

    1998-01-01

    Risk assessments of nuclear installations require accurate safety and reliability analyses to estimate the consequences of accidental events and their probability of occurrence. The objective of the work performed in this field at the Belgian Nuclear Research Centre SCK-CEN is to develop expertise in probabilistic and deterministic reactor safety analysis. The four main activities of the research project on reactor safety analysis are: (1) the development of software for the reliable analysis of large systems; (2) the development of an expert system for the aid to diagnosis; (3) the development and the application of a probabilistic reactor-dynamics method, and (4) to participate in the international PHEBUS-FP programme for severe accidents. Progress in research during 1997 is described

  18. Natural convection type reactor

    International Nuclear Information System (INIS)

    Nakayama, Takafumi; Horiuchi, Tetsuo; Moriya, Kimiaki; Matsumoto, Masayoshi; Akita, Minoru.

    1988-01-01

    Purpose: To improve the reliability by decreasing the number of dynamic equipments and safely shutdown the reactor core upon occurrence of accidents. Constitution: A pressure relief valve and a pressurizing tank or gravitational water falling tank disposed to the main steam pipe of a reactor are installed in combination. Upon loss-of-coolant accident, the pressure relief valve is opened to reduce the pressure in the reactor pressure vessel to the operation pressure for each of the tanks, thereby enabling to inject water in the pressurizing tank at first and, thereafter, water in the gravitational water falling tank successively to the inside of the pressure vessel. By utilizing the natural force in this way, the reliability can be improved as compared with the case of pumped water injection. Further, by injecting an aqueous boric acid to a portion of a plurality of tanks, if the control rod insertion becomes impossible, aqueous boric acid can be injected. (Takahashi, M.)

  19. Technology of nuclear reactors

    International Nuclear Information System (INIS)

    Ravelet, F.

    2016-01-01

    This academic report for graduation in engineering first presents operation principles of a nuclear reactor core. It presents core components, atomic nuclei, the notions of transmutation and radioactivity, quantities used to characterize ionizing radiations, the nuclear fission, statistical aspects of fission and differences between fast and slow neutrons, a comparison between various heat transfer fluids, the uranium enrichment process, and different types of reactor (boiling water, natural uranium and heavy water, pressurized water, and fourth generation). Then, after having recalled the French installed power, the author proposes an analysis of a typical 900 MWe nuclear power plant: primary circuit, reactor, fuel, spent fuel, pressurizer and primary pump, secondary circuit, aspects related to control-command, regulation, safety and exploitation. The last part proposes a modelling of the thermodynamic cycle of a pressurized water plant by using an equivalent Carnot cycle, a Rankine cycle, and a two-phase expansion cycle with drying-overheating

  20. Nuclear research reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  1. RB research reactor safety report

    International Nuclear Information System (INIS)

    Sotic, O.; Pesic, M.; Vranic, S.

    1979-04-01

    This new version of the safety report is a revision of the safety report written in 1962 when the RB reactor started operation after reconstruction. The new safety report was needed because reactor systems and components have been improved and the administrative procedures were changed. the most important improvements and changes were concerned with the use of highly enriched fuel (80% enriched), construction of reactor converter outside the reactor vessel, improved control system by two measuring start-up channels, construction of system for heavy water leak detection, new inter phone connection between control room and other reactor rooms. This report includes description of reactor building with installations, rector vessel, reactor core, heavy water system, control system, safety system, dosimetry and alarm systems, experimental channels, neutron converter, reactor operation. Safety aspects contain analyses of accident reasons, method for preventing reactivity insertions, analyses of maximum hypothetical accidents for cores with natural uranium, 2% enriched and 80% enriched fuel elements. Influence of seismic events on the reactor safety and well as coupling between reactor and the converter are parts of this document

  2. Nuclear research reactors in Brazil

    International Nuclear Information System (INIS)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias

    2011-01-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  3. Reactor inventory monitoring system for Angra-1 reactor

    International Nuclear Information System (INIS)

    S Neto, Joaquim A.; Silva, Marcos C.; Pinheiro, Ronaldo F.M.; Soares, Milton; Martinez, Aquilino; Comerlato, Cesar A.; Oliveira, Eugenio A.

    1996-01-01

    This work describes the project of Reactor Inventory Monitoring System, which will be installed in Angra I Nuclear Power Plant. The inventory information is important to the operators take corrective actions in case of an incident that may cause a failure in the core cooling. (author)

  4. SIR - small is safe [in reactor design

    International Nuclear Information System (INIS)

    Hayns, M.

    1989-01-01

    A joint USA-UK venture has been initiated to design a small nuclear reactor which offers low capital cost, greater flexibility and a potentially lower environmental impact. Called Safe Integral Reactor (SIR), the lead unit could be built in the United Kingdom Atomic Energy Authority's (UKAEA's) Winfrith site if the design is accepted by the UK Nuclear Installations Inspectorate (NII). This article describes the 320 MWe reactor unit that is the basis of the design being developed. (author)

  5. Fuel assembly transfer and storage system for nuclear reactors

    International Nuclear Information System (INIS)

    Allain, Albert; Thomas, Claude.

    1981-01-01

    Transfer and storage system on a site comprising several reactors and at least one building housing the installations common to all these reactors. The system includes: transfer and storage modules for the fuel assemblies comprising a containment capable of containing several assemblies carried on a transport vehicle, a set of tracks for the modules between the reactors and the common installations, handling facilities associated with each reactor for moving the irradiated assemblies from the reactor to a transfer module placed in loading position on a track serving the reactor and conversely to move the new assemblies from the transfer module to the reactor, and at least one handling facility located in the common installation building for loading the modules with new assemblies [fr

  6. Nitrogen treatment from digestat of biogas plants in a moving bed biofilm reactor; Projet de recherche pilote. Traitement de l'azote des digestats issus d'installations de biogaz au moyen d'un reacteur a biofilm sur support mobile - Rapport final

    Energy Technology Data Exchange (ETDEWEB)

    Roches, S.; Bakx, T.; Membrez, Y. [EREP SA, Aclens (Switzerland); Baggenstos, M.; Chappaz, A. [Wabag Water Technology Ltd, Winterthur (Switzerland); Holliger, Ch. [Swiss Federal Institute of Technology, EPFL, Laboratory for Environmental Biotechnology, Lausanne (Switzerland)

    2010-11-15

    Ammonia emissions are a source for polluting ecosystems, causing in particular acidification and eutrophication of the affected areas. In Switzerland 90% of the atmospheric ammonia emissions are due to agriculture, mostly during storage and use of animal manures and slurries. Anaerobic digestion of these manures and slurries produces renewable energy and stabilises the agricultural effluents. However, it does not solve the ammonia problem; on the contrary, it releases an additional amount of ammonium while mineralizing a large part of the organic nitrogen. A previous study dealing with the biological removal of ammonia from digested manures was conducted at the Laboratory of Environmental Biotechnology, EPFL. It has shown that it is possible to obtain simultaneously a conversion of ammonium and nitrogen removal in a same continuously aerated aerobic reactor, using a mobile support for fixing the biomass. The obtained efficiencies were high, with 90% of the ammonium being converted of which 80% as N{sub 2}-gas. This current study proposed to test the process at pilot scale, to evaluate the transferability of the technique to a full-scale application and to determine the operating parameter. The results are as follows: (i) It is possible to obtain high nitrification and denitrification rates without pre-treating the digestat or adding a carbon source; (ii) Biochemical reactions are extremely sensitive to the oxygenation rate, which in turn is very sensitive to the liquid characteristics in the reactor, such as the dry matter content. It fairly complicates maintaining simultaneous nitrification and denitrification; (iii) At a minimum hydraulic residence time of 4 days, over 90% of the ammonium is converted and 85% of it is removed. These results provide the basic design parameters for a full-scale installation. Depending on the performance desired, it would have a volume going from 30 to 60 m{sup 3} for a 400 m{sup 3} digester. The aeration rate would be between 300

  7. The installation of helium auxiliary systems in HTGR

    International Nuclear Information System (INIS)

    Qin Zhenya; Fu Xiaodong

    1993-01-01

    The inert gas Helium was chosen as reactor coolant in high temperature gas coolant reactor, therefore a set of Special and uncomplex helium auxiliary systems will be installed, the safe operation of HTR-10 can be safeguarded. It does not effect the inherent safety of HTR-10 MW if any one of all those systems were damaged during operation condition. This article introduces the design function and the system principle of all helium auxiliary systems to be installed in HTR-10. Those systems include: helium purification and its regeneration system, helium supply and storage system, pressure control and release system of primary system, dump system for helium auxiliary system and fuel handling, gaseous waste storage system, water extraction system for helium auxiliary systems and evacuation system for primary system

  8. Successful pipeline installation for Parque das Conchas development; Subsea installation

    Energy Technology Data Exchange (ETDEWEB)

    Bartz, Cesar

    2010-07-01

    Subsea 7 has successfully delivered again in Brazilian deep-waters. The subsea engineering and construction company has recently completed pipeline installation activities for the Parque das Conchas (BC-10) development, offshore Brazil. (AG)

  9. Seismic evaluation of nuclear installations; Avaliacao sismica de instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Mattar Neto, Miguel [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    1997-10-01

    Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs.

  10. Control of reactor coolant flow path during reactor decay heat removal

    International Nuclear Information System (INIS)

    Hunsbedt, A.N.

    1988-01-01

    This patent describes a sodium cooled reactor of the type having a reactor hot pool, a slightly lower pressure reactor cold pool and a reactor vessel liner defining a reactor vessel liner flow gap separating the hot pool and the cold pool along the reactor vessel sidewalls and wherein the normal sodium circuit in the reactor includes main sodium reactor coolant pumps having a suction on the lower pressure sodium cold pool and an outlet to a reactor core; the reactor core for heating the sodium and discharging the sodium to the reactor hot pool; a heat exchanger for receiving sodium from the hot pool, and removing heat from the sodium and discharging the sodium to the lower pressure cold pool; the improvement across the reactor vessel liner comprising: a jet pump having a venturi installed across the reactor vessel liner, the jet pump having a lower inlet from the reactor vessel cold pool across the reactor vessel liner and an upper outlet to the reactor vessel hot pool

  11. Improvement of research reactor sustainability

    International Nuclear Information System (INIS)

    Ciocanescu, M.; Paunoiu, C.; Toma, C.; Preda, M.; Ionila, M.

    2010-01-01

    The Research Reactors as is well known have numerous applications in a wide range of science technology, nuclear power development, medicine, to enumerate only the most important. The requirements of clients and stack-holders are fluctuating for the reasons out of control of Research Reactor Operating Organization, which may ensure with priority the safety of facility and nuclear installation. Sustainability of Research Reactor encompasses several aspects which finally are concentrated on safety of Research Reactor and economical aspects concerning operational expenses and income from external resources. Ensuring sustainability is a continuous, permanent activity and also it requests a strategic approach. The TRIGA - 14 MW Research Reactor detains a 30 years experience of safe utilization with good performance indicators. In the last 4 years the reactor benefited of a large investment project for modernization, thus ensuring the previous performances and opening new perspectives for power increase and for new applications. The previous core conversion from LEU to HEU fuel accomplished in 2006 ensures the utilization of reactor based on new qualified European supplier of TRIGA LEU fuel. Due to reduction of number of performed research reactors, the 14 MW TRIGA modernized reactor will play a significant role for the following two decades. (author)

  12. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

  13. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  14. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  15. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  16. Solar Installation Labor Market Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Friedman, B.; Jordan, P.; Carrese, J.

    2011-12-01

    The potential economic benefits of the growing renewable energy sector have led to increased federal, state, and local investments in solar industries, including federal grants for expanded workforce training for U.S. solar installers. However, there remain gaps in the data required to understand the size and composition of the workforce needed to meet the demand for solar power. Through primary research on the U.S. solar installation employer base, this report seeks to address that gap, improving policymakers and other solar stakeholders understanding of both the evolving needs of these employers and the economic opportunity associated with solar market development. Included are labor market data covering current U.S. employment, expected industry growth, and employer skill preferences for solar installation-related occupations. This study offers an in-depth look at the solar installation sectors. A study published by the Solar Foundation in October 2011 provides a census of labor data across the entire solar value chain.

  17. Installation of the Gbar LINAC

    CERN Multimedia

    Maximilien, Brice

    2017-01-01

    Installation of the GBAR linac in its shielding bunker. The electrons accelerated to 10 MeV toward a target will produce the positrons that are necessary to form anti hydrogen with the antiprotons coming from the ELENA decelerator.

  18. DAQ INSTALLATION IN USC COMPLETED

    CERN Multimedia

    A. Racz

    After one year of work at P5 in the underground control rooms (USC55-S1&S2), the DAQ installation in USC55 is completed. The first half of 2006 was dedicated to the DAQ infrastructures installation (private cable trays, rack equipment for a very dense cabling, connection to services i.e. water, power, network). The second half has been spent to install the custom made electronics (FRLs and FMMs) and place all the inter-rack cables/fibers connecting all sub-systems to central DAQ (more details are given in the internal pages). The installation has been carried out by DAQ group members, coming from the hardware and software side as well. The pictures show the very nice team spirit !

  19. Nuclear installations and their environment

    International Nuclear Information System (INIS)

    Rieu, Ch.; Berge-Thierry, C.; Duval, C.; Bonnet, Ch.; Gaubert, B.; Riffard, Th.; Greffier, G.; Cervantes, J.C.; Le Breton, F.; Clement, C.; Charbonnier, R.; Andreani, A.M.; Maubert, H.; Maisonneuve, A.

    2002-01-01

    This dossier deals with protection of nuclear installations against external risks. The articles come from the presentations of the Conference on 'Nuclear installations and their environment', held by the 'Safety and Environment Protection' Section of the French Nuclear Energy Society on October 15, 2002. Floods, earthquakes, winter cold, snow-falls, wind, fires are the main natural risks taken into account. Risks from industrial environment and communication lines are also considered. (authors)

  20. Suitcase to Audit Solar Installations

    Energy Technology Data Exchange (ETDEWEB)

    Alberdi, J.; Barcala, J.M.; Blas de, J.; Molinero, A.; Navarrete, J.J.; Yuste, C.

    2001-07-01

    The audit suitcase was proposed by BESEL to introduce in the solar energy market a new tool which can make an evaluation of solar installation efficiency. Non-invasive sensors and low power components permit both easy installation of the devices and data storage for a period as long as ten days. This project was funded by the contract JOR3-CT98-7030 of the European Union JOULE III program. (Author)

  1. Suitcase to Audit Solar Installations

    International Nuclear Information System (INIS)

    Alberdi, J.; Barcala, J. M.; Blas, J. de; Molinero, A.; Navarrete, J. J.; Yuste, C.

    2001-01-01

    The audit suitcase was proposed by BESEL to introduce in the solar energy market a new tool which can make an evaluation of solar installation efficiency. Non-invasive sensors and low power components permit both easy installation of the devices and data storage for a period as long as ten days. This project was funded by the contract JOR3-CT98-7030 of the European Union JOULE III program. (Author)

  2. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  3. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  4. BWR reactor management system

    International Nuclear Information System (INIS)

    Makino, Kakuji; Kawamura, Atsuo; Yoshioka, Ritsuo; Neda, Toshikatsu.

    1979-01-01

    It is necessary to grasp the delicate state of operation in reactor cores in view of the control of burn-up and power output at the time of the operation management of BWRs. Enormous labor has been required for the collection, processing and evaluation of the data. It is desirable to obtain the safer, more efficient and faster method of operation control by predicting the states in cores including the change of xenon and reflecting them to operation plans as well as by tracing with high accuracy the past burn-up history for a long period. At present, the on-line evaluation of the states in cores is carried out with the process computers attached to respective units, but the amount of data required for core operation management of high degree far exceeds their capacity. From such viewpoints, the research and development on the reactor management system were carried out. The data processing concerning core operation management is performed with newly installed computers utilizing the data from existing process computers, and the operation of reactor cores, the qualitative improvement of management works, labor saving, and fast, efficient operation control are feasible with it. This system was installed in an actual plant in October, 1977. The composition of the system, the prediction of the change in local output distribution accompanying control rod operation, the prediction of the change in the states in cores due to the flow rate of coolant, and the function of collecting plant data are explained. (Kako, I.)

  5. 46 CFR 76.17-90 - Installations contracted for prior to November 19, 1952.

    Science.gov (United States)

    2010-10-01

    ... they are maintained in good condition to the satisfaction of the Officer in Charge, Marine Inspection. Minor repairs and alterations may be made to the same standards as the original installation. (2) The... VESSELS FIRE PROTECTION EQUIPMENT Foam Extinguishing Systems, Details § 76.17-90 Installations contracted...

  6. 46 CFR 76.30-90 - Installations contracted for prior to November 19, 1952.

    Science.gov (United States)

    2010-10-01

    ... and they are maintained in good condition to the satisfaction of the Officer in Charge, Marine Inspection. Minor repairs and alterations may be made to the same standards as the original installation. (2... VESSELS FIRE PROTECTION EQUIPMENT Pneumatic Fire Detecting System, Details § 76.30-90 Installations...

  7. 46 CFR 76.33-90 - Installations contracted for prior to November 19, 1952.

    Science.gov (United States)

    2010-10-01

    ... maintained in good condition to the satisfaction of the Officer in Charge, Marine Inspection. Minor repairs and alterations may be made to the same standards as the original installation. (2) The details of the... VESSELS FIRE PROTECTION EQUIPMENT Smoke Detecting System, Details § 76.33-90 Installations contracted for...

  8. 46 CFR 76.35-90 - Installations contracted for prior to November 19, 1952.

    Science.gov (United States)

    2010-10-01

    ... maintained in good condition to the satisfaction of the Officer in Charge, Marine Inspection. Minor repairs and alterations may be made to the same standards as the original installation. (2) The details of the... VESSELS FIRE PROTECTION EQUIPMENT Manual Alarm System, Details § 76.35-90 Installations contracted for...

  9. 46 CFR 95.17-90 - Installations contracted for prior to November 19, 1952.

    Science.gov (United States)

    2010-10-01

    ... and they are maintained in good condition to the satisfaction of the Officer in Charge, Marine Inspection. Minor repairs and alterations may be made to the same standards as the original installation. (2... MISCELLANEOUS VESSELS FIRE PROTECTION EQUIPMENT Foam Extinguishing Systems, Details § 95.17-90 Installations...

  10. 46 CFR 76.27-90 - Installations contracted for prior to November 19, 1952.

    Science.gov (United States)

    2010-10-01

    ..., and they are maintained in good condition to the satisfaction of the Officer in Charge, Marine Inspection. Minor repairs and alterations may be made to the same standards as the original installation. (2... VESSELS FIRE PROTECTION EQUIPMENT Electric Fire Detecting System, Details § 76.27-90 Installations...

  11. Statement on incidents at nuclear installations - second quarter 1987

    International Nuclear Information System (INIS)

    1988-01-01

    The first incident reported occurred at the Sellafield reprocessing plant when a process worker was contaminated on the right knee of his overalls and received a skin dose in excess of the annual dose limit. Following an inquiry, he was allowed to return to normal working within 3 months. The second incident occurred at the Oldbury nuclear power station when reaction-1 tripped following the failure of one of the three phases of the electricity supply to part of the instrumentation. This caused a loss of forced coolant circulating for a short time following the reactor shutdown. However, following safety checks it was allowed to return to power. Improvements in the instrument supply system protection were subsequently installed on reactor-2 and will be, when possible, on reactor-1. (UK)

  12. Shielding design to obtain compact marine reactor

    International Nuclear Information System (INIS)

    Yamaji, Akio; Sako, Kiyoshi

    1994-01-01

    The marine reactors equipped in previously constructed nuclear ships are in need of the secondary shield which is installed outside the containment vessel. Most of the weight and volume of the reactor plants are occupied by this secondary shield. An advanced marine reactor called MRX (Marine Reactor X) has been designed to obtain a more compact and lightweight marine reactor with enhanced safety. The MRX is a new type of marine reactor which is an integral PWR (The steam generator is installed in the pressure vessel.) with adopting a water-filled containment vessel and a new shielding design method of no installation of the secondary shield. As a result, MRX is considerably lighter in weight and more compact in size as compared with the reactors equipped in previously constructed nuclear ships. For instance, the plant weight and volume of the containment vessel of MRX are about 50% and 70% of those of the Nuclear Ship MUTSU, in spite of the power of MRX is 2.8 times as large as the MUTSU's reactor. The shielding design calculation was made using the ANISN, DOT3.5, QAD-CGGP2 and ORIGEN codes. The computational accuracy was confirmed by experimental analyses. (author)

  13. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

    Reference is made to water cooled reactors and in particular to the cooling system of steam generating heavy water reactors (SGHWR). A two-coolant circuit is described for the latter. Full constructural details are given. (U.K.)

  14. Reactor decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1984-01-01

    A pioneering project on the decommissioning of the Windscale Advanced Gas-cooled Reactor, by the UKAEA, is described. Reactor data; policy; waste management; remote handling equipment; development; and recording and timescales, are all briefly discussed. (U.K.)

  15. RA Reactor

    International Nuclear Information System (INIS)

    1978-02-01

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation [sr

  16. Multiregion reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The study of reflected reactors can be done employing the multigroup diffusion method. The neutron conservation equations, inside the intervals, can be written by fluxes and group constants. A reflected reactor (one and two groups) for a slab geometry is studied, aplying the continuity of flux and current in the interface. At the end, the appropriated solutions for a infinite cylindrical reactor and for a spherical reactor are presented. (Author) [pt

  17. Opportunities for TRIGA reactors in neutron radiography

    International Nuclear Information System (INIS)

    Barton, John P.

    1978-01-01

    In this country the two most recent installations of TRIGA reactors have both been for neutron radiography, one at HEDL and the other at ANL. Meanwhile, a major portion of the commercial neutron radiography is performed on a TRIGA fueled reactor at Aerotest. Each of these installations has different primary objectives and some comparative observations can be drawn. Another interesting comparison is between the TRIGA reactors for neutron radiography and other small reactors that are being installed for this purpose such as the MIRENE slow pulse reactors in France, a U-233 fueled reactor for neutron radiography in India and the L88 solution reactor in Denmark. At Monsanto Laboratory, in Ohio, a subcritical reactor based on MTR-type fuel has recently been purchased for neutron radiography. Such systems, when driven by a Van de Graaff neutron source, will be compared with the standard TRIGA reactor. Future demands on TRIGA or competitive systems for neutron radiography are likely to include the pulsing capability of the reactor, and also the extraction of cold neutron beams and resonance energy beams. Experiments recently performed on the Oregon State TRIGA Reactor provide information in each of these categories. A point of particular current concern is a comparison made between the resonance energy beam intensity extracted from the edge of the TRIGA core and from a slot which penetrated to the center of the TREAT reactor. These results indicate that by using such slots on a TRIGA, resonance energy intensities could be extracted that are much higher than previously predicted. (author)

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sato, Morihiko.

    1994-01-01

    Liquid metals such as liquid metal sodium are filled in a reactor container as primary coolants. A plurality of reactor core containers are disposed in a row in the circumferential direction along with the inner circumferential wall of the reactor container. One or a plurality of intermediate coolers are disposed at the inside of an annular row of the reactor core containers. A reactor core constituted with fuel rods and control rods (module reactor core) is contained at the inside of each of the reactor core containers. Each of the intermediate coolers comprises a cylindrical intermediate cooling vessels. The intermediate cooling vessel comprises an intermediate heat exchanger for heat exchange of primary coolants and secondary coolants and recycling pumps for compulsorily recycling primary coolants at the inside thereof. Since a plurality of reactor core containers are thus assembled, a great reactor power can be attained. Further, the module reactor core contained in one reactor core vessel may be small sized, to facilitate the control for the reactor core operation. (I.N.)

  19. Nuclear reactor vessel fuel thermal insulating barrier

    Science.gov (United States)

    Keegan, C. Patrick; Scobel, James H.; Wright, Richard F.

    2013-03-19

    The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of the thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.

  20. Displacement pile installation effects in sand

    NARCIS (Netherlands)

    Beijer-Lundberg, A.

    2015-01-01

    Installation effects govern the post-installation behaviour of displacement piles in sand. These effects are currently not completely understood. Suitable experimental techniques to model these installation effects include field, laboratory and experimental models. In the current thesis a

  1. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

    After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

  2. Safety studies concerning nuclear power reactors

    International Nuclear Information System (INIS)

    Bailly, Jean; Pelce, Jacques

    1980-01-01

    The safety of nuclear installations poses different technical problems, whether concerning pressurized water reactors or fast reactors. But investigating methods are closely related and concern, on the one hand, the behavior of shields placed between fuel and outside and, on the other, analysis of accidents. The article is therefore in two parts based on the same plan. Concerning light water reactors, the programme of studies undertaken in France accounts for the research carried out in countries where collaboration agreements exist. Concerning fast reactors, France has the initiative of their studies owing to her technical advance, which explains the great importance of the programmes under way [fr

  3. Temperature etalon of WWER-440 reactor

    International Nuclear Information System (INIS)

    Stanc, S.; Slanina, M.

    2001-01-01

    The presentation deals with the description, parameters and advantages of use of the temperature etalon. The system ensures temperature measurement of reactor outlet and inlet temperatures with high accuracy. Accuracy of temperature measurement is 0.18 deg C, accuracy of temperature difference measurement is 0.14 deg C, both with probability 0.95. Using the temperature etalon it is possible to increase accuracy of the standard temperature reactor measurements and to check their accuracy in the course of power reactor statuses in every measurement cycle. Temperature reactor etalon was installed in 12 WWER-440 units in Slovakia, Bohemia and Bulgaria. (Authors)

  4. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  5. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  6. Backfitting swimming pool reactors

    International Nuclear Information System (INIS)

    Roebert, G.A.

    1978-01-01

    Calculations based on measurements in a critical assembly, and experiments to disclose fuel element surface temperatures in case of accidents like stopping of primary coolant flow during full power operation, have shown that the power of the swimming pool type research reactor FRG-2 (15 MW, operating since 1967) might be raised to 21 MW within the present rules of science and technology, without major alterations of the pool buildings and the cooling systems. A backfitting program is carried through to adjust the reactor control systems of FRG-2 and FRG-1 (5 MW, housed in the same reactor hall) to the present safety rules and recommendations, to ensure FRG-2 operation at 21 MW for the next decade. (author)

  7. Small nuclear reactors for desalination

    International Nuclear Information System (INIS)

    Goldsmith, K.

    1978-01-01

    Small nuclear reactors are considered to have an output of not more than 400MW thermal. Since they can produce steam at much higher conditions than needed by the brine heater of a multi-flash desalination unit, it may be economically advantageous to use small reactors for a dual-purpose installation of appropriate size, producing both electricity and desalted water, rather than for a single-purpose desalination plant only. Different combinations of dual-purpose arrangements are possible depending principally on the ratio of electricity to water output required. The costs of the installation as well as of the products are critically dependent on this ratio. For minimum investment costs, the components of the dual-purpose installation should be of a standardised design based on normal commercial power plant practice. This then imposes some restrictions on the plant arrangement but, on the other hand, it facilitates selection of the components. Depending on the electricity to water ratio to be achieved, the conventional part of the installation - essentially the turbines - will form a combination of back-pressure and condensing machines. Each ratio will probably lead to an optimum combination. In the economic evaluation of this arrangement, a distinction must be made between single-purpose and dual-purpose installations. The relationship between output and unit costs of electricity and water will be different for the two cases, but the relation can be expressed in general terms to provide guidelines for selecting the best dimensions for the plant. (author)

  8. Automated installation methods for photovoltaic arrays

    Science.gov (United States)

    Briggs, R.; Daniels, A.; Greenaway, R.; Oster, J., Jr.; Racki, D.; Stoeltzing, R.

    1982-11-01

    Since installation expenses constitute a substantial portion of the cost of a large photovoltaic power system, methods for reduction of these costs were investigated. The installation of the photovoltaic arrays includes all areas, starting with site preparation (i.e., trenching, wiring, drainage, foundation installation, lightning protection, grounding and installation of the panel) and concluding with the termination of the bus at the power conditioner building. To identify the optimum combination of standard installation procedures and automated/mechanized techniques, the installation process was investigated including the equipment and hardware available, the photovoltaic array structure systems and interfaces, and the array field and site characteristics. Preliminary designs of hardware for both the standard installation method, the automated/mechanized method, and a mix of standard installation procedures and mechanized procedures were identified to determine which process effectively reduced installation costs. In addition, costs associated with each type of installation method and with the design, development and fabrication of new installation hardware were generated.

  9. Quality and safety of nuclear installations: the role of administration, and, nuclear safety and regulatory procedures

    International Nuclear Information System (INIS)

    Queniart, D.

    1979-12-01

    In the first paper the author defines the concepts of safety and quality and describes the means of intervention by the Public Authorities in safety matters of nuclear installations. These include individual authorisations, definition and application of technical rules and surveillance of installations. In the second paper he defines the distinction between radiation protection and safety and presents the legislative and regulatory plan for nuclear safety in France. A central safety service for nuclear installations was created in March 1973 within the Ministry of Industrial and Scientific Development, where, amongst other tasks, it draws up regulatory procedures and organizes inspections of the installations. The main American regulations for light water reactors are outlined and the French regulatory system for different types of reactors discussed

  10. Calculation of anti-seismic design for Xi'an pulsed reactor

    International Nuclear Information System (INIS)

    Li Shuian

    2002-01-01

    The author describes the reactor safety rule, safety regulation and design code that must be observed to anti-seismic design in Xi'an pulsed reactor. It includes the classification of reactor installation, determination of seismic loads, calculate contents, program, method, results and synthetically evaluation. According to the different anti-seismic structure character of reactor installation, an appropriate method was selected to calculate the seismic response. The results were evaluated synthetically using the design code and design requirement. The evaluate results showed that the anti-seismic design function of reactor installation of Xi'an pules reactor is well, and the structure integrality and normal property of reactor installation can be protect under the designed classification of the earthquake

  11. PIK reactor construction status

    International Nuclear Information System (INIS)

    Konoplev, K.A.; Smolsky, S.L.

    2001-01-01

    The 100MW reactor PIK for fundamental researches has a thermal neutron flux of more than 10 15 n/cm 2 sec. This presentation outlines the construction state as of 2001, its prospects and completion tactics in the conditions of unstable finance. Construction of the reactor started in 1976. In 1986 construction of the building was completed and significant part of the installation work fulfilled. Construction of cooling systems was finished, the control panel assembled, and adjustment of the pump and gate valve control circuits started. After Chernobyl catastrophe, the USSR nuclear reactor safety requirements were revised. The PIK design did not meet these requirements and underwent considerable revision. The reconstruction design resulted in double the initial cost. Creation of the containment was the bulkiest part of the reconstruction. It brought about the need to disassemble the roofing of the building, dismantle all the equipment of the two upper floors, and lay up the equipment of the lower floors. As of 2001, construction in accordance with the revised design is at the stage of assemblage of the most important units, i.e. reactor itself, cooling system, heavy water system, and a number of auxiliary systems, such as depleted fuel storage, emergency cooling system etc. (orig.)

  12. The nuclear reactor strategy between fast breeder reactors and advanced pressurized water reactors

    International Nuclear Information System (INIS)

    Seifritz, W.

    1983-01-01

    A nuclear reactor strategy between fast breeder reactors (FBRs) and advanced pressurized water reactors (APWRs) is being studied. The principal idea of this strategy is that the discharged plutonium from light water reactors (LWRs) provides the inventories of the FBRs and the high-converter APWRs, whereby the LWRs are installed according to the derivative of a logistical S curve. Special emphasis is given to the dynamics of reaching an asymptotic symbiosis between FBRs and APWRs. The main conclusion is that if a symbiotic APWR-FBR family with an asymptotic total power level in the terawatt range is to exist in about half a century from now, we need a large number of FBRs already in an early phase

  13. Horn installed in CNGS tunnel

    CERN Multimedia

    Maximilien Brice

    2005-01-01

    The horn is installed for the CERN Neutrinos to Gran Sasso (CNGS) project. Protons collide with a graphite target producing charged particles that are focussed by the magnetic field in the horn. These particles will then pass into a decay tube where they decay into neutrinos, which travel towards a detector at Gran Sasso 732 km away in Italy.

  14. Installation tests for BERSAFE 88

    International Nuclear Information System (INIS)

    Bamfield, R.D.; Haigh, R.

    1989-02-01

    A set of ten test problems for each of the four BERSAFE stress analysis programs is provided. These problems along with this report, which forms part of the BERSAFE 88 documentation, constitute a test of the customers' BERSAFE installation. On running the problems and attaining results identical to those presented here, the customer should have some confidence that his system is operating correctly. (author)

  15. Solar Water Heater Installation Package

    Science.gov (United States)

    1982-01-01

    A 48-page report describes water-heating system, installation (covering collector orientation, mounting, plumbing and wiring), operating instructions and maintenance procedures. Commercial solar-powered water heater system consists of a solar collector, solar-heated-water tank, electrically heated water tank and controls. Analysis of possible hazards from pressure, electricity, toxicity, flammability, gas, hot water and steam are also included.

  16. Installation package - home solar heater

    Science.gov (United States)

    1980-01-01

    Installation of commerical solar-heating system at two story, three bedroom house in New Hampshire is described in 65 page report. System collectors are integrated part of building replacing conventional roofing or siding. Report also includes general description of system, its operation and guidelines, orientation and references.

  17. YB0 SERVICES INSTALLATION COMPLETED

    CERN Document Server

    The beauty of the completed YB0 was briefly visible at P5 as preparations continue for Tracker installation. A tremendous effort, lasting 7 months and involving more than 100 workers on the busiest days, resulted in 5700 electrical cables, 780 optical cables with 65k fibre channels, and 550 pipes laid on YB0 for HB, EB and Tracker.

  18. Procedures for permission of installation of nuclear power stations

    International Nuclear Information System (INIS)

    Narita, Yoriaki

    1980-01-01

    The locations of atomic power stations are first selected by electric power enterprises in consultation with the Ministry of International Trade and Industry or under the guidance of authorities concerned. The surveys of the climate, topography, water and plants in the planned sites and the influences of nuclear power generation to the surrounding areas are made by the enterprisers under the administrative guidance of the MITI. Secondly, the basic project shall be submitted to and decided by the Power Resource Development Council headed by the Prime Minister (Article 10, the Power Resource Development Law). The Council shall, if necessary, call for the attendance of the governors of prefectures concerned and hear their opinions (Article 11, the Law). As the third and most complicated phase, various procedures include; (a) permission of the changes of electrical facilities under the Electricity Enterprises Act; (b) authorization of the installation of reactors under the Nuclear Reactor Regulation Law; (c) permission or authorization under other regulations including the Agricultural Land Act, etc.; (d) additional procedures related to the indemnification to fishery and so forth. Finally the reactors are to be operated after receiving the certificates of the Minister of ITI on the inspections of construction works, nuclear fuel materials used for the reactors and welding processes of reactor containment vessels, boilers, turbines, etc. (Okada, K.)

  19. An acclerator-based installation of small power with the lead-bismuth coolant

    Energy Technology Data Exchange (ETDEWEB)

    Gorshkov, V.T.; Yefimov, E.I.; Novikova, N.N. [Research and Development Bereau, Podolsk (Russian Federation)] [and others

    1995-10-01

    The structure of the accelerator-based installation is described that includes the subcritical reactor-blanket with power 15 MW(h) cooled with lead-bismuth, the lead-bismuth flow target where a beam of {alpha}-particle is injected, the equipment of a primary and secondary curcuits. Some results of calculations and estimations are discussed that have been carried out to justify the target and blanket constructions. Some main characteristics of the installation are presented.

  20. Experience in installing a microprocessor-based protection system on a UK nuclear power plant

    International Nuclear Information System (INIS)

    Jones, C.D.; Smith, I.C.

    1993-01-01

    This paper describes a recently completed project to install a microprocessor-based reactor protection system on a twin reactor station in the United Kingdom. This represented the first application of digital technology as part of such a system in the UK. The background of the application and details of the chosen solution are provided. The experience gained during the installation, commissioning and early operation of the equipment is reviewed by the operators. Interactions between the utility and the regulatory body are outlined and the impact of the regulatory process on the utility's resources and the project timescales are discussed

  1. Liquid-poison type power controlling device for nuclear reactor

    International Nuclear Information System (INIS)

    Horiuchi, Tetsuo; Yamanari, Shozo; Sugisaki, Toshihiko; Goto, Hiroshi.

    1981-01-01

    Purpose: To improve the safety and the operability of a nuclear reactor by adjusting the density of liquid poison. Constitution: The thermal expansion follow-up failure between cladding and a pellet upon abrupt and local variations of the power is avoided by adjusting the density of liquid poison during ordinary operation in combination with a high density liquid poison tank and a filter and smoothly controlling the reactor power through a pipe installed in the reactor core. The high density liquid poison is abruptly charged in to the reactor core under relatively low pressure through the tube installed in the reactor core at the time of control rod insertion failure in an accident, thereby effectively shutting down the reactor and improving the safety and the operability of the reactor. (Yoshihara, H.)

  2. FFTF report: FFTF piping installation and welding techniques

    International Nuclear Information System (INIS)

    Gilles, J.

    1975-01-01

    The main sodium piping with a diameter of 16'' or 28 '' is being installed at the FFTF construction site starting in December 1974. The supplier and authority demarcations are: Combustion Engineering supplies the reactor vessel, guard vessel and adjoining pipes and uses the machine welding equipment ''Dimetrics''; for the piping system of the primary and secondary loops the pipes manufactured by Rollmet at HUICO, Pasco, were delivered and prefabricated there, as far as compatible with the installation. ''Astroarc'' welding machines are used by Bechtel for the piping prefabrication in the weld laboratory as well as on site at the construction site. Technical welding problems occurring during the course of the installation at the construction site and several during this time are described. At present 6 weld seams in the reactor and 14 weld seams in the secondary loop are accepted. The requirement exists to carry out as many welds as possible automatically, in order to produce sodium pipe welds of high technical quality and which are reproducible. The welding equipment is described

  3. 30 CFR 57.4504 - Fan installations.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Fan installations. 57.4504 Section 57.4504... Control Installation/construction/maintenance § 57.4504 Fan installations. (a) Fan houses, fan bulkheads... of combustible materials, except installed wiring, ground and track support, headframes, and direct...

  4. The reactor Cabri

    International Nuclear Information System (INIS)

    Ailloud, J.; Millot, J.P.

    1964-01-01

    It has become necessary to construct in France a reactor which would permit the investigation of the conditions of functioning of future installations, the choice, the testing and the development of safety devices to be adopted. A water reactor of a type corresponding to the latest CEA constructions in the field of laboratory or university reactors was decided upon: it appeared important to be able to evaluate the risks entailed and to study the possibilities of increasing the power, always demanded by the users; on the other hand, it is particularly interesting to clarify the phenomena of power oscillation and the risks of burn out. The work programme for CABRI will be associated with the work carried out on the American Sperts of the same type, during its construction, very useful contacts were made with the American specialists who designed the se reactors. A brief description of the reactor is given in the communication as well as the work programme for the first years with respect to the objectives up to now envisaged. Rough description of the reactor. CABRI is an open core swimming-pool reactor without any lateral protection, housed in a reinforced building with controlled leakage, in the Centre d'Etudes Nucleaires de Cadarache. It lies alone in the middle of an area whose radius is 300 meters long. Control and measurements equipment stand out on the edge of that zone. It consumes MTR fuel elements. The control-safety rods are propelled by compressed air. The maximum flow rate of cooling circuit is 1500 m 3 /h. Transient measurements are recorded in a RW330 unit. Aims and work programme. CABRI is meant for: - studies on the safety of water reactors - for the definition of the safety margins under working conditions: research of maximum power at which a swimming-pool reactor may operate with respect to a cooling accident, of local boiling effect on the nuclear behaviour of the reactor, performances of the control and safety instruments under exceptional

  5. Buffer protection in the installation phase

    International Nuclear Information System (INIS)

    Wimelius, Hans; Pusch, Roland

    2008-12-01

    The research and development of the design and construction of the SKB's repository for final disposal of spent reactor fuel is conducted along several paths ('lines'). Issues concerning the bedrock are dealt with in the 'rock line' and those related to buffer and backfill in deposition holes and tunnels are considered in the 'buffer line' and 'backfill line', respectively. These lines also deal with sub-activities that are coupled to several other lines. One of them includes development of techniques for protecting buffer blocks from moisture and water in the installation phase. Techniques and methods for placement and removal of the 'buffer protection sheet' are dealt with in the 'buffer line'. The removal is, however, considered as being part of the backfilling sequence. Since the performance of the sheet is of fundamental importance to the placement and function of the buffer it deserves particular attention. Thus, the removal of the rubber sheet that serves to protect the buffer blocks in the installation phase may be difficult and can cause significant problems that may require retrieval of already placed canister, buffer and backfill. These matters are in focus in the present report. Arrangements for protecting already placed buffer blocks from moist air and water have been tested in earlier large-scale experiments, i.e. the Prototype Repository project at Aespoe but the experience from them has called for more effective protection of the clay blocks as described in the present report. Focus is on the construction of foundation components at the bottom of the deposition holes required for establishing a tight seal between rock and buffer blocks, and on the protection sheet and arrangements for limiting water pressure on it. Special attention is paid to the drainage of the space between rock and protection sheet that is necessary for avoiding failure of the sheet and to systems for achieving this and for providing alarm signals if the allowed pressure is

  6. Buffer protection in the installation phase

    Energy Technology Data Exchange (ETDEWEB)

    Wimelius, Hans (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)); Pusch, Roland (Geodevelopment International AB, Lund (Sweden))

    2008-12-15

    The research and development of the design and construction of the SKB's repository for final disposal of spent reactor fuel is conducted along several paths ('lines'). Issues concerning the bedrock are dealt with in the 'rock line' and those related to buffer and backfill in deposition holes and tunnels are considered in the 'buffer line' and 'backfill line', respectively. These lines also deal with sub-activities that are coupled to several other lines. One of them includes development of techniques for protecting buffer blocks from moisture and water in the installation phase. Techniques and methods for placement and removal of the 'buffer protection sheet' are dealt with in the 'buffer line'. The removal is, however, considered as being part of the backfilling sequence. Since the performance of the sheet is of fundamental importance to the placement and function of the buffer it deserves particular attention. Thus, the removal of the rubber sheet that serves to protect the buffer blocks in the installation phase may be difficult and can cause significant problems that may require retrieval of already placed canister, buffer and backfill. These matters are in focus in the present report. Arrangements for protecting already placed buffer blocks from moist air and water have been tested in earlier large-scale experiments, i.e. the Prototype Repository project at Aespoe but the experience from them has called for more effective protection of the clay blocks as described in the present report. Focus is on the construction of foundation components at the bottom of the deposition holes required for establishing a tight seal between rock and buffer blocks, and on the protection sheet and arrangements for limiting water pressure on it. Special attention is paid to the drainage of the space between rock and protection sheet that is necessary for avoiding failure of the sheet and to systems for achieving

  7. Reactor container

    International Nuclear Information System (INIS)

    Naruse, Yoshihiro.

    1990-01-01

    The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

  8. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

  9. Nuclear reactor

    International Nuclear Information System (INIS)

    Garabedian, G.

    1988-01-01

    A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

  10. Feasibility study on the transient fuel test loop installation

    International Nuclear Information System (INIS)

    Kim, J. Y.; Lee, C. Y.

    1997-02-01

    The design and installation of the irradiation test facility for verification test of the fuel performance are very important in connection with maximization of the utilization of HANARO. The objective of this study is to investigate and analyze the test capsules and loops in research reactors of the other countries and to design preliminarily the eligible transient fuel test facility to be installed in HANARO. The principle subjects of this study are to analyze the contents, kinds and scopes of the irradiation test facilities for nuclear technology development. The guidances for the basic and detail design of the transient fuel test facility in the future are presented. The investigation and analysis of various kinds of test facilities that are now in operation at the research reactors of nuclear advanced countries are carried out. Based on the design data of HANARO the design materials for an eligible transient fuel test facility comprises two pacts : namely, in pile test fuel in reactor core site, and out of pile system regulates the experimental conditions in the in pile test section. Especially for power ramping and cycling selection of the eligible power variation equipment in HANARO is carried out. (author). 13 refs., 4 tabs., 46 figs

  11. Handling and carrying head for nuclear fuel assemblies and installation including this head

    International Nuclear Information System (INIS)

    Artaud, R.; Cransac, J.P.; Jogand, P.

    1986-01-01

    The present invention proposes a handling and carrying head ensuring efficiently the cooling of the nuclear fuel asemblies it transports so that any storage in liquid metal in a drum within or adjacent the reactor vessel is suppressed. The invention claims also a nuclear fuel handling installation including the head; it allows a longer time between loading and unloading campaigns and the space surrounding the reactor vessel keeps free without occupying a storage zone within the vessel [fr

  12. Nuclear reactor

    International Nuclear Information System (INIS)

    Batheja, P.; Huber, R.; Rau, P.

    1985-01-01

    Particularly for nuclear reactors of small output, the reactor pressure vessel contains at least two heat exchangers, which have coolant flowing through them in a circuit through the reactor core. The circuit of at least one heat exchanger is controlled by a slide valve, so that even for low drive forces, particularly in natural circulation, the required even loading of the heat exchanger is possible. (orig./HP) [de

  13. Heterogeneous reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author) [pt

  14. Regulatory requirements and administrative practice in safety of nuclear installations

    International Nuclear Information System (INIS)

    Servant, J.

    1977-01-01

    This paper reviews the current situation of the France regulatory rules and procedures dealing with the safety of the main nuclear facilities and, more broadly, the nuclear security. First, the author outlines the policy of the French administration which requires that the licensee responsible for an installation has to demonstrate that all possible measures are taken to ensure a sufficient level of safety, from the early stage of the project to the end of the operation of the plant. Thus, the administration performs the assessment on a case-by-case basis, of the safety of each installation before granting a nuclear license. On the other hand, the administration settles overall safety requirements for specific categories of installations or components, which determine the ultimate safety performances, but avoid, as far as possible, to detail the technical specifications to be applied in order to comply with these goals. This approach, which allows the designers and the licensees to rely upon sound codes and standards, gains the advantage of a great flexibility without imparing the nuclear safety. The author outlines the licensing progress for the main categories of installations: nuclear power plants of the PWR type, fast breeders, uranium isotope separation plants, and irradiated fuel processing plants. Emphasis is placed on the most noteworthy points: standardization of projects, specific risks of each site, problems of advanced type reactors, etc... The development of the technical regulations is presented with emphasis on the importance of an internationally concerned action within the nuclear international community. The second part of this paper describes the France operating experience of nuclear installations from the safety point of view. Especially, the author examines the technical and administrative utilization of data from safety significant incidents in reactors and plants, and the results of the control performed by the nuclear installations

  15. Planned reliability in the transport and installation of large nuclear components

    International Nuclear Information System (INIS)

    Bieler, L.

    1988-01-01

    The transport and installation of heavy and bulky large components require detailed planning of all jobs and activities, trained and experienced personnel and corresponding technical equipment for reliable and quality-assured implementation. The correct approach to the planning and implementation of such transports and installations has been confirmed by years of successful performance of these jobs e.g. in reactor pressure vessels and steam generators for nuclear power plants. Large components for nuclear power plants are truly extreme examples but will be all the better suited for demonstrating the problems inherent in transport and installation. (orig.) [de

  16. Physical protection of nuclear installations

    International Nuclear Information System (INIS)

    Toepfer, K.

    1989-01-01

    This contribution investigates the possible danger and the legal basis of physical protection and explains the current, integrated system provided for, as well as the underlying possible scenarios of an assault: (1) by a violent crowd of aggressors outside the installation, (2) by a small group of aggressors outside the installation, (3) by a person allowed to enter (internal assault). The physical protection system supplements the internal safety measures to enhance protection against hypothetical and possible acts of terrorism or other criminal assault. The system covers external and internal controlled areas, access monitoring, physical protection control room and service, security checks of the personnel, and activities to disclose sabotage. Some reflections on the problem field between security controls and the constitutional state conclude this contribution. (orig./HSCH) [de

  17. The dismantling of nuclear installations

    International Nuclear Information System (INIS)

    Lacoste, A.C.; Duthe, M.; Mignon, H.; Lambert, F.; Pradel, Ph.; Hillewaere, J.P.; Dupre la Tour, St.; Mandil, C.; Weil, L.; Eickelpasch, N.; Finsterwalder, L.

    1997-01-01

    for nuclear installations, the dismantling is an important part of their exploitation. The technology of dismantling is existing and to get a benefit from the radioactive decay, it seems more easy for operating company such E.D.F. to wait for fifty years before dismantling. But in order to get the knowledge of this operation, the Safety Authority wanted to devote this issue of 'Controle'to the dismantling method. This issue includes: the legal aspects, the risks assessment, the dismantling policy at E.D.F., the site of Brennilis (first French experience of dismantling), the dismantling techniques, the first dismantling of a fuel reprocessing plant, comparison with classical installations, economic aspect, some German experiences, the cleansing of the american site of Handford. (N.C.)

  18. ATLAS Software Installation on Supercomputers

    CERN Document Server

    Undrus, Alexander; The ATLAS collaboration

    2018-01-01

    PowerPC and high performance computers (HPC) are important resources for computing in the ATLAS experiment. The future LHC data processing will require more resources than Grid computing, currently using approximately 100,000 cores at well over 100 sites, can provide. Supercomputers are extremely powerful as they use resources of hundreds of thousands CPUs joined together. However their architectures have different instruction sets. ATLAS binary software distributions for x86 chipsets do not fit these architectures, as emulation of these chipsets results in huge performance loss. This presentation describes the methodology of ATLAS software installation from source code on supercomputers. The installation procedure includes downloading the ATLAS code base as well as the source of about 50 external packages, such as ROOT and Geant4, followed by compilation, and rigorous unit and integration testing. The presentation reports the application of this procedure at Titan HPC and Summit PowerPC at Oak Ridge Computin...

  19. Environmental assessment [of nuclear installations

    International Nuclear Information System (INIS)

    Townsley, M.

    1989-01-01

    The European Community has introduced a directive which instructs that for all projects likely to have a significant effect on the environment consent should only be given after a rigorous assessment of such effects has been carried out and presented as an environmental statement. Projects requiring environmental assessment include nuclear power stations, any thermal power station over 300MW, any radioactive waste storage or disposal facility, any installation which produces electricity, power lines, installations for fuel production, fuel reprocessing, radioactive waste processing and fuel enrichment. The statement must include a description of the likely effects, direct and indirect, on the environment of the development, with reference to human beings, flora, fauna, soil, water, air, climate, landscape, interactions of two or more of these, material assets and cultural heritage. Measures to avoid or remedy the impact must be included. (U.K.)

  20. Smectite alteration

    International Nuclear Information System (INIS)

    Anderson, D.M.

    1984-11-01

    This report contains the proceedings of a second workshop in Washington DC December 8-9, 1983 on the alteration of smectites intended for use as buffer materials in the long-term containment of nuclear wastes. It includes extended summaries of all presentations and a transcript of the detailed scientific discussion. The discussions centered on three main questions: What is the prerequisite for and what is the precise mechanism by which smectite clays may be altered to illite. What are likly sources of potassium with respect to the KBS project. Is it likely that the conversion of smectite to illite will be of importance in the 10 5 to the 10 6 year time frame. The workshop was convened to review considerations and conclusions in connection to these questions and also to broaden the discussion to consider the use of smectite clays as buffer materials for similar applications in different geographical and geological settings. SKBF/KBS technical report 83-03 contains the proceedings from the first workshop on these matters that was held at the State University of New York, Buffalo May 26-27, 1982. (Author)

  1. Quality assurance in nuclear installations

    International Nuclear Information System (INIS)

    Torres M, Nelson.

    1985-08-01

    It has been proven that the bad quality of products, equipment, installations, and services is not due to the lack of tests, experiments and verifications. The main causes are associated with insufficient organization of the activities that have influence on the quality. The garantee of quality is conceptualized as an appropriate instrument composed of normalized criteria initially in advanced technologies. Such as nuclear science and aerospace technology. However, with the appropriate modifications it can be applied to conventional technologies

  2. Method of installing well conductors

    International Nuclear Information System (INIS)

    Houser, D.M.

    1991-01-01

    This patent describes a method of installing a well conductor in a marine environment. It comprises sealing a well conductor with a watertight plug; submerging the conductor from an elevated platform; adding additional conductor lengths to the conductor as needed thereby forming a conductor string; adjusting the buoyancy of the string to control the lowering of the string to the sea floor; and drilling through the plug after the conductor string has achieved the desired penetration depth

  3. Mounting clips for panel installation

    Science.gov (United States)

    Cavieres, Andres; Al-Haddad, Tristan; Goodman, Joseph

    2017-07-11

    A photovoltaic panel mounting clip comprising a base, central indexing tabs, flanges, lateral indexing tabs, and vertical indexing tabs. The mounting clip removably attaches one or more panels to a beam or the like structure, both mechanically and electrically. It provides secure locking of the panels in all directions, while providing guidance in all directions for accurate installation of the panels to the beam or the like structure.

  4. Environmental Information Document: L-reactor reactivation

    Energy Technology Data Exchange (ETDEWEB)

    Mackey, H.E. Jr. (comp.)

    1982-04-01

    Purpose of this Environmental Information Document is to provide background for assessing environmental impacts associated with the renovation, restartup, and operation of L Reactor at the Savannah River Plant (SRP). SRP is a major US Department of Energy installation for the production of nuclear materials for national defense. The purpose of the restart of L Reactor is to increase the production of nuclear weapons materials, such as plutonium and tritium, to meet projected needs in the nuclear weapons program.

  5. Environmental Information Document: L-reactor reactivation

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.

    1982-04-01

    Purpose of this Environmental Information Document is to provide background for assessing environmental impacts associated with the renovation, restartup, and operation of L Reactor at the Savannah River Plant (SRP). SRP is a major US Department of Energy installation for the production of nuclear materials for national defense. The purpose of the restart of L Reactor is to increase the production of nuclear weapons materials, such as plutonium and tritium, to meet projected needs in the nuclear weapons program

  6. High temperature reactor safety and environment

    International Nuclear Information System (INIS)

    Brisbois, J.; Charles, J.

    1975-01-01

    High-temperature reactors are endowed with favorable safety and environmental factors resulting from inherent design, main-component safety margins, and conventional safety systems. The combination of such characteristics, along with high yields, prove in addition, that such reactors are plagued with few problems, can be installed near users, and broaden the recourse to specific power, therefore fitting well within a natural environment [fr

  7. Proposal of space reactor for nuclear electric propulsion system

    International Nuclear Information System (INIS)

    Nishiyama, Takaaki; Nagata, Hidetaka; Nakashima, Hideki

    2009-01-01

    A nuclear reactor installed in spacecrafts is considered here. The nuclear reactor could stably provide an enough amount of electric power in deep space missions. Most of the nuclear reactors that have been developed up to now in the United States and the former Soviet Union have used uranium with 90% enrichment of 235 U as a fuel. On the other hand, in Japan, because the uranium that can be used is enriched to below 20%, the miniaturization of the reactor core is difficult. A Light-water nuclear reactor is an exception that could make the reactor core small. Then, the reactor core composition and characteristic are evaluated for the cases with the enrichment of the uranium fuel as 20%. We take up here Graphite reactor, Light-water reactor, and Sodium-cooled one. (author)

  8. Installed capacity in New York

    International Nuclear Information System (INIS)

    Charlton, J.

    2006-01-01

    This presentation discussed capacity issues related to the New York Independent System Operator (NYISO). The NYISO's market volume was approximately $11 billion in 2005, and it was responsible for providing 32,075 MW of electricity at peak load to its users. Regulatory uncertainty is currently discouraging investment in new generating resources. All load serving entities are required to contract for sufficient capacity in order to meet their capacity obligations. Market participants currently determine capacity and energy revenues. The NYISO market allows suppliers to recover variable costs for providing ancillary services, and the economic value of the revenue source governs decisions made in the wholesale electricity market. The installed capacity market was designed as a spot auction deficiency auction. Phased-in demand curves are used to modify the installed capacity market's design. A sloped demand curve mechanism is used to value capacity above the minimum requirement for both reliability and competition. Participation in the day-ahead market enhances competition and exerts downward pressure on energy and ancillary service market prices. It was concluded that the market structures and design features of the installed capacity markets recognize the need for system reliability in addition to encouraging robust competition and recognizing energy price caps and regulatory oversights. tabs., figs

  9. Leukaemia near british nuclear installations

    International Nuclear Information System (INIS)

    Hubert, D.

    1991-01-01

    An excess of childhood leukaemia has been seen near some British nuclear installations, especially near the Sellafield reprocessing plant. The same result was found in a more general study including a large number of nuclear sites. Similar studies made in USA, Canada and France have been negative. Moreover, epidemiological studies made in England have discovered other childhood leukaemia clusters in areas far from nuclear facilities, and especially near potential sites of nuclear installations. Several explanations are suggested but no definite conclusion is yet possible. Doses from radioactive releases seem to be too low to account for the additional deaths from leukaemia by environmental contamination. A virus activation, which might be associated with population influx into rural isolated areas, has been considered. The hypothesis of genetic mutation induced by ionising radiation in the fathers of children with leukaemia has been made because a higher risk of leukaemia was observed for children of fathers employed at Sellafield. No firm conclusion is possible considering the small number of observed cases and the lack of excess leukaemias in the offspring of Hiroshima and Nagasaki survivors. The possibility of internal contamination, chemicals or even radon is discussed as other causes. Studies in progress might allow to find an answer to the problem of leukaemia in the vicinity of British nuclear installations [fr

  10. Safety aspects of spent nuclear fuel interim storage installations

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, Luiz Sergio [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil). Dept. da Qualidade. Div. de Sistemas da Qualidade]. E-mail: romanato@ctmsp.mar.mil.br; Rzyski, Barbara Maria [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Div. de Ensino]. E-mail: bmrzyski@ipen.br

    2007-07-01

    Nowadays safety and security of spent nuclear fuel (SNF) interim storage installations are very important, due to a great concentration of fission products, actinides and activation products. In this kind of storage it is necessary to consider the physical security. Nuclear installations have become more vulnerable. New types of accidents must be considered in the design of these installations, which in the early days were not considered like: fissile material stolen, terrorists' acts and war conflicts, and traditional accidents concerning the transport of the spent fuel from the reactor to the storage location, earthquakes occurrence, airplanes crash, etc. Studies related to airplane falling had showed that a collision of big commercials airplanes at velocity of 800 km/h against SNF storage and specially designed concrete casks, do not result in serious structural injury to the casks, and not even radionuclides liberation to the environment. However, it was demonstrated that attacks with modern military ammunitions, against metallic casks, are calamitous. The casks could not support a direct impact of this ammo and the released radioactive materials can expose the workers and public as well the local environment to harmful radiation. This paper deals about the main basic aspects of a dry SNF storage installation, that must be physically well protected, getting barriers that difficult the access of unauthorized persons or vehicles, as well as, must structurally resist to incidents or accidents caused by unauthorized intrusion. (author)

  11. Safety aspects of spent nuclear fuel interim storage installations

    International Nuclear Information System (INIS)

    Romanato, Luiz Sergio

    2007-01-01

    Nowadays safety and security of spent nuclear fuel (SNF) interim storage installations are very important, due to a great concentration of fission products, actinides and activation products. In this kind of storage it is necessary to consider the physical security. Nuclear installations have become more vulnerable. New types of accidents must be considered in the design of these installations, which in the early days were not considered like: fissile material stolen, terrorists' acts and war conflicts, and traditional accidents concerning the transport of the spent fuel from the reactor to the storage location, earthquakes occurrence, airplanes crash, etc. Studies related to airplane falling had showed that a collision of big commercials airplanes at velocity of 800 km/h against SNF storage and specially designed concrete casks, do not result in serious structural injury to the casks, and not even radionuclides liberation to the environment. However, it was demonstrated that attacks with modern military ammunitions, against metallic casks, are calamitous. The casks could not support a direct impact of this ammo and the released radioactive materials can expose the workers and public as well the local environment to harmful radiation. This paper deals about the main basic aspects of a dry SNF storage installation, that must be physically well protected, getting barriers that difficult the access of unauthorized persons or vehicles, as well as, must structurally resist to incidents or accidents caused by unauthorized intrusion. (author)

  12. Design and installation of a ferromagnetic wall in tokamak geometry

    International Nuclear Information System (INIS)

    Hughes, P. E.; Levesque, J. P.; Rivera, N.; Mauel, M. E.; Navratil, G. A.

    2015-01-01

    Low-activation ferritic steels are leading material candidates for use in next-generation fusion development experiments such as a prospective component test facility and DEMO power reactor. Understanding the interaction of plasmas with a ferromagnetic wall will provide crucial physics for these facilities. In order to study ferromagnetic effects in toroidal geometry, a ferritic wall upgrade was designed and installed in the High Beta Tokamak–Extended Pulse (HBT-EP). Several material options were investigated based on conductivity, magnetic permeability, vacuum compatibility, and other criteria, and the material of choice (high-cobalt steel) is characterized. Installation was accomplished quickly, with minimal impact on existing diagnostics and overall machine performance, and initial results demonstrate the effects of the ferritic wall on plasma stability

  13. Design and installation of a ferromagnetic wall in tokamak geometry

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, P. E., E-mail: peh2109@columbia.edu; Levesque, J. P.; Rivera, N.; Mauel, M. E.; Navratil, G. A. [Columbia University Plasma Physics Laboratory, Columbia University, 102 S.W. Mudd, 500 W. 120th St., New York, New York 10027 (United States)

    2015-10-15

    Low-activation ferritic steels are leading material candidates for use in next-generation fusion development experiments such as a prospective component test facility and DEMO power reactor. Understanding the interaction of plasmas with a ferromagnetic wall will provide crucial physics for these facilities. In order to study ferromagnetic effects in toroidal geometry, a ferritic wall upgrade was designed and installed in the High Beta Tokamak–Extended Pulse (HBT-EP). Several material options were investigated based on conductivity, magnetic permeability, vacuum compatibility, and other criteria, and the material of choice (high-cobalt steel) is characterized. Installation was accomplished quickly, with minimal impact on existing diagnostics and overall machine performance, and initial results demonstrate the effects of the ferritic wall on plasma stability.

  14. Slurry reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kuerten, H; Zehner, P [BASF A.G., Ludwigshafen am Rhein (Germany, F.R.)

    1979-08-01

    Slurry reactors are designed on the basis of empirical data and model investigations. It is as yet not possible to calculate the flow behavior of such reactors. The swarm of gas bubbles and cluster formations of solid particles and their interaction in industrial reactors are not known. These effects control to a large extent the gas hold-up, the gas-liquid interface and, similarly as in bubble columns, the back-mixing of liquids and solids. These hydrodynamic problems are illustrated in slurry reactors which constructionally may be bubble columns, stirred tanks or jet loop reactors. The expected effects are predicted by means of tests with model systems modified to represent the conditions in industrial hydrogenation reactors. In his book 'Mass Transfer in Heterogeneous Catalysis' (1970) Satterfield complained of the lack of knowledge about the design of slurry reactors and hence of the impossible task of the engineer who has to design a plant according to accepted rules. There have been no fundamental changes since then. This paper presents the problems facing the engineer in designing slurry reactors, and shows new development trends.

  15. Reactor safety

    International Nuclear Information System (INIS)

    Butz, H.P.; Heuser, F.W.; May, H.

    1985-01-01

    The paper comprises an introduction into nuclear physics bases, the safety concept generally speaking, safety devices of pwr type reactors, accident analysis, external influences, probabilistic safety assessment and risk studies. It further describes operational experience, licensing procedures under the Atomic Energy Law, research in reactor safety and the nuclear fuel cycle. (DG) [de

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Mysels, K.J.; Shenoy, A.S.

    1976-01-01

    A nuclear reactor is described in which the core consists of a number of fuel regions through each of which regulated coolant flows. The coolant from neighbouring fuel regions is combined in a manner which results in an averaging of the coolant temperature at the outlet of the core. By this method the presence of hot streaks in the reactor is reduced. (UK)

  17. Reactor container

    International Nuclear Information System (INIS)

    Kato, Masami; Nishio, Masahide.

    1987-01-01

    Purpose: To prevent the rupture of the dry well even when the melted reactor core drops into a reactor pedestal cavity. Constitution: In a reactor container in which a dry well disposed above the reactor pedestal cavity for containing the reactor pressure vessel and a torus type suppression chamber for containing pressure suppression water are connected with each other, the pedestal cavity and the suppression chamber are disposed such that the flow level of the pedestal cavity is lower than the level of the pressure suppression water. Further, a pressure suppression water introduction pipeway for introducing the pressure suppression water into the reactor pedestal cavity is disposed by way of an ON-OFF valve. In case if the melted reactor core should fall into the pedestal cavity, the ON-OFF valve for the pressure suppression water introduction pipeway is opened to introduce the pressure suppression water in the suppression chamber into the pedestal cavity to cool the melted reactor core. (Ikeda, J.)

  18. RA Reactor

    International Nuclear Information System (INIS)

    1989-01-01

    This chapter includes the following: General description of the RA reactor, organization of work, responsibilities of leadership and operators team, regulations concerning operation and behaviour in the reactor building, regulations for performing experiments, regulations and instructions for inserting samples into experimental channels [sr

  19. Reactor physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1998-01-01

    Progress in research on reactor physics in 1997 at the Belgian Nuclear Research Centre SCK/CEN is described. Activities in the following four domains are discussed: core physics, ex-core neutron transport, experiments in Materials Testing Reactors, international benchmarks

  20. ETF reactor design status

    International Nuclear Information System (INIS)

    Sager, P.H.

    1981-01-01

    Conceptual design studies of a tokamak Engineering Test Facility (ETF) are being carried out as a joint laboratory--industry effort at the ETF Design Center at Oak Ridge National Laboratory (ORNL). Designs are being developed for two reactors, one with a bundle divertor and one with a poloidal divertor. These machines, which are designed for ignition and a burn time of 100 s, both have a major radius of 5.4 m, a plasma minor radius of 1.3 m, and a D-shaped plasma elongation ratio of 1.6. The plasma chamber must be conditioned at 10 -7 Torr (10 -5 Pa). During the 13 s dwell between burns, the chamber must be pumped down from 3 x 10 -4 to 3 x 10 -5 Torr. In the design with the bundle divertor, four pairs of compound cryopumps, each pump with a 4 m 2 cryosorption pumping surface, are installed to pump down the plasma chamber. In the design with the poloidal divertor, the plasma chamber is evacuated with the ten pairs of compound cryopumps, each pump with a cryosorption pumping surface of 13 m 2 , installed to handle the divertor load. In both cases the pumps are installed in pairs so that one set can be regenerated while the other set is on-line

  1. The differential radiological impact of plutonium recycle in the light-water reactor fuel cycle: effluent discharges during normal operation

    International Nuclear Information System (INIS)

    Bouville, A.; Guetat, P.; Jones, J.A.; Kelly, G.N.; Legrand, J.; White, I.F.

    1980-01-01

    The radiological impact of a light-water reactor fuel cycle utilizing enriched uranium fuel may be altered by the recycle of plutonium. Differences in impact may arise during various operations in the fuel cycle: those which arise from effluents discharged during normal operation of the various installations comprising the fuel cycle are evaluated in this study. The differential radiological impact on the population of the European Communities (EC) of effluents discharged during the recycling of 10 tonnes of fissile plutonium metal is evaluated. The contributions from each stage of the fuel cycle, i.e. fuel fabrication, reactor operation and fuel reprocessing and conversion, are identified. Separate consideration is given to airborne and liquid effluents and account is taken of a wide range of environmental conditions, representative of the EC, in estimating the radiological impact. The recycle of plutonium is estimated to result in a reduction in the radiological impact from effluents of about 30% of that when using enriched uranium fuel

  2. Quality assurance in the project of RECH-2 research reactor

    International Nuclear Information System (INIS)

    Goycolea Donoso, C.; Nino de Zepeda Schele, A.

    1989-01-01

    The implantation of a Quality Assurance Program for the design, supply, construction, installation, and testing of the RECH-2 research reactor, is described in this paper. The obtained results, demonstrate that a Quality Assurance Program constitutes a suitable mean to assure that the installation complies with the safety and reliability requirements. (author)

  3. Reactor core

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

    In a BWR type reactor, a great number of pipes (spectral shift pipes) are disposed in the reactor core. Moderators having a small moderating cross section (heavy water) are circulated in the spectral shift pipes to suppress the excess reactivity while increasing the conversion ratio at an initial stage of the operation cycle. After the intermediate stage of the operation cycle in which the reactor core reactivity is lowered, reactivity is increased by circulating moderators having a great moderating cross section (light water) to extend the taken up burnup degree. Further, neutron absorbers such as boron are mixed to the moderator in the spectral shift pipe to control the concentration thereof. With such a constitution, control rods and driving mechanisms are no more necessary, to simplify the structure of the reactor core. This can increase the fuel conversion ratio and control great excess reactivity. Accordingly, a nuclear reactor core of high conversion and high burnup degree can be attained. (I.N.)

  4. Reactor container

    International Nuclear Information System (INIS)

    Fukazawa, Masanori.

    1991-01-01

    A system for controlling combustible gases, it has been constituted at present such that the combustible gases are controlled by exhausting them to the wet well of a reactor container. In this system, however, there has been a problem, in a reactor container having plenums in addition to the wet well and the dry well, that the combustible gases in such plenums can not be controlled. In view of the above, in the present invention, suction ports or exhaust ports of the combustible gas control system are disposed to the wet well, the dry well and the plenums to control the combustible gases in the reactor container. Since this can control the combustible gases in the entire reactor container, the integrity of the reactor container can be ensured. (T.M.)

  5. Reactor container

    International Nuclear Information System (INIS)

    Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

    1997-01-01

    In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

    A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

  7. Practical decommissioning experience with nuclear installations in the European Community

    International Nuclear Information System (INIS)

    Skupinski, E.

    1992-01-01

    Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by the AEA, BNFL and the CEC at Windermere and the sites of Windscale/Sellafield, where the former Windscale advanced gas-cooled reactor and the Windscale piles are currently being dismantled. The meeting aimed at gathering a limited number of European experts for the presentation and discussion of operations, results and conclusions on techniques and procedures currently applied in the dismantling of large scale nuclear installations in the European Community

  8. On the safety of nuclear installations in the Soviet Union

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    The cooperation agreements between authorities and industries of the Soviet Union and West Germany now are gaining shape in practice. In this context, the framework conditions are of great interest that govern the realisation of the extensive nuclear energy programme of the Soviet Union. The chairman of the State Commission established in 1984 for supervision of nuclear installations and guidance on safety-engineering enhancement of nuclear power plant in the USSR has been interviewed by atw on topics of organisations, measures and regulatory activities in the field of reactor safety and radiation protection. The interview is given in full. (orig.) [de

  9. Gas turbine installations in nuclear power plants in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Sevestedt, Lars [Electrical Equipment and Gas Turbines, Swedish State Power Board, Ringhals Nuclear Power Plant, S-430 22 Vaeroebacka (Sweden)

    1986-02-15

    At each of the four nuclear power stations in Sweden (Ringhals, Forsmark, Oskarshamn, Barsebaeck) gas turbine generating sets have been installed. These units are normally used for peak load operation dictated of grid and System requirements but they are also connected to supply the electrical auxiliary load of the nuclear plant as reserve power sources. The gas turbines have automatic start capability under certain abnormal conditions (such as reactor trips, low frequency grid etc) but they can also be started manually from several different locations. Starting time is approximately 2- 3 minutes from start up to full load. (author)

  10. Gas turbine installations in nuclear power plants in Sweden

    International Nuclear Information System (INIS)

    Sevestedt, Lars

    1986-01-01

    At each of the four nuclear power stations in Sweden (Ringhals, Forsmark, Oskarshamn, Barsebaeck) gas turbine generating sets have been installed. These units are normally used for peak load operation dictated of grid and System requirements but they are also connected to supply the electrical auxiliary load of the nuclear plant as reserve power sources. The gas turbines have automatic start capability under certain abnormal conditions (such as reactor trips, low frequency grid etc) but they can also be started manually from several different locations. Starting time is approximately 2- 3 minutes from start up to full load. (author)

  11. RETRAN-02 installation and verification for the CRAY computer

    International Nuclear Information System (INIS)

    1990-03-01

    The RETRAN-02 transient thermal-hydraulic analysis program developed by the Electric Power Research Institute (EPRI) has been selected as a tool for use in assessing the operation and safety of the SP-100 space reactor system being developed at Los Alamos National Laboratory (LANL). The released versions of RETRAN-02 are not operational on CRAY computer systems which are the primary mainframes in use at LANL requiring that the code be converted to the CRAY system. This document describes the code conversion, installation, and validation of the RETRAN-02/MOD004 code on the LANL CRAY computer system

  12. Nuclear reactor PBMR and cogeneration; Reactor nuclear PBMR y cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J. R.; Alonso V, G., E-mail: ramon.ramirez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    In recent years the nuclear reactor designs for the electricity generation have increased their costs, so that at the moment costs are managed of around the 5000 US D for installed kw, reason for which a big nuclear plant requires of investments of the order of billions of dollars, the designed reactors as modular of low power seek to lighten the initial investment of a big reactor dividing the power in parts and dividing in modules the components to lower the production costs, this way it can begin to build a module and finished this to build other, differing the long term investment, getting less risk therefore in the investment. On the other hand the reactors of low power can be very useful in regions where is difficult to have access to the electric net being able to take advantage of the thermal energy of the reactor to feed other processes like the water desalination or the vapor generation for the processes industry like the petrochemical, or even more the possible hydrogen production to be used as fuel. In this work the possibility to generate vapor of high quality for the petrochemical industry is described using a spheres bed reactor of high temperature. (Author)

  13. Operational safety and reactor life improvements of Kyoto University Reactor

    International Nuclear Information System (INIS)

    Utsuro, M.; Fujita, Y.; Nishihara, H.

    1990-01-01

    Recent important experience in improving the operational safety and life of a reactor are described. The Kyoto University Reactor (KUR) is a 25-year-old 5 MW light water reactor provided with two thermal columns of graphite and heavy water as well as other kinds of experimental facilities. In the graphite thermal column, noticeable amounts of neutron irradiation effects had accumulated in the graphite blocks near the core. Before the possible release of the stored energy, all the graphite blocks in the column were successfully replaced with new blocks using the opportunity provided by the installation of a liquid deuterium cold neutron source in the column. At the same time, special seal mechanisms were provided for essential improvements to the problem of radioactive argon production in the column. In the heavy-water thermal column we have accomplished the successful repair of a slow leak of heavy water through a thin instrumentation tube failure. The repair work included the removal and reconstructions of the lead and graphite shielding layers and welding of the instrumentation tube under radiation fields. Several mechanical components in the reactor cooling system were also exchanged for new components with improved designs and materials. On-line data logging of almost all instrumentation signals is continuously performed with a high speed data analysis system to diagnose operational conditions of the reactor. Furthermore, through detailed investigations on critical components, operational safety during further extended reactor life will be supported by well scheduled maintenance programs

  14. Reactor Safety Commission Code of Practice for Pressurized Water Reactors

    International Nuclear Information System (INIS)

    1990-01-01

    The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

  15. FBR type reactors

    International Nuclear Information System (INIS)

    Otsuka, Masaya; Yamakawa, Masanori; Goto, Tadashi; Ikeuchi, Toshiaki; Yamaki, Hideo.

    1986-01-01

    Purpose: To prevent thermal deformation and making the container compact by improving the cooling performance of main container walls. Constitution: A pipeway is extended from a high pressure plenum below the reactor core and connected to the lower side of the flow channel at the inside of a thermal shielding layer disposed to the inside of the main container wall. Low pressure sodium sent from the low temperature plenum into the high pressure plenum is introduced to the pipeway, caused to uprise in the inside flow channel, then turned for the direction, caused to descend in the outer side flow channel between the main container and the inside flow channel and then returned to the low temperature plenum. A heat insulating layer disposed with argon gas is installed to the inside of the flow channel to reduce the temperature change applied upon reactor scram. An annular linear induction pump capable of changing the voltage polarity is disposed at the midway of the pipeway and the polarity is switched such that the direction of flow of the liquid sodium is exerted as a braking force upon rated operation, whereas exerted as a pumping force upon reactor scram. (Sekiya, K.)

  16. Measurement of chimney dimensions and development of special tools for installation of in-chimney bracket in HANARO

    International Nuclear Information System (INIS)

    Cho, Yeong Garp; Ryu, J. S.; Lee, J. H.; Lee, Y. S; Lee, B. H.

    2000-06-01

    The in-chimney bracket is a structure which supports the guide tubes of irradiation facilities at the irradiation sites of CT, IR1, IR2, OR4 and/or OR5 in HANARO core to reduce the flow-induced vibration and the dynamic response to seismic load. It horizontally supports the middle part of lthe irradiation facilities for CT/IR sites in addition to the robot arms which had already been installed at the reactor pool liner to support the top of the facilities, and supports the top of the guide tubes for OR sites. For these purposes, the in-chimney bracket was installed in the chimney using four siphoning holes located at 70 cm below the chimney top. It is necessary to measure the dimensions of chimney before the design of in-chimney bracket because there must be manufacturing tolerances and the deformation of the chimney due to the load of the system pipes. To implement this, various special tools had been developed to measure the as-built dimensions of the chimney at the elevation of the siphoning holes, and measured the chimney dimensions and the eccentricity of the chimney center from the reactor core center. Also, a special tool was developed for the installation of the in-chimney bracket by remote operating at the pool top 10 meters apart from the chimney. The installation procedures were established through the enough installation rehearsal using the installation tool and the dummhy chimney which was fabricated to the same dimensions of the real chimney, and the installation interference problems were resolved through the preliminaly installation to the reactor chimney. Finally, the in-chimey bracket was successfully installed at the reactor chimney and is well being used for the irradiation test since the installation on May 16, 2000

  17. Fast Reactors and Nuclear Nonproliferation

    International Nuclear Information System (INIS)

    Avrorina, E.N.; Chebeskovb, A.N.

    2013-01-01

    Conclusion remarks: 1. Fast reactor start-up with U-Pu fuel: – dependent on thermal reactors, – no needs in U enrichment, – needs in SNF reprocessing, – Pu is a little suitable for NED, – practically impossible gun-type NED, – difficulties for implosion-type NED: necessary tests, advanced technologies, etc. – Pu in blankets is similar to WPu by isotopic composition, – Use of blanket for production isotopes (e.g. 233 U), – Combined reprocessing of SNF: altogether blanket and core, – Blanket elimination: decrease in Pu production – No pure Pu separation. 2. Fast reactor start-up with U fuel: - Needs in both U enrichment and SNF reprocessing, - Independent of thermal reactors, - Good Pu bred in the core let alone blankets, - NED of simple gun-type design, - Increase of needs in SWU, - Increased demands in U supply. 3. Fast reactors for export: - Uranium shortage, - To replace thermal reactors in future, - No blankets (depends on the country, though), - Fuel supply and SNF take back, - International centers for rendering services of NFC. Time has come to remove from FRs and their NFC the label unfairly identifying them as the most dangerous installations of nuclear power from the standpoint of being a proliferation problem

  18. Nuclear reactor PBMR and cogeneration

    International Nuclear Information System (INIS)

    Ramirez S, J. R.; Alonso V, G.

    2013-10-01

    In recent years the nuclear reactor designs for the electricity generation have increased their costs, so that at the moment costs are managed of around the 5000 US D for installed kw, reason for which a big nuclear plant requires of investments of the order of billions of dollars, the designed reactors as modular of low power seek to lighten the initial investment of a big reactor dividing the power in parts and dividing in modules the components to lower the production costs, this way it can begin to build a module and finished this to build other, differing the long term investment, getting less risk therefore in the investment. On the other hand the reactors of low power can be very useful in regions where is difficult to have access to the electric net being able to take advantage of the thermal energy of the reactor to feed other processes like the water desalination or the vapor generation for the processes industry like the petrochemical, or even more the possible hydrogen production to be used as fuel. In this work the possibility to generate vapor of high quality for the petrochemical industry is described using a spheres bed reactor of high temperature. (Author)

  19. Functional approaches: a new view of nuclear reactors management

    International Nuclear Information System (INIS)

    Papin, B.

    2000-01-01

    Since many years a research program on the future reactors command, has been decided by the CEA, in collaboration with EDF and Framatome. This program aims to enhance the reactor safety by a better control of the installation in any exploitation situations. The paper presents the state of the art and the first reflexions. (A.L.B.)

  20. Evaluation of an automated struvite reactor to recover phosphorus ...

    African Journals Online (AJOL)

    In the present study we attempted to develop a reactor system to recover phosphorus by struvite precipitation, and which can be installed anywhere in the field without access to a laboratory. A reactor was developed that can run fully automated and recover up to 93% of total phosphorus (total P). Turbidity and conductivity ...

  1. Simulation of the TREAT-Upgrade Automatic Reactor Control System

    International Nuclear Information System (INIS)

    Lipinski, W.C.; Kirsch, L.W.; Valente, A.D.

    1984-01-01

    This paper describes the design of the Automatic Reactor Control System (ARCS) for the Transient Reactor Test Facility (TREAT) Upgrade. A simulation was used to facilitate the ARCS design and to completely test and verify its operation before installation at the TREAT facility

  2. Brazilian multipurpose reactor

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    The Brazilian Multipurpose Reactor (RMB) Project is an action of the Federal Government, through the Ministry of Science Technology and Innovation (MCTI) and has its execution under the responsibility of the Brazilian National Nuclear Energy Commission (CNEN). Within the CNEN, the project is coordinated by the Research and Development Directorate (DPD) and developed through research units of this board: Institute of Nuclear Energy Research (IPEN); Nuclear Engineering Institute (IEN); Centre for Development of Nuclear Technology (CDTN); Regional Center of Nuclear Sciences (CRCN-NE); and Institute of Radiation Protection and Dosimetry (IRD). The Navy Technological Center in Sao Paulo (CTMSP) and also the participation of other research centers, universities, laboratories and companies in the nuclear sector are important and strategic partnerships. The conceptual design and the safety analysis of the reactor and main facilities, related to nuclear and environmental licensing, are performed by technicians of the research units of DPD / CNEN. The basic design was contracted to engineering companies as INTERTHECNE from Brazil and INVAP from Argentine. The research units from DPD/CNEN are also responsible for the design verification on all engineering documents developed by the contracted companies. The construction and installation should be performed by specific national companies and international partnerships. The Nuclear Reactor RMB will be a open pool type reactor with maximum power of 30 MW and have the OPAL nuclear reactor of 20 MW, built in Australia and designed by INVAP, as reference. The RMB reactor core will have a 5x5 configuration, consisting of 23 elements fuels (EC) of U{sub 3}Si{sub 2} dispersion-type Al having a density of up to 3.5 gU/cm{sup 3} and enrichment of 19.75% by weight of {sup 23{sup 5}}U. Two positions will be available in the core for materials irradiation devices. The main objectives of the RMB Reactor and the other nuclear and radioactive

  3. Brazilian multipurpose reactor

    International Nuclear Information System (INIS)

    2014-01-01

    The Brazilian Multipurpose Reactor (RMB) Project is an action of the Federal Government, through the Ministry of Science Technology and Innovation (MCTI) and has its execution under the responsibility of the Brazilian National Nuclear Energy Commission (CNEN). Within the CNEN, the project is coordinated by the Research and Development Directorate (DPD) and developed through research units of this board: Institute of Nuclear Energy Research (IPEN); Nuclear Engineering Institute (IEN); Centre for Development of Nuclear Technology (CDTN); Regional Center of Nuclear Sciences (CRCN-NE); and Institute of Radiation Protection and Dosimetry (IRD). The Navy Technological Center in Sao Paulo (CTMSP) and also the participation of other research centers, universities, laboratories and companies in the nuclear sector are important and strategic partnerships. The conceptual design and the safety analysis of the reactor and main facilities, related to nuclear and environmental licensing, are performed by technicians of the research units of DPD / CNEN. The basic design was contracted to engineering companies as INTERTHECNE from Brazil and INVAP from Argentine. The research units from DPD/CNEN are also responsible for the design verification on all engineering documents developed by the contracted companies. The construction and installation should be performed by specific national companies and international partnerships. The Nuclear Reactor RMB will be a open pool type reactor with maximum power of 30 MW and have the OPAL nuclear reactor of 20 MW, built in Australia and designed by INVAP, as reference. The RMB reactor core will have a 5x5 configuration, consisting of 23 elements fuels (EC) of U 3 Si 2 dispersion-type Al having a density of up to 3.5 gU/cm 3 and enrichment of 19.75% by weight of 23 5 U. Two positions will be available in the core for materials irradiation devices. The main objectives of the RMB Reactor and the other nuclear and radioactive facilities are

  4. Reactor building

    International Nuclear Information System (INIS)

    Maruyama, Toru; Murata, Ritsuko.

    1996-01-01

    In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

  5. Reactor container

    International Nuclear Information System (INIS)

    Shibata, Satoru; Kawashima, Hiroaki

    1984-01-01

    Purpose: To optimize the temperature distribution of the reactor container so as to moderate the thermal stress distribution on the reactor wall of LMFBR type reactor. Constitution: A good heat conductor (made of Al or Cu) is appended on the outer side of the reactor container wall from below the liquid level to the lower face of a deck plate. Further, heat insulators are disposed to the outside of the good heat conductor. Furthermore, a gas-cooling duct is circumferentially disposed at the contact portion between the good heat conductor and the deck plate around the reactor container. This enables to flow the cold heat from the liquid metal rapidly through the good heat conductor to the cooling duct and allows to maintain the temperature distribution on the reactor wall substantially linear even with the abrupt temperature change in the liquid metal. Further, by appending the good heat conductor covered with inactive metals not only on the outer side but also on the inside of the reactor wall to introduce the heat near the liquid level to the upper portion and escape the same to the cooling layer below the roof slab, the effect can be improved further. (Ikeda, J.)

  6. Nuclear power station with nuclear reactor accommodated largely secure against catastrophes

    International Nuclear Information System (INIS)

    Rosen, O.

    1987-01-01

    If the nuclear reactor is installed underground near the power station unit, then danger to the environment due to radiation contamination can be largely or nearly completely prevented by a covering of constant thickness or by a covering which can be installed by a catastrophic accident. The extinguishing of a burning reactor is also relatively simple for a reactor accommodated in a pit. The above-mentioned measures can be used individually or combined. (orig./HP) [de

  7. Graphite-water steam-generating reactor in the USSR

    Energy Technology Data Exchange (ETDEWEB)

    Dollezhal, N A [AN SSSR, Moscow

    1981-10-01

    One of the types of power reactor used in the USSR is the graphite-water steam-generating reactor RBMK. This produces saturated steam at a pressure of 7MPa. Reactors giving 1GWe each have been installed at the Leningrad, Kursk, Chernobyl and other power stations. Further stations using reactors of this type are being built. A description is given of the fuel element design, and of the layout of the plant. The main characteristics of RBMK reactors using fuel of rated and higher enrichment are listed.

  8. Modifications and modernization of the Portuguese research reactor (RPI)

    International Nuclear Information System (INIS)

    Cardeira, F.M.; Menezes, J.B.

    1995-01-01

    The Portuguese Research Reactor (RPI) reached its criticality in April 1961 and has successfully operated for more than 30 years without important incidents. Several replacements of equipment and improvements were introduced during this period, the most important occurring in the modernisation period (1987-1991), with the purpose of improving safety and reliability of the reactor exploitation. The reactor has been shut-down during more than two years for important works of replacement and refurbishment of the primary piping and pool lining. The objective of this paper is to describe the main works performed on RPI reactor during its life time concerning replacements, upgrading and modernisation of reactor equipment and installations. (orig.)

  9. Cable handling system for use in a nuclear reactor

    International Nuclear Information System (INIS)

    Crosgrove, R.O.; Larson, E.M.; Moody, E.

    1982-01-01

    A cable handling system for use in an installation such as a nuclear reactor is disclosed herein along with relevant portions of the reactor which, in a preferred embodiment, is a liquid metal fast breeder reactor. The cable handling system provides a specific way of interconnecting certain internal reactor components with certain external components, through an assembly of rotatable plugs. Moreover, this is done without having to disconnect these components from one another during rotation of the plugs and yet without interfering with other reactor components in the vicinity of the rotating plugs and cable handling system

  10. Application of plasma focus installations for a study of the influence ...

    Indian Academy of Sciences (India)

    The appearance of a large number of cracks on the surface of vanadium under the impulse influence of deuterium plasma shows that pure vanadium cannot be used for the construction of thermonuclear fusion reactors. Such PF installations could also be used effectively for the study of other material and construction ...

  11. Helium transfer line installation details.

    CERN Multimedia

    G. Perinic

    2007-01-01

    A particularity of the 32 m long four in one helium transfer line in between the cold box in USC55 and the cavern UX5 is the fact that the transfer line passes through a hole in the crane rail support beam. In order to ensure the alignment of the suspension rail in the interconnecting tunnel with the hole in the rail support as well as the connection points at both ends required precise measurements of the given geometries as well as the installation of a temporary target for the verification of the theoretical predictions.

  12. Rehyd development and installation report

    International Nuclear Information System (INIS)

    Schuch, R.L.; Woodall, H.N.

    1977-12-01

    Rehyd, a low-impedance, HYDRA-type, water transmission line for bremsstrahlung exposures, was installed on the north side of the REBA facility. Rehyd produces 300 kA beams of 1.2 MeV electrons with a pulse width of 170 ns. Nominal x-ray exposure dose capabilities of 7 cal/g and 20 to 25 kJ were realized thus far. A description is given of the specific design parameters and facility layouts including the unique features of the REBA Marx generator/Rehyd line energy-transfer system. Diode configurations, magnetic-field applications, and output measurements are also presented

  13. Fast reactor fuel reprocessing in the UK

    International Nuclear Information System (INIS)

    Allardice, R.H.; Williams, J.; Buck, C.

    1977-01-01

    Enriched uranium metal fuel irradiated in the Dounreay Fast Reactor has been reprocessed and refabricated in plants specifically designed for the purpose in the U.K. since 1961. Efficient and reliable fuel recycle is essential to the development of a plutonium based fast reactor system and the importance of establishing at an early stage fast reactor fuel reprocessing has been reinforced by current world difficulties in reprocessing high burn-up thermal reactor oxide fuel. In consequence, the U.K. has decided to reprocess irradiated fuel from the 250 MW(E) Prototype Fast Reactor as an integral part of the fast reactor development programme. Flowsheet and equipment development work for the small scale fully active demonstration plant have been carried out over the past 5 years and the plant will be commissioned and ready for active operation during 1977. In parallel, a comprehensive waste management system has been developed and installed. Based on this development work and the information which will arise from active operation of the plant a parallel development programme has been initiated to provide the basis for the design of a large scale fast reactor fuel reprocessing plant to come into operation in the late 1980s to support the projected U.K. fast reactor installation programme. The paper identifies the important differences between fast reactor and thermal reactor fuel reprocessing technologies and describes some of the development work carried out in these areas for the small scale P.F.R. fuel reprocessing operation. In addition, the development programme in aid of the design of a larger scale fast reactor fuel reprocessing plant is outlined and the current design philosophy is discussed

  14. The modification of the Rossendorf Research Reactor

    International Nuclear Information System (INIS)

    Gehre, G.; Hieronymus, W.; Kampf, T.; Ringel, V.; Robbander, W.

    1990-01-01

    The Rossendorf Research Reactor is of the WWR-SM type. It is a heterogeneous water moderated and cooled tank reactor with a thermal power of 10 MW, which was in operation from 1957 to 1986. It was shut down in 1987 for comprehensive modifications to increase its safety and to improve the efficiency of irradiation and experimentals. The modifications will be implemented in two steps. The first one to be finished in 1989 comprises: 1) the replacement of the reactor tank and its components, the reactor cooling system, the ventilation system and the electric power installation; 2) the construction of a new reactor control room and of filtering equipment; 3) the renewal of process instrumentation and control engineering equipment for reactor operation, equipment for radiation protection monitoring, and reactor operation and safety documentation. The second step, to be implemented in the nineties, is to comprise: 1) the enlargement of the capacity for storage of spent fuel; 2) the modernization of reactor operations by computer-aided control; 3) the installation of an automated measuring systems for accident and environmental monitoring. Two objects of the modification, the replacement of the reactor tank and the design of a new and safer one as well as the increase of the redundancy of the core emergency cooling system are described in detail. For the tank replacement the exposure data are also given. Furthermore, the licensing procedures based on national ordinances and standards as well as on international standards and recommendations and the mutual responsibilities and activities of the licensing authority and of the reactor manager are presented. Finally, the present state of the modifications and the schedule up to the reactor recommissioning and test operation at full power is outlined

  15. Proper Installation of Replacement Windows | Efficient Windows

    Science.gov (United States)

    Collaborative Foundry Foundry New Construction Windows Window Selection Tool Selection Process Design Guidance Installation Replacement Windows Window Selection Tool Assessing Options Selection Process Design Guidance Installation Understanding Windows Benefits Design Considerations Measuring

  16. Performance evaluation of buried pipe installation.

    Science.gov (United States)

    2010-05-01

    The purpose of this study is to determine the effects of geometric and mechanical parameters characterizing the soil structure interaction developed in a buried pipe installation located under roads/highways. The drainage pipes or culverts installed ...

  17. 14 CFR 171.159 - Installation requirements.

    Science.gov (United States)

    2010-01-01

    ... Installation requirements. (a) The facility must be installed according to accepted good engineering practices... must have a reliable source of suitable primary power, either from a power distribution system or...

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

    The reactor core of nuclear reactors usually is composed of individual elongated fuel elements that may be vertically arranged and through which coolant flows in axial direction, preferably from bottom to top. With their lower end the fuel elements gear in an opening of a lower support grid forming part of the core structure. According to the invention a locking is provided there, part of which is a control element that is movable along the fuel element axis. The corresponding locking element is engaged behind a lateral projection in the opening of the support grid. The invention is particularly suitable for breeder or converter reactors. (orig.) [de

  19. Experience in operation of heavy water reactors

    International Nuclear Information System (INIS)

    Rotaru, Ion; Bilegan, Iosif; Ghitescu, Petre

    1999-01-01

    The paper presents the main topics of the CANDU owners group (COG) meeting held in Mangalia, Romania on 7-10 September 1998. These meetings are part of the IAEA program for exchange of information related mainly to CANDU reactor operation safety. The first meeting for PHWR reactors took place in Vienna in 1989, followed by those in Argentina (1991), India (1994) and Korea (1996). The topics discussed at the meeting in Romania were: operation experience and recent major events, performances of CANDU reactors and safe operation, nuclear safety and operation procedures of PHWR, programs and strategies of lifetime management of installations and components of NPPs, developments and updates

  20. ADVANCED CONTROL FOR A ETHYLENE REACTOR

    Directory of Open Access Journals (Sweden)

    Dumitru POPESCU

    2017-06-01

    Full Text Available The main objective of this work is the design and implementation of control solutions for petrochemical processes, namely the control and optimization of a pyrolysis reactor, the key-installation in the petrochemical industry. We present the technological characteristics of this petrochemical process and some aspects about the proposed control system solution for the ethylene plant. Finally, an optimal operating point for the reactor is found, considering that the process has a nonlinear multi-variable structure. The results have been implemented on an assembly of pyrolysis reactors on a petrochemical platform from Romania.

  1. Pyrometric fuel particle measurements in pressurised reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hernberg, R.; Joutsenoja, T. [Tampere Univ. of Technology (Finland)

    1996-12-01

    A fiberoptic two-colour pyrometric technique for fuel particle temperature and size measurement is modified and applied to three pressurized reactors of different type in Finland, Germany and France. A modification of the pyrometric method for simultaneous in situ measurement of the temperature and size of individual pulverized coal particles at the pressurized entrained flow reactor in Jyvaeskylae was developed and several series of measurements were made. In Orleans a fiberoptic pyrometric device was installed to a pressurised thermogravimetric reactor and the two-colour temperatures of fuel samples were measured. Some results of these measurements are presented. The project belongs to EU`s Joule 2 extension research programme. (author)

  2. A digital controller for the Omega West Reactor

    International Nuclear Information System (INIS)

    Minor, M.M.; Kaufman, M.D.; Smith, T.W.

    1992-05-01

    A new nuclear reactor control system for the Omega West Reactor (OWR) has been designed to replace the aging and hard to maintain controller presently installed. The controller uses single board computers, digital and analog input and output modules, and stepping motor indexers installed on a standard bus (VME bus). The eight poison control rod drive motors are replaced with stepping motors. The control algorithm for the OWR was not changed in order to expedite approval for installation. This report presents the results of the development of the new control system. Included in the report are copies of some of the software that drives the new controller

  3. Radiation embrittlement in pressure vessels of power reactors

    International Nuclear Information System (INIS)

    Kempf, Rodolfo; Fortis, Ana M.

    2007-01-01

    It is presented the project to study the effect of lead factors on the mechanical behavior of Reactor Pressure Vessel steels. It is described the facility designed to irradiate Charpy specimens with V notch of SA-508 type 3 steel at power reactor temperature, installed in the RA-1 reactor. The objective is to obtain the fracture behavior of irradiated specimens with different lead factors and to know their dependence with the diffusion of alloy elements. (author) [es

  4. Flat-plate solar collector - installation package

    Science.gov (United States)

    1978-01-01

    Package includes installation, operation and maintenance manual for collector, analysis of safety hazards, special handling instructions, materials list, installation drawings, and warranty and certification statement. Manual includes instructions for roof preparation and for preparing collector for installation. Several pages are devoted to major and minor repairs.

  5. Experimental installations and instruments at the FRM-II

    International Nuclear Information System (INIS)

    Steichele, E.

    1999-01-01

    The new research reactor FRM-II of the Technical University Munich will be the strongest neutron source in Germany when going into operation in 2001/2002. From the beginnings on it was designed as a multipurpose research reactor based on local traditions, recent experience and new ideas. The reactor will be used for neutron scattering and material science, for fundamental physics with cold and ultracold neutrons, for isotope production, fission fragment acceleration, medical tumor treatment and for a manifold of technical and practical applications like computer tomography with fast and cold neutrons. According to the wide spectrum of applications the reactor needs a manifold of special installations and instruments, which will be introduced in the present paper. The reactor will be equipped with a liquid-D 2 cold source for high resolution neutron scattering and a solid-D 2 UCN source for fundamental physics, with a graphite hot source for high-Q neutron diffraction and a 'converter', which is a U-235 target in the thermal flux maximum to produce fast fission neutrons for medical applications and technical tomography. A series of irradiation plants is designed for production and study of radio-isotopes with half-lives as short as seconds and for phosphor-doping of semiconductor silicon crystals with diameters up to 8 inch. The reactor will be equipped with ten horizontal, one vertical and two inclined beam-tubes, one of the latter ones will take up a most intense, newly developed positron source for solid state physics. Three horizontal beam tubes will look onto the cold source, one of which will take up six neutron guides going into a neutron guide hall 50 x 25 m 2 . Most of the neutron guides will be coated with super-mirror which allows to build effective beam switches for many end-position experiments. The first generation of about 20 instruments and experimental installations as recommended by the instruments committee will be financed by the Federal and

  6. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    A nuclear reactor containment vessel faced internally with a metal liner is provided with thermal insulation for the liner, comprising one or more layers of compressible material such as ceramic fiber, such as would be conventional in an advanced gas-cooled reactor and also a superposed layer of ceramic bricks or tiles in combination with retention means therefor, the retention means (comprising studs projecting from the liner, and bolts or nuts in threaded engagement with the studs) being themselves insulated from the vessel interior so that the coolant temperatures achieved in a High-Temperature Reactor or a Fast Reactor can be tolerated with the vessel. The layer(s) of compressible material is held under a degree of compression either by the ceramic bricks or tiles themselves or by cover plates held on the studs, in which case the bricks or tiles are preferably bedded on a yielding layer (for example of carbon fibers) rather than directly on the cover plates

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    Miyashita, Akio.

    1981-01-01

    Purpose: To facilitate and accelerate a leakage test of valves of a main steam pipe by adding a leakage test partition valve thereto. Constitution: A leakage testing partition valve is provided between a pressure vessel for a nuclear reactor and the most upstream side valve of a plurality of valves to be tested for leakage, a testing branch pipe is communicated with the downstream side of the partition valve, and the testing water for preventing leakage is introduced thereto through the branch pipe. Since main steam pipe can be simply isolated by closing the partition valve in the leakage test, the leakage test can be conducted without raising or lowering the water level in the pressure vessel, and since interference with other work in the reactor can be eliminated, the leakage test can be readily conducted parallel with other work in the reactor in a short time. Clean water can be used without using reactor water as the test water. (Yoshihara, H.)

  8. Reactor container

    International Nuclear Information System (INIS)

    Abe, Yoshihito; Sano, Tamotsu; Ueda, Sabuo; Tanaka, Kazuhisa.

    1987-01-01

    Purpose: To improve the liquid surface disturbance in LMFBR type reactors. Constitution: A horizontal flow suppressing mechanism mainly comprising vertical members is suspended near the free liquid surface of coolants in the upper plenum. The horizontal flow of coolants near the free liquid surface is reduced by the suppressing mechanism to effectively reduce the surface disturbance. The reduction in the liquid surface disturbance further prevails to the entire surface region with no particular vertical variations to the free liquid surface to remarkably improve the preventive performance for the liquid surface disturbance. Accordingly, it is also possible to attain the advantageous effects such as prevention for the thermal fatigue in reactor vessel walls, reactor upper mechanisms, etc. and prevention of burning damage to the reactor core due to the reduction of envolved Ar gas. (Kamimura, M.)

  9. REACTOR SHIELD

    Science.gov (United States)

    Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

    1959-02-17

    Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

  10. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  11. A TRIGA reactor in an industrial laboratory

    International Nuclear Information System (INIS)

    Anders, Oswald U.

    1980-01-01

    The Dow TRIGA Reactor is a well established facility in its industrial environment. It is used extensively for internal Dow projects. The primary use of the TRIGA is as neutron source for NAA. It faces similar technical and organizational challenges as other TRIGA installations and over the years developed its own solutions

  12. Breeder reactors

    International Nuclear Information System (INIS)

    Gollion, H.

    1977-01-01

    The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components [fr

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    Schulze, I.; Gutscher, E.

    1980-01-01

    The core contains a critical mass of UN or U 2 N 3 in the form of a noncritical solution with melted Sn being kept below a N atmosphere. The lining of the reactor core consists of graphite. If fission progresses part of the melted metal solution is removed and cleaned from fission products. The reactor temperatures lie in the range of 300 to 2000 0 C. (Examples and tables). (RW) [de

  14. Reactor technology

    International Nuclear Information System (INIS)

    Erdoes, P.

    1977-01-01

    This is one of a series of articles discussing aspects of nuclear engineering ranging from a survey of various reactor types for static and mobile use to mention of atomic thermo-electric batteries of atomic thermo-electric batteries for cardiac pacemakers. Various statistics are presented on power generation in Europe and U.S.A. and economics are discussed in some detail. Molten salt reactors and research machines are also described. (G.M.E.)

  15. University Reactor Instrumentation Grant. Final report 08/06/1998 - 08/13/1999

    International Nuclear Information System (INIS)

    Bajorek, S. M.

    2000-01-01

    A noble gas air monitoring system was purchased through the University Reactor Instrumentation Grant Program. This monitor was installed in the Kansas State TRIGA reactor bay at a location near the top surface of the reactor pool according to recommendation by the supplier. This system is now functional and has been incorporated into the facility license

  16. J.O. no. 10 of the 13 january 2004, page 991, text no. 14. Decrees, orders. General texts. Decree no. 2004-47 of the 12 january 2004 modifying the decree no. 96-978 of the 31 october 1996 relative to the creation of the nuclear installation no. 162 named EL4-D, installation of storage for the Monts d'Arree power plants materials; J.O. no. 10 du 13 janvier 2004, page 991, texte no. 14. Decrets, arretes, circulaires. Textes generaux. Decret no. 2004-47 du 12 janvier 2004 modifiant le decret no. 96-978 du 31 octobre 1996 relatif a la creation de l'installation nucleaire de base no. 162 denommee EL4-D, installation d'entreposage de materiels de la centrale nucleaire des monts d'Arree

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-06-01

    The reactor EL4, implemented in december 1966, has definitely shutdown on the 31 july 1985. This reactor was an industrial prototype, built and exploited by Cea and EDF. In the framework of the partial dismantling of the installation, the decree 96-978 of the 31 october 1996 agreed the Cea to modify the installation to become a storage installation. (A.L.B.)

  17. Reactor containment

    International Nuclear Information System (INIS)

    Kawabe, Ryuhei; Yamaki, Rika.

    1990-01-01

    A water vessel is disposed and the gas phase portion of the water vessel is connected to a reactor container by a pipeline having a valve disposed at the midway thereof. A pipe in communication with external air is extended upwardly from the liquid phase portion to a considerable height so as to resist against the back pressure by a waterhead in the pipeline. Accordingly, when the pressure in the container is reduced to a negative level, air passes through the pipeline and uprises through the liquid phase portion in the water vessel in the form of bubbles and then flows into the reactor container. When the pressure inside of the reactor goes higher, since the liquid surface in the water vessel is forced down, water is pushed up into the pipeline. Since the waterhead pressure of a column of water in the pipeline and the pressure of the reactor container are well-balanced, gases in the reactor container are not leaked to the outside. Further, in a case if a great positive pressure is formed in the reactor container, the inner pressure overcomes the waterhead of the column of water, so that the gases containing radioactive aerosol uprise in the pipeline. Since water and the gases flow being in contact with each other, this can provide the effect of removing aerosol. (T.M.)

  18. Fast reactors

    International Nuclear Information System (INIS)

    Vasile, A.

    2001-01-01

    Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

  19. Developments in the regulation of research reactors

    International Nuclear Information System (INIS)

    Loy, J.

    2003-01-01

    The International Atomic Energy Agency (IAEA) has data on over 670 research reactors in the world. Fewer than half of them are operational and a significant number are in a shutdown but not decommissioned state. The International Nuclear Safety Advisory Group (INSAG) has expressed concerns about the safety of many research reactors and this has resulted in a process to draw up an international Code of Conduct on the Safety of Research Reactors. The IAEA is also reviewing its safety standards applying to research reactors. On the home front, regulation of the construction of the Replacement Research Reactor continues. During the construction phase, regulation has centred around the consideration of Requests for Approval (RFA) for the manufacture and installation of systems, structures and components important for safety. Quality control of construction of systems, structures and components is the central issue. The process for regulation of commissioning is under consideration

  20. Core monitoring at the WNP-2 reactor

    International Nuclear Information System (INIS)

    Skeen, D.R.; Torres, R.H.; Burke, W.J.; Jenkins, I.; Jones, S.W.

    1992-01-01

    The WNP-2 reactor is a 3,323-MW(thermal) boiling water reactor (BWR) that is operated by the Washington Public Power Supply System. The WNP-2 reactor began commercial operation in 1984 and is currently in its eighth cycle. The core monitoring system used for the first cycle of operation was supplied by the reactor vendor. Cycles 2 through 6 were monitored with the POWERPLEX Core Monitoring Software System (CMSS) using the XTGBWR simulation code. In 1991, the supply system upgraded the core monitoring system by installing the POWERPLEX 2 CMSS prior to the seventh cycle of operation for WNP-2. The POWERPLEX 2 CMSS was developed by Siemens Power Corporation (SPC) and is based on SPC's advanced state-of-the-art reactor simulator code MICROBURN-B. The improvements in the POWERPLEX 2 system are possible as a result of advances in minicomputer hardware

  1. J.O. no. 10 of the 13 january 2004, page 991, text no. 14. Decrees, orders. General texts. Decree no. 2004-47 of the 12 january 2004 modifying the decree no. 96-978 of the 31 october 1996 relative to the creation of the nuclear installation no. 162 named EL4-D, installation of storage for the Monts d'Arree power plants materials

    International Nuclear Information System (INIS)

    2004-06-01

    The reactor EL4, implemented in december 1966, has definitely shutdown on the 31 july 1985. This reactor was an industrial prototype, built and exploited by Cea and EDF. In the framework of the partial dismantling of the installation, the decree 96-978 of the 31 october 1996 agreed the Cea to modify the installation to become a storage installation. (A.L.B.)

  2. Installation of the LHC experimental insertions

    CERN Document Server

    Bartolome-Jimenez, S

    2004-01-01

    The installation of the LHC experimental insertions, and particularly the installation of the low-beta quadrupoles, raises many technical challenges due to the stringent alignment specifications and to the difficulty of access in very confined areas. The compact layout with many lattice elements, vacuum components, beam control instrumentation and the presence of shielding does not allow for any improvisation in the installation procedure. This paper reviews all the constraints that need to be taken into account when installing the experimental insertions. It describes the chronological sequence of installation and discusses the technical solutions that have been adopted.

  3. INSTALLATION OF THE LHC EXPERIMENTAL INSERTIONS

    CERN Document Server

    Bartolome-Jimenez, S

    2004-01-01

    The installation of the LHC experimental insertions, and particularly the installation of the Low-Beta quadrupoles, raises many technical challenges due to the stringent alignment specifications and to the difficulty of access in very confined areas. The compact layout with many lattice elements, vacuum components, beam control instrumentation and the presence of shielding does not allow for any improvisation in the installation procedure. This paper reviews all the constraints that need to be taken into account when installing the experimental insertions. It describes the chronological sequence of installation and discusses the technical solutions that have been adopted.

  4. Wind profiler installed in Antarctica

    Science.gov (United States)

    Balsley, B. B.; Carey, J.; Woodman, R. F.; Sarango, M.; Urbina, J.; Rodriguez, R.; Ragaini, E.

    A VHF (50 MHz) wind profiler was installed in Antarctica at the Peruvian Base “Machu Picchu” on King George Island from January 21 to 26. The wind profiler will provide a first look at atmospheric dynamics over the region.The profiler—the first of its kind in Antarctica—is a National Science Foundationsponsored cooperative project of the University of Colorado, the Geophysical Institute of Peru, the University of Piura (Peru), and the Peruvian Navy. This venture was also greatly facilitated by Peru's Comision Nacional de Asuntos Antartidos and Consejo Nacional de Ciencias y Tecnologia, with additional logis tics support provided by the Argentinean Navy and the Uruguayan Air Force.

  5. NEMP effects on domestic installation

    International Nuclear Information System (INIS)

    Braun, C.; Clemens, P.; Graf, W.; Guidi, P.; Schmidt, H.U.

    1985-01-01

    The measurements have been made in a building of a psychiatric clinic at Alzey/West Germany. The building has been chosen for the measuring campaign because it has its own electrical installation for mains current supply and emergency power supply, apart from systems of the other buildings. The two supply systems DONNERSBERG could be cut off completely from the other mains systems, so that coupling and feed experiments could be made without mains voltage. Current supply to the measuring systems was done by means of extension cables, or by batteries. The wiring for connection to the room circuits is parallel to the exterior wall, so that measurements could be done by using a frame antenna placed outside of the building parallel to the exterior wall. (orig./DG) [de

  6. Generation IV reactors: reactor concepts

    International Nuclear Information System (INIS)

    Cardonnier, J.L.; Dumaz, P.; Antoni, O.; Arnoux, P.; Bergeron, A.; Renault, C.; Rimpault, G.; Delpech, M.; Garnier, J.C.; Anzieu, P.; Francois, G.; Lecomte, M.

    2003-01-01

    Liquid metal reactor concept looks promising because of its hard neutron spectrum. Sodium reactors benefit a large feedback experience in Japan and in France. Lead reactors have serious assets concerning safety but they require a great effort in technological research to overcome the corrosion issue and they lack a leader country to develop this innovative technology. In molten salt reactor concept, salt is both the nuclear fuel and the coolant fluid. The high exit temperature of the primary salt (700 Celsius degrees) allows a high energy efficiency (44%). Furthermore molten salts have interesting specificities concerning the transmutation of actinides: they are almost insensitive to irradiation damage, some salts can dissolve large quantities of actinides and they are compatible with most reprocessing processes based on pyro-chemistry. Supercritical water reactor concept is based on operating temperature and pressure conditions that infers water to be beyond its critical point. In this range water gets some useful characteristics: - boiling crisis is no more possible because liquid and vapour phase can not coexist, - a high heat transfer coefficient due to the low thermal conductivity of supercritical water, and - a high global energy efficiency due to the high temperature of water. Gas-cooled fast reactors combining hard neutron spectrum and closed fuel cycle open the way to a high valorization of natural uranium while minimizing ultimate radioactive wastes and proliferation risks. Very high temperature gas-cooled reactor concept is developed in the prospect of producing hydrogen from no-fossil fuels in large scale. This use implies a reactor producing helium over 1000 Celsius degrees. (A.C.)

  7. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

  8. The SPHINX reactor for engineering tests

    International Nuclear Information System (INIS)

    Adamov, E.O.; Artamkin, K.N.; Bovin, A.P.; Bulkin, Y.M.; Kartashev, E.F.; Korneev, A.A.; Stenbok, I.A.; Terekhov, A.S.; Khmel'Shehikov, V.V.; Cherkashov, Y.M.

    1990-01-01

    A research reactor known as SPHINX is under development in the USSR. The reactor will be used mainly to carry out tests on mock-up power reactor fuel assemblies under close-to-normal parameters in experimental loop channels installed in the core and reflector of the reactor, as well as to test samples of structural materials in ampoule and loop channels. The SPHINX reactor is a channel-type reactor with light-water coolant and moderator. Maximum achievable neutron flux density in the experimental channels (cell composition 50% Fe, 50% H 2 O) is 1.1 X 10 15 neutrons/cm 2 · s for fast neutrons (E > 0.1 MeV) and 1.7 X 10 15 for thermal neutrons at a reactor power of 200 MW. The design concepts used represent a further development of the technical features which have met with approval in the MR and MIR channel-type engineering test reactors currently in use in the USSR. The 'in-pond channel' construction makes the facility flexible and eases the carrying out of experimental work while keeping discharges of radioactivity into the environment to a low level. The reactor and all associated buildings and constructions conform to modern radiation safety and environmental protection requirements

  9. Research reactors; Les piles de recherche

    Energy Technology Data Exchange (ETDEWEB)

    Kowarski, L [Commissariat a l' Energie Atomique, Paris (France). Centre d' Etudes Nucleaires; [Organisation europeenne pour la Recherche Nucleaire, Geneve (Switzerland)

    1955-07-01

    It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

  10. Research reactors; Les piles de recherche

    Energy Technology Data Exchange (ETDEWEB)

    Kowarski, L. [Commissariat a l' Energie Atomique, Paris (France). Centre d' Etudes Nucleaires]|[Organisation europeenne pour la Recherche Nucleaire, Geneve (Switzerland)

    1955-07-01

    It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

  11. Tokamak fusion reactor exhaust

    International Nuclear Information System (INIS)

    Harrison, M.F.A.; Harbour, P.J.; Hotston, E.S.

    1981-08-01

    This report presents a compilation of papers dealing with reactor exhaust which were produced as part of the TIGER Tokamak Installation for Generating Electricity study at Culham. The papers are entitled: (1) Exhaust impurity control and refuelling. (2) Consideration of the physical problems of a self-consistent exhaust and divertor system for a long burn Tokamak. (3) Possible bundle divertors for INTOR and TIGER. (4) Consideration of various magnetic divertor configurations for INTOR and TIGER. (5) A appraisal of divertor experiments. (6) Hybrid divertors on INTOR. (7) Refuelling and the scrape-off layer of INTOR. (8) Simple modelling of the scrape-off layer. (9) Power flow in the scrape-off layer. (10) A model of particle transport within the scrape-off plasma and divertor. (11) Controlled recirculation of exhaust gas from the divertor into the scrape-off plasma. (U.K.)

  12. Safeguards by Design - Experiences from New Nuclear Installation

    International Nuclear Information System (INIS)

    Okko, O.; Honkamaa, T.; Kuusi, A.; Rautjaervi, J.

    2010-01-01

    The experiences obtained from the current construction projects at Olkiluoto clearly point out the need to introduce the safeguards requirements into facility design process at an early stage. The early Design Information is completed, in principle, before the construction. However, during the design of containment, surveillance systems, and non-destructive assay equipment and their cabling, the design requirements for safeguards systems were not available either for the new reactor unit or for the disposal plant with a geological repository. Typically, the official Design Information documents are not available early enough for efficient integration of safeguards systems into new facilities. In case of the Olkiluoto projects, this was due to understandable reasons: at the new reactor unit the design acceptance by the ordering company and by the nuclear safety authorities was a long process, ongoing simultaneously with parts of the construction; and at the geological repository the national legislation assigns the repository the status of a nuclear facility only after the initial construction and research phase of the repository when the long-term safety of the disposal concept is demonstrated. As similar factors are likely to delay the completion of the official Design Information documents with any new reactor projects until the construction is well underway and efficient integration of safeguards systems is impossible. Therefore, the proliferation resistance of new nuclear installations should be addressed in the design phase before the official Design Information documents are finished. This approach was demonstrated with the enlargement of the Olkiluoto spent fuel storage building. For this approach to work, strong national contribution is needed to facilitate the early communication and exchange of information between the IAEA and the other stakeholders to enable the design of facilities that can be efficiently safeguarded. With the renaissance of nuclear

  13. Nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Prescott, R F; George, B V; Baglin, C J

    1978-05-10

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given.

  14. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1978-01-01

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given. (UK)

  15. Bioconversion reactor

    Science.gov (United States)

    McCarty, Perry L.; Bachmann, Andre

    1992-01-01

    A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

  16. Extension of TRIGA reactor capabilities

    International Nuclear Information System (INIS)

    Gietzen, A.J.

    1980-01-01

    The first TRIGA reactor went into operation at 10 kW about 22 years ago. Since that time 55 TRIGAs have been put into operation including steady-state powers up to 14,000 kW and pulsing reactors that pulse to 20,000,000 kW. Five more are under construction and a proposal will soon be submitted for a reactor of 25,000 kW. Along with these increases in power levels (and the corresponding fluxes) the experimental facilities have also been expanded. In addition to the installation of new TRIGA reactors with enhanced capabilities many of the older reactors have been modified and upgraded. Also, a number of reactors originally fueled with plate fuel were converted to TRIGA fuel to take advantage of the improved technical and safety characteristics, including the ability for pulsed operation. In order to accommodate increased power and performance the fuel has undergone considerable evolution. Most of the changes have been in the geometry, enrichment and cladding material. However, more recently further development on the UZrH alloy has been carried out to extend the uranium content up to 45% by weight. This increased U content is necessary to allow the use of less than 20% enrichment in the higher powered reactors while maintaining longer core lifetime. The instrumentation and control system has undergone remarkable improvement as the electronics technology has evolved so rapidly in the last two decades. The information display and the circuitry logic has also undergone improvements for enhanced ease of operation and safety. (author)

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    Scholz, M.

    1976-01-01

    An improvement of the accessibility of that part of a nuclear reactor serving for biological shield is proposed. It is intended to provide within the biological shield, distributed around the circumference of the reactor pressure vessel, several shielding chambers filled with shielding material, which are isolated gastight from the outside by means of glass panes with a given bursting strength. It is advantageous that, on the one hand, inspection and maintenance will be possible without great effort and, on the other, a large relief cross section will be at desposal if required. (UWI) [de

  18. NEUTRONIC REACTOR

    Science.gov (United States)

    Wigner, E.P.; Weinberg, A.W.; Young, G.J.

    1958-04-15

    A nuclear reactor which uses uranium in the form of elongated tubes as fuel elements and liquid as a coolant is described. Elongated tubular uranium bodies are vertically disposed in an efficient neutron slowing agent, such as graphite, for example, to form a lattice structure which is disposed between upper and lower coolant tanks. Fluid coolant tubes extend through the uranium bodies and communicate with the upper and lower tanks and serve to convey the coolant through the uranium body. The reactor is also provided with means for circulating the cooling fluid through the coolant tanks and coolant tubes, suitable neutron and gnmma ray shields, and control means.

  19. BWR type reactor core

    International Nuclear Information System (INIS)

    Tatemichi, Shin-ichiro.

    1981-01-01

    Purpose: To eliminate the variation in the power distribution of a BWR type reactor core in the axial direction even if the flow rate is increased or decreased by providing a difference in the void coefficient between the upper part and the lower parts of the reactor core, and increasing the void coefficient at the lower part of the reactor core. Constitution: The void coefficient of the lower region from the center to the lower part along the axial direction of a nuclear fuel assembly is increased to decrease the dependence on the flow rate of the axial power distribution of the nuclear fuel assembly. That is, a water/fuel ratio is varied, the water in non-boiled region is increased or the neutron spectrum is varied so as to vary the void coefficient. In order to exemplify it, the rate of the internal pellets of the fuel rod of the nuclear fuel assembly or the shape of the channel box is varied. Accordingly, the power does not considerably vary even if the flow rate is altered since the power is varied in the power operation. (Yoshihara, H.)

  20. Startup of Torrey Pines Mark III and Puerto Rico Nuclear Center reactors with TRIGA-FLIP fuel

    Energy Technology Data Exchange (ETDEWEB)

    Chesworth, R. H. [Gulf E and ES, San Diego, CA (United States)

    1972-07-01

    This paper discusses the characteristics of TRIGA FLIP cores in two different geometries: the normal TRIGA single-rod geometry as typified by the installation in the Torrey Pines Mark III reactor; and the four-rod cluster geometry as typified by the conversion core installed in the Puerto Rico Nuclear Center reactor at Mayaguez. In both reactors the fuel is 8-1/2 wt % uranium, 70% enriched in U-235. The hydrogen to zirconium atom ratio is 1.5 to 1.65 and the cladding material is stainless steel. The basic neutronic characteristics of the fuel in both reactor installations are briefly discussed.

  1. Novel Concept of an Installation for Sustainable Thermal Utilization of Sewage Sludge

    Directory of Open Access Journals (Sweden)

    Wilhelm Jan Tic

    2018-03-01

    Full Text Available This study proposes an innovative installation concept for the sustainable utilization of sewage sludge. The aim of the study is to prove that existing devices and technologies allow construction of such an installation by integration of a dryer, torrefaction reactor and gasifier with engine, thus maximizing recovery of the waste heat by the installation. This study also presents the results of drying tests, performed at a commercial scale paddle dryer as well as detailed analysis of the torrefaction process of dried sewage sludge. Both tests aim to identify potential problems that could occur during the operation. The scarce literature studies published so far on the torrefaction of sewage sludge presents results from batch reactors, thus giving very limited data of the composition of the torgas. This study aims to cover that gap by presenting results from the torrefaction of sewage sludge in a continuously working, laboratory scale, isothermal rotary reactor. The study confirmed the feasibility of a self-sustaining installation of thermal utilization of sewage sludge using low quality heat. Performed study pointed out the most favorable way to use limited amounts of high temperature heat. Plasma gasification of the torrefied sewage sludge has been identified that requires further studies.

  2. Spectrometric assembly for portable installations

    International Nuclear Information System (INIS)

    Kluger, A.; Popescu, C.

    1997-01-01

    The components of the portable spectrometric assembly are: - the detecting probe with Na I(Tl) crystal and air-tight case of industrial type; - a microcomputer; - a unit of analogical processing of the signal from the detecting probe; - a single-channel analyzer with adjustable threshold; - commands and display module; - a source of high voltage; - an electrical supply battery. The device uses the method of gamma photons detection in energetic windows. Through theoretical and experimental studies carried out during the prototype development phase, the superiority of this method has been proved as compared with the installations which make use of the classical principle of photon integral detection. The achieved prototype has a basic program enabling the setting of all working parameters (measuring time, discriminating thresholds, discriminators operating conditions, etc.). Through the included interface RS232 it is possible to transmit the data to a more powerful computer in order to continually process the results. The spectrometric assembly, realized on the basis of micro-computers, can be used in a wide range of applications: measurement of thickness and erosion of walls and tubes, measurement of level in closed containers, of soil density, etc. The adjustment for specific application is performed only through a program modification. (authors)

  3. ALARA in European nuclear installations

    International Nuclear Information System (INIS)

    Lefaure, C.; Croft, J.; Pfeffer, W.; Zeevaert, T.

    1995-01-01

    For over a decade the Commission of the European Community has sponsored research projects on the development and practical implementation of the Optimization principle, or as it is often referred to, ALARA. These projects have given rise to a series of successful international Optimization training courses and have provided a significant input to the periodic European Seminars on Optimization, the last one of which took place in April 1993. This paper reviews the approaches to Optimization that have development within Europe and describes the areas of work in the current project. The on-going CEC research project addresses the problem of ALARA and internal exposures, and tries to define procedures for ALARA implementation, taking account of the perception of the hazard as well as the levels of probability of exposure. The relationships between ALARA and work management, and ALARA and decommissioning of installations appear to be other fruitful research areas. Finally, this paper introduces some software for using ALARA decision aiding techniques and databases containing feed back experience developed in Europe

  4. ALARA in European nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Lefaure, C. [CEPN, Fontenay-Aux-Roses (France); Croft, J. [NRPB, Chilton, Didcot (United Kingdom); Pfeffer, W. [GRS, Koeln (Germany); Zeevaert, T. [SCK/CEN, Mol (Belgium)

    1995-03-01

    For over a decade the Commission of the European Community has sponsored research projects on the development and practical implementation of the Optimization principle, or as it is often referred to, ALARA. These projects have given rise to a series of successful international Optimization training courses and have provided a significant input to the periodic European Seminars on Optimization, the last one of which took place in April 1993. This paper reviews the approaches to Optimization that have development within Europe and describes the areas of work in the current project. The on-going CEC research project addresses the problem of ALARA and internal exposures, and tries to define procedures for ALARA implementation, taking account of the perception of the hazard as well as the levels of probability of exposure. The relationships between ALARA and work management, and ALARA and decommissioning of installations appear to be other fruitful research areas. Finally, this paper introduces some software for using ALARA decision aiding techniques and databases containing feed back experience developed in Europe.

  5. ID Barrel installed in cryostat

    CERN Multimedia

    Apsimon, R.; Romaniouk, A.

    Wednesday 23rd August was a memorable day for the Inner Detector community as they witnessed the transport and installation of the central part of the inner detector (ID-barrel) into the ATLAS detector. Many members of the collaboration gathered to witness this moment at Point 1. After years of design, construction and commissioning, the outer two detectors (TRT and SCT) of the ID barrel were moved from the SR1 cleanroom to the ATLAS cavern. The barrel was moved across the car park from building 2175 to SX1. Although only a journey of about 100 metres, this required weeks of planning and some degree of luck as far as the weather was concerned. Accelerometers were fitted to the barrel to provide real-time monitoring and no values greater than 0.1 g were recorded, fully satisfying the transport specification for this extremely precise and fragile detector. Muriel, despite her fear of heights, bravely volunteered to keep a close eye on the detector. Swapping cranes to cross the entire parking lot, while Mur...

  6. Research nuclear reactor RA, Annual Report 2001

    International Nuclear Information System (INIS)

    Sotic, O.

    2002-01-01

    During 2001, activities at the RA research nuclear reactor in were performed according to the Contract about financing of the RA reactor for the period January-December 2001, signed by the Ministry of Science, technology and development of the Republic of Serbia. RA reactor was not operated since shutdown in August 1984. Although, the most of the planned reconstruction activities were finished until 1991, the most important, which was concerned with exchange of the reactor instrumentation, financed by the IAEA, was interrupted due to international sanctions imposed on the country. Since 1992, all the renewal and reconstruction activities were ceased. Continuous aging and degradation of the equipment and facilities demand decision making about the future status of the Ra reactor. Until this decision is made it is an obligation to maintain control and maintenance of ventilation system, power supply, internal transportation system, spent fuel storage, hot cells, electronic fuel surveillance system, and part of the stationary dosimetry system. In 2001, apart from the mentioned activities, actions were undertaken related to maintenance of the reactor building and installations. The most important tasks fulfilled were: protection of the roof of the ventilation system building, purchase and installing the fire protection system and twelve new battery cells in the reactor building. There were no actions concerned with improvement of the conditions for intermediate spent fuel storage. With the support of IAEA, actions were initiated for possible transport of the spent fuel tu Russia. At the end of 2001, preparations were started for possible future decommissioning of the RA reactor. After, renewal of the membership of our country in the IAEA, the Government of Yugoslavia has declared its attitude about the intention of RA reactor decommissioning at the General Conference in September 2001 [sr

  7. Modern electrical installation for craft students

    CERN Document Server

    Scaddan, Brian

    2013-01-01

    Modern Electrical Installation for Craft Students, Volume 2, Third Edition discusses several topics concerning electrical installations. The book is comprised of eight chapters that deal with craft theory, associated subjects, and electrical industries. Chapter 1 covers inductors and inductance, while Chapter 2 tackles capacitors and capacitance. Chapter 3 deals with inductance and capacitance in installation work. The book also discusses cells, batteries, and transformers. The electrical industries, control and earthing, and testing are also dealt with. The last chapter discusses the basic el

  8. Current status and installation of dental PACS

    International Nuclear Information System (INIS)

    Park, Chang Seo; Kim, Kee Deog; Park, Hyok; Jeong, Ho Gul

    2004-01-01

    Picture Archiving and Communication System (PACS) is difficult to implement in the best of situations, but evidence is growing that the benefits are significant. The aims of this study are to analyze the current status of full PACS and establish successful installation standard of dental PACS. Materials and Methods were based on the investigation of current working status and installation standard of PACS, and observation of variable issues to installation of dental PACS. By September 30, 2004, full PACS implementations in their facilities were 88.1% in specialized general hospitals (37 installations out of total 42 hospitals), 59.8% in general hospitals (144 installations out of total 241 hospitals), 12.3% in medical hospitals (116 installations out of total 941 hospitals) and 3.6% in dental hospitals (4 installations out of total 110 hospitals). Only 4 university dental hospitals currently have installed and are operating full PACS. Major obstacle to wide spread of dental PACS is initial high investments. Clinical environments of dental PACS differed from medical situation. Because of characteristic dental practice, the initial investments for dental PACS are generally much greater than those of medical PACS. Also new economic crisis makes users scruple. The best way to overcome these limitations is to establish an economic installation standard for dental PACS. Also the clear technical communication between the customer and the supplier before both sides are committed to the obstacles are critical to its success.

  9. Safety of nuclear installations in Slovakia

    International Nuclear Information System (INIS)

    1998-01-01

    In this part next aspects are described: (1) Site selection (Legislation related to site selection; Meeting criteria at Bohunice and Mochovce sites; International agreements); (2) Design preparation and construction (Designing and construction-relevant legislation; Nuclear installation project preparation of nuclear installation at Mochovce site); (3) Operation (Operator licensing procedure; Operation limits and conditions; Maintenance testing and control documentation for management and operation; Technical support of operation; Analysis of events at nuclear installations and Radioactive waste production); (4) Planned safety upgrading activities at nuclear installations

  10. 14 CFR 171.9 - Installation requirements.

    Science.gov (United States)

    2010-01-01

    ...) The facility must be installed according to accepted good engineering practices, applicable electric... a power distribution system or locally generated, with a supplemental standby system, if needed. (c...

  11. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    The method of operating a water-cooled neutronic reactor having a graphite moderator is described which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40--60 volume percent of the mixture, in contact with the graphite moderator. 2 claims, 4 figures

  12. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield

  13. Reactor facility

    International Nuclear Information System (INIS)

    Suzuki, Hiroaki; Murase, Michio; Yokomizo, Osamu.

    1997-01-01

    The present invention provides a BWR type reactor facility capable of suppressing the amount of steams generated by the mutual effect of a failed reactor core and coolants upon occurrence of an imaginal accident, and not requiring spacial countermeasures for enhancing the pressure resistance of the container vessel. Namely, a means for supplying cooling water at a temperature not lower by 30degC than the saturated temperature corresponding to the inner pressure of the containing vessel upon occurrence of an accident is disposed to a lower dry well below the pressure vessel. As a result, upon occurrence of such an accident that the reactor core should be melted and flown downward of the pressure vessel, when cooling water at a temperature not lower than the saturated temperature, for example, cooling water at 100degC or higher is supplied to the lower dry well, abrupt generation of steams by the mutual effect of the failed reactor core and cooling water is scarcely caused compared with a case of supplying cooling water at a temperature lower than the saturation temperature by 30degC or more. Accordingly, the amount of steams to be generated can be suppressed, and special countermeasure is no more necessary for enhancing the pressure resistance of the container vessel is no more necessary. (I.S.)

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Gilroy, J.E.

    1980-01-01

    An improved cover structure for liquid metal cooled fast breeder type reactors is described which it is claimed reduces the temperature differential across the intermediate grid plate of the core cover structure and thereby reduces its subjection to thermal stresses. (UK)

  15. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

    This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sekine, Katsuhisa.

    1987-01-01

    Purpose: To decrease the thickness of a reactor container and reduce the height and the height and plate thickness of a roof slab without using mechanical vibration stoppers. Constitution: Earthquake proofness is improved by filling fluids such as liquid metal between a reactor container and a secondary container and connecting the outer surface of the reactor container with the inner surface of the secondary container by means of bellows. That is, for the horizontal seismic vibrations, horizontal loads can be supported by the secondary container without providing mechanical vibration stoppers to the reactor container and the wall thickness can be reduced thereby enabling to simplify thermal insulation structure for the reduction of thermal stresses. Further, for the vertical seismic vibrations, verical loads can be transmitted to the secondary container thereby enabling to reduce the wall thickness in the same manner as for the horizontal load. By the effect of transferring the point of action of the container load applied to the roof slab to the outer circumferential portion, the intended purpose can be attained and, in addition, the radiation dose rate at the upper surface of the roof slab can be decreased. (Kamimura, M.)

  17. Reactor system

    International Nuclear Information System (INIS)

    Miyano, Hiroshi; Narabayashi, Naoshi.

    1990-01-01

    The represent invention concerns a reactor system with improved water injection means to a pressure vessel of a BWR type reactor. A steam pump is connected to a heat removing system pipeline, a high pressure water injection system pipeline and a low pressure water injection system pipeline for injecting water into the pressure vessel. A pump actuation pipeline is disposed being branched from a main steam pump or a steam relieaf pipeline system, through which steams are supplied to actuate the steam pump and supply cooling water into the pressure vessel thereby cooling the reactor core. The steam pump converts the heat energy into the kinetic energy and elevates the pressure of water to a level higher than the pressure of the steams supplied by way of a pressure-elevating diffuser. Cooling water can be supplied to the pressure vessel by the pressure elevation. This can surely inject cooling water into the pressure vessel upon loss of coolant accident or in a case if reactor scram is necessary, without using an additional power source. (I.N.)

  18. New about research reactors

    International Nuclear Information System (INIS)

    Egorenkov, P.M.

    2001-01-01

    The multi-purpose research reactor MAPLE (Canada) and concept of new reactor MAPLE-CNF as will substitute the known Canadian research reactor NRU are described. New reactor will be used as contributor for investigations into materials, neutron beams and further developments for the CANDU type reactor. The Budapest research reactor (BRR) and its application after the last reconstruction are considered also [ru

  19. BEACON TSM application system to the operation of PWR reactors

    International Nuclear Information System (INIS)

    Lozano, J. A.; Mildrum, C.; Serrano, J. F.

    2012-01-01

    BEACON-TSM is an advanced core monitoring system for PWR reactor cores, and also offers the possibility to perform a wide range of predictive calculation in support of reactor operation. BEACON-TSM is presently installed and licensed in the 5 Spanish PWR reactors of standard Westinghouse design. the purpose of this paper is to describe the features of this software system and to show the advantages obtainable by a nuclear power plant from its use. To illustrate the capabilities and benefits of BEACON-TSM two real case reactor operating situations are presented. (Author)

  20. Fuel element load/unload machine for the PEC reactor

    International Nuclear Information System (INIS)

    Clayton, K.F.

    1984-01-01

    GEC Energy Systems Limited are providing two fuel element load/unload machines for use in the Italian fast reactor programme. One will be used in the mechanism test facility (IPM) at Casaccia, to check the salient features of the machine operating in a sodium environment prior to the second machine being installed in the PEC Brasimone Reactor. The machine is used to handle fuel elements, control rods and other reactor components in the sodium-immersed core of the reactor. (U.K.)

  1. Ageing management experience at NUR Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Melllal, Sabrina; Rezig, Mohamed; Zamoun, Rachid; Ameur, Azeddin [Nuclear Research Center of Draria, Algiers (Algeria)

    2013-07-01

    NUR is a 1 MW, open pool reactor moderated and cooled by light water. It was commissioned in 1989. NUR is used for education and training in Nuclear Engineering and related topics for COMENA and National Scientific Community. It is also used to perform R and D works and services at national and regional levels. In this presentation, we describe the methodology and the main development activities related to the ageing management at NUR reactor. These activities include inspection actions and development actions to introduce modifications, to solve obsolescence issues in view to implement the required preventive and curative maintenance programs and to improve the performances of the installation. These actions involved mainly the Operation Assistance System of the Reactor (OAS), the secondary cooling loop, the cooling tower. A new OAS using a new technology and having more possibilities than the older one was introduced in the control system of the reactor. The OAS hardware structure, software structure and the main functions performed are presented. The second loop is entirely refurbished. Two new cooling towers are installed and connected to the main heat exchanger with new piping and valves. The architecture of this new installation is described and the performance assessed. Other actions which involve auxiliary systems like emergency electrical system, air pneumatic system and automatic fire extinguishing are presented.

  2. The Thermos process heat reactor

    International Nuclear Information System (INIS)

    Lerouge, Bernard

    1979-01-01

    The THERMOS process heat reactor was born from the following idea: the hot water energy vector is widely used for heating purposes in cities, so why not save on traditional fossil fuels by simply substituting a nuclear boiler of comparable power for the classical boiler installed in the same place. The French Atomic Energy Commission has techniques for heating in the big French cities which provide better guarantees for national independence and for the environment. This THERMOS technique would result in a saving of 40,000 to 80,000 tons of oil per year [fr

  3. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

    1994-01-01

    In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

  4. Extension of the technical scope of the Paris and Vienna Conventions: fusion reactors and reactors in means of transport

    International Nuclear Information System (INIS)

    Reye, S.

    1993-01-01

    This paper examines the possibility of extending the technical scope of the Vienna and Paris Conventions to two types of nuclear installation presently excluded. Industrial use of fusion reactors is not expected for several decades, but the present revision of the liability regime provides a useful opportunity to ensure in advance that future industrial reactors will be covered, as well as covering risks arising from existing research reactors. Inclusion of nuclear reactors comprised in means of transport (in practice, in ships) in the liability regime would have certain advantages, but given their almost exclusively military use, such a proposal would be politically controversial. 18 refs

  5. Radiation shield for nuclear reactors

    International Nuclear Information System (INIS)

    Weissenfluh, J.A.

    1980-01-01

    A reusable radiation shield for use in a reactor installation comprises a thin-walled, flexible and resilient container, made of plastic or elastomeric material, containing a hydrogenous fluid with boron compounds in solution. The container can be filled and drained in position and the fluid can be recirculated if required. When not in use the container can be folded and stored in a small space. The invention relates to a shield to span the top of the annular space between a reactor vessel and the primary shield. For this purpose a continuous toroidal container or a series of discrete segments is used. Other forms can be employed for different purposes, e.g. mattress- or blanket-like forms can be draped over potential sources of radiation or suspended from a mobile carrier and placed between a worker and a radiation source. (author)

  6. The fast reactor and energy supply

    International Nuclear Information System (INIS)

    1979-01-01

    The progress made with fast reactor development in many countries is summarised showing that the aim is to provide to the nation concerned an ability to instal fast reactor power stations at the end of this century or early in the next one. Accepting the importance of fast reactors as a potential independent source of energy, problems concerning economics, industrial capability, technical factors, public acceptibility and in particular plutonium management, are discussed. It is concluded that although fast reactors have reached a comparatively advanced stage of development, a number of factors make it likely that their introduction for electricity generation will be a gradual process. Nevertheless it is necessary to complete demonstration and development phases in good time. (U.K.)

  7. Occupational analysis for the Angra-1 reactor

    International Nuclear Information System (INIS)

    Moraes, A.

    1991-01-01

    Due to several modifications which were imposed to its time schedule during construction, the Angra-1 reactor did not enter to the grid in 1982 as it was initially foreseen. These modifications occurred due to an unforeseen scenario that was verified in steam generators (serie D-3, Westinghouse) of power stations with similar configurations which had been installed in other countries such as Ringhals-3 (Sweden), Almaraz-1 (Spain) and McGuine-1 (USA). So, among the main events that occurred in the Angra-1 reactor, which were of interest from the point of view of radiation protection, it could be pointed out the personnel monitoring, and the occupational exposure measurements at different reactor power, during the reactor fueling and during modification and tests performed at the steam generators and at ducts of the primary coolant circuit. (author)

  8. Which life expectancy for EDF reactors?

    International Nuclear Information System (INIS)

    Carlier, P.; Fluchere, J.; Giraud, B.; Poizat, F.

    2008-01-01

    After having recalled that the French nuclear reactors have been designed for a 40-year long life with a 30-year depreciation, the authors notice that foreign reactors which are identical or older get a 60 year operation authorization. The authors analyse the age of the nuclear reactors which are currently operating in the world, in terms of age, of country. They also discuss the license renewal process in the USA. In the next part they analyse the conditions of a life extension to 60 years. These conditions concern material monitoring, maintenance strategy for the replacement of components, the condition of installations, personnel management and behaviour. Appendices contain a table of operating reactors which are still being operated and more than 30 year old, the status of license renewal applications to the US NRC

  9. 49 CFR 393.30 - Battery installation.

    Science.gov (United States)

    2010-10-01

    ... NECESSARY FOR SAFE OPERATION Lamps, Reflective Devices, and Electrical Wiring § 393.30 Battery installation... 49 Transportation 5 2010-10-01 2010-10-01 false Battery installation. 393.30 Section 393.30 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL MOTOR CARRIER SAFETY...

  10. Installation package for the Solaron solar subsystem

    Science.gov (United States)

    1979-01-01

    Information that is intended to be a guide for installation, operation, and maintenance of the various solar subsystems is presented. The subsystems consist of the following: collectors, storage, transport (air handler) and controller for heat pump and peak storage. Two prototype residential systems were installed at Akron, Ohio, and Duffield, Virginia.

  11. Data Acquisition System On Beta Installation

    International Nuclear Information System (INIS)

    Abtokhi, Ahmad; Nurhanan; Sudarno; Sumarno, Edy

    2000-01-01

    Data acquisition system is needed on every installation. This is important used to monitoring and processing data to get information desired. This system applied to β installation which is facility to carry out experiments on accident condition like as reflooding phenomena in test section. The 16 exp.th channel data acquisition system is drived by ADC 0804 and programme application DELPHI

  12. ATLAS semiconductor tracker installed into its barrel

    CERN Multimedia

    Maximilien Brice

    2005-01-01

    The ATLAS silicon tracker is installed in the silicon tracker barrel. Absolute precision was required in this operation to ensure that the tracker was inserted without damage through minimal clearance. The installation was performed in a clean room on the CERN site so that no impurities in the air would contaminate the tracker's systems.

  13. Demographic characteristics of nuclear installations sites

    International Nuclear Information System (INIS)

    Doumenc, A.; Faure, J.

    1988-01-01

    The selection of a nuclear installations sites can not be conceived without a deep analysis of demographic context. This analysis permits to define the critical populations around the installation and is an essential element of emergency plans. 1 tab., 2 refs. (F.M.)

  14. Using game engines in mixed reality installations

    NARCIS (Netherlands)

    Nakevska, M.; Vos, E.C.; Juarez, Alex; Hu, J.; Langereis, G.R.; Rauterberg, G.W.M.; Anacleto, J.; Fels, S.; Graham, N.; et al., xx

    2011-01-01

    In a mixed reality installation, a variety of technologies is integrated such as virtual reality, augmented reality, and animated virtual agents and robotic agents. One of the main challenges is how to design and implement a mixed reality installation that integrates a heterogeneous array of sensors

  15. Installed water resource modelling systems for catchment ...

    African Journals Online (AJOL)

    Following international trends there are a growing number of modelling systems being installed for integrated water resource management, in Southern Africa. Such systems are likely to be installed for operational use in ongoing learning, research, strategic planning and consensus-building amongst stakeholders in the ...

  16. Installation Service - Changes in opening hours

    CERN Multimedia

    GS Department

    2010-01-01

    For organizational matters, please note that, as from 15 March 2010, the Installation Service will have wen opening hours. The new schedule will be from 14:00 to 17:00 (Monday to Friday). Contact persons are: Martine Briant, Karine Robert and Claudia Bruggmann. The office address remains 73-3-014. Installation Service

  17. Some corrosion effects of the aluminum tank surface of Dalat research reactor

    International Nuclear Information System (INIS)

    Nguyen Mong Sinh

    1995-01-01

    The Dalat Nuclear Research Reactor was reconstructed from the TRIGA-MARK-II reactor installed in 1963 with a nominal power of 250 kW. Reconstruction and upgrading of this reactor to nominal power of 500 kW had been completed in the end of 1983. The reactor was commissioned in the beginning of March 1984. The aluminum reactor tank and some components of the former reactor are more than 30 year old. The good quality of reactor water minimized the total corrosion rate of reactor material surface. But some local corrosion had been found out at the tank bottom especially in water stagnant areas. The corrosion processes could be due to the electrochemical reactions associated with different metals and alloys in the reactor water and keeping in touch with the surface of aluminum reactor tank. (orig.)

  18. Public perception of nuclear installations

    International Nuclear Information System (INIS)

    Kiipper, Felipe de Moura

    2011-01-01

    The key for nuclear renaissance is public acceptance. Facing energetic needs that occur around the world and lack of resources, the work of characterizing and proposing new models to represent public opinion is extremely important to all stakeholders. Even though public opinion's study on risks is relatively recent, may approaches of this subject have been suggested and presented, especially for the topic of perceptions on nuclear installations. Actual definitions on risk exist between objective and subjective models, that reflect opinions of lay public and experts. Strategies on communications with the public may be evaluated from many developed models, and its results may be registered. The use of structural models may present an exploratory character as well as confirmatory theories, as an adequate tool for the development of studies on public perception. In this work, a structural model is presented from data obtained in a previous report, and added to data collected before and after the Fukushima nuclear accident, in Japan. The effects developed from this accident offered a unique opportunity to study public opinion through the effects of a serious nuclear accident and its effects on risk communications. Aside, this work attempted to check the structural model according with obtained results, in order to sustain a constant improvement of the working tools. Yet, a comparison between data according to experts' respondents and lay public ones as well as a comparison among different students before and after a visit to nuclear station is considered. Obtained data for the structural models has been applied for on a structural model and analyzed by structural correlation matrix, latent variable structural coefficients and R 2 values. Results indicate that public opinion maintains its rejection on nuclear energy and the perception of benefits, facing perceived risks before the accident, has diminished. A new model that included a latent variable for corresponding

  19. Education for university students, high school teachers and the general public using the Kinki University Reactor

    International Nuclear Information System (INIS)

    Tsuruta, T.

    2007-01-01

    Atomic Energy Research Institute of Kinki University is equipped with a nuclear reactor which is called UTR-KINKI. UTR is the abbreviation for University Teaching and Research Reactor. The reactor is the first one installed in Japanese universities. Though the reactor is owned and operated by Kinki University, its use is widely open to scientists and students from other universities and research institutions. The reactor is made the best of teaching instrument for the training of high school teachers. In addition, the reactor is utilized for general public education concerning atomic energy. (author)

  20. Buckling of Bucket Foundations During Installation

    DEFF Research Database (Denmark)

    Madsen, Søren

    There is a great politically will to expand the green energy market in these times. A proven green technology is wind turbines. Wind turbines have been installed in great numbers on land over the last decades. However, the current development in wind turbine design leads to larger turbine sizes...... in order to reduce the cost of energy. This limits the on land application due to transportation limitations and unwillingness from prospect neighbours. Thus, offshore wind energy started developing over the last couple of years. Although installing the wind turbines offshore resolves the before men tioned...... issues, it brings up the cost of energy mainly due to increased installation and maintenance costs. A very large part—up to 30–50% using current technology—of the installation cost origins from the expenses related to the installation of foundations. A new foundation concept—the bucket foundation...