WorldWideScience

Sample records for mochovce final treatment

  1. Mochovce waste treatment centre

    International Nuclear Information System (INIS)

    Sedliak, D.; Endrody, J.

    2000-01-01

    The first unit of the Mochovce NPP (WWER 440 MW) was put in a test operation in October 1998. The second unit with the same power output was put in the test operation in March 2000. The Nuclear Regulatory Authority of the Slovak Republic in its Decision No. 318/98 of 28 October 1998, by which an agreement with the operation of the Unit 1 of the Mochovce. Nuclear Power Plant was issued, requires to start the construction of the Liquid Radioactive Waste Treatment Centre until January 2004. The subject of this presentation is a system description of the Liquid Radioactive Waste (LRW) management in the Mochovce NPP. The initial part is dedicated to a short description of the radioactive waste management legislation requirements. Then the presentation continues with an information about the LRW production in the Mochovce NPP, LRW sources, chemical and radiochemical attributes, description of storage. The presentation also provides real values of its production in a comparison with the design data. The LRW production minimization principles are also mentioned there. Another part deals with the basic requirements for the technology proposal of the liquid RW treatment, especially concerning the acceptance criteria at the Republic RW Repository Mochovce. The final part is devoted to a short description of the investment procedure principles - design preparation levels and a proposed construction schedule of the centre. (authors)

  2. National radioactive wasterRepository Mochovce

    International Nuclear Information System (INIS)

    2000-01-01

    In this leaflet the scheme of the Mochovce National radioactive waste repository for the Slovak Republic is presented. The National radioactive waste repository in Mochovce is a surface type storage facility. It is intended for final disposal of solid and solidified low and intermediate radioactive waste produced during the operation of nuclear power plants and institutions located within the territory of the Slovak Republic. The Repository site is situated about 2 km northwest to the Mochovce NPP

  3. Mochovce site

    International Nuclear Information System (INIS)

    1997-01-01

    In Mochovce site the construction of four units of WWER 440 NPP with V-213 type of reactor is being carried out. The financing of Mochovce units completion was resolved in April 1996. The completion work commenced at the construction site under leadership of SKODA Prague, the general supplier. The completion work on building part and tests of constructional electric distributions and lightning constructors started. The revisions in technological part were finished, and final protocols from revisions are the basis for starting of completion work. The assembly of transport container anchorage,ventilation system in hermetic areas and hermetic coverage of pools for stored spent nuclear fuel is being carried out. The pre-completion tests of instrumentation and control of ventilation systems, individual dosimetric control in medical station, and tests of nuclear programme according to commissioning and assembling work schedule at the equipment for physical protection of the NPP area started. Inspection activities at Mochovce were performed in accordance with inspection plan for 1996. Evaluation of routine inspections was performed by means of quarterly protocols. Main findings from the inspections performed in Mochovce were in the following areas: (a) deficiencies in the knowledge of the respective regulation and conditions from the Resolution of the state regulatory body, concerning selected employees; (b) training of the selected employees; (c) aim of the measures imposes by inspectors is to eliminate deficiencies in preparation of programmes for pre-completion and completion testing. NRA SR assessment activities at Mochovce NPP were focused mainly on approving and inspecting of design modification to approving programmes for pre-completion and completion testing of system s and equipment and on approving quality assurance programmes. The suggestions of international missions, which reviewed Mochovce safety in the years, were taken into consideration in the programme

  4. Final treatment of liquid radioactive wastes

    International Nuclear Information System (INIS)

    Svolik, S.

    2004-01-01

    Final treatment of liquid radioactive wastes which are produced by 1 st and 2 nd bloc of the Mochovce NPP, prepares the NPP in its natural range. The purpose of the equipment is liquidation of wastes, which are formed at production. Wastes are warehoused in the building of active auxiliary plants in the present time, where are reservoirs in which they are deposited. Because they are already feeling and in 2006 year they should be filled definitely, it is necessary to treat them in that manner, so as they may be liquidated. Therefore the Board of directors of the Slovenske elektrarne has disposed about construction of final treatment of liquid radioactive wastes in the Mochovce NPP. Because of transport the wastes have to be treated in the locality of power plant. Technically, the final treatment of the wastes will be interconnected with building of active operation by bridges. These bridges will transport the wastes for treatment into processing centre

  5. Mochovce Unit 3 and 4 Completion

    International Nuclear Information System (INIS)

    Aquilanti, G.

    2007-01-01

    Purpose of the Feasibility Study was to define in detail all technical, economic, financial, legal and authorization aspects of Mochovce NPP Unit 3 and 4 completion in order to provide Slovenske Elektrarne, a. s. (SE) and ENEL Top Management with all the necessary information for a final decision on Mochovce Unit 3 and 4. Feasibility study has started in January 2006. SE had the commitment to complete the Feasibility Study within 12 months from Closing of SE acquisition (April 2007). In order not to delay completion of Mochovce Unit 3 and 4, SE has decided to perform, in parallel to the Feasibility study, also all design and permitting activities which are required for the completion of Plant. This has involved anticipation of expenses for approximately 700 MSKK (or approx. 20 MEuro). SE was able to announce the positive decision about completion on Mochovce NPP Unit 3 and 4, two months in advance of the deadline.

  6. Safety upgrading program in NPP Mochovce

    International Nuclear Information System (INIS)

    Baumeister, P.

    1999-01-01

    EMO interest is to operate only nuclear power plants with high standards of nuclear safety. This aim EMO declare on preparation completion and commissioning of Mochovce Nuclear Power Plant. Wide co-operation of our company with International Atomic Energy Agency and west European Inst.ions and companies has been started with aim to fulfil the nuclear safety requirements for Mochovce NPP. Set of 87 safety measures was implemented at Mochovce Unit 1 and is under construction at Unit 2. Mochovce NPP approach to safety upgrading implementation is showed on chosen measures. This presentation is focused on the issues category III.(author)

  7. The seismic reassessment Mochovce NPP

    International Nuclear Information System (INIS)

    Baumeister, P.

    2004-01-01

    The design of Mochovce NPP was based on the Novo-Voronez type WWER-440/213 reactor - twin units. Seismic characteristic of this region is characterized by very low activity. Mochovce NPP site is located on the rock soil with volcanic layer (andesit). Seismic reassessment of Mochovce NPP was done in two steps: deterministic approach up to commissioning confirmed value Horizontal Peak Ground Acceleration HPGA=0.1 g and activities after commissioning as a consequence of the IAEA mission indicate higher hazard values. (author)

  8. Recent history of Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    Holy, R.

    1999-01-01

    Mochovce Nuclear Power Plant has been an open project involving a wide international co-operation of numerous organisations of countries stretching from the Atlantic coast up to the Urals that make it a truly European project. The units at Mochovce are the later V-213 type of Soviet-designed WWER-440 reactors. They therefore incorporate a number of improvements over the earlier V-230 type. There are four units at Mochovce site: unit 1 has been in operation since summer 1998, unit 2 is currently in the stage of commissioning tests and scheduled for operation by the end of this year, and unit 3 and 4 are still waiting for the final governmental decision about their completion, currently 40% and 30% completed respectively. Beginning in 1981, the construction works were stopped in early 90's due to the decision on replacement of the original I and C system, as well as lack of funding afterwards. Slovenske elektrarne, a.s. have been working to resuscitate the project focusing initially on completion of the units 1 and 2 with assistance of western companies. one month later the governmental guarantees were given for loans and Slovenske elektrarne signed loan agreements to finance the project completion, as well as construction completion agreements with contractors. (Author)

  9. Safety culture at Mochovce NPP

    International Nuclear Information System (INIS)

    Markus, Jozef; Feik, Karol

    2002-01-01

    This article presents the approach of Mochovce NPP to the Safety culture. It presents activities, which have been taken by Mochovce NPP up to date in the area of Safety culture enhancement with the aim of getting the term into the subconscious of each employee, and thus minimising the human factor impact on occurrence of operational events in all safety areas. The article furthermore presents the most essential information on how the elements characterising a continuous progress in reaching the planned Safety culture goals of the company management have been implemented at Mochovce NPP, as well as the management's efforts to get among the best nuclear power plant operators in this area and to be an example for the others. (author)

  10. Mochovce NPP simulator

    International Nuclear Information System (INIS)

    Ziakova, M.

    1998-01-01

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

  11. Radioactive waste handling at the Mochovce NPP, 1998-2008

    International Nuclear Information System (INIS)

    Vasickova, Gabriela

    2009-01-01

    The radioactive waste management system at the Mochovce NPP is described. The system addresses technical aspects as well as administrative provisions related to radioactive waste generated within the controlled area, from the waste generation phase to waste sorting, packaging, storage, recording, measurement, and transportation to the Bohunice waste processing facility or transfer to the Mochovce liquid radioactive waste treatment facility. The article also addresses conditions for release from the controlled area to the environment for radioactive waste which can be exempt from the institutional administrative control system or released to the environment on the basis of a valid permission issued by the relevant regulatory authority

  12. Performance assessment of Mochovce repository

    Energy Technology Data Exchange (ETDEWEB)

    Mrskova, A; Hanusik, V [Dept. of Accident Management and Risk Assessment, Vyskumny Ustav Jadrovych Elektrarni, Trnava (Slovakia)

    2000-07-01

    The near-surface disposal site at Mochovce is designed for low-level and intermediate level radioactive waste. It is a vault-type concrete structure housing the reinforced concrete containers as the final waste packages. This paper shortly presents the long-term safety analysis methods applied for the post-closure phase of the repository. The main aim of paper is description of the philosophy of analysis, development of the scenarios, their modeling and comparing of the results of normal evolution scenario, alternative scenario and intruders scenario for some radionuclides. (author)

  13. Performance assessment of Mochovce repository

    International Nuclear Information System (INIS)

    Mrskova, A.; Hanusik, V.

    2000-01-01

    The near-surface disposal site at Mochovce is designed for low-level and intermediate level radioactive waste. It is a vault-type concrete structure housing the reinforced concrete containers as the final waste packages. This paper shortly presents the long-term safety analysis methods applied for the post-closure phase of the repository. The main aim of paper is description of the philosophy of analysis, development of the scenarios, their modeling and comparing of the results of normal evolution scenario, alternative scenario and intruders scenario for some radionuclides. (author)

  14. Final Treatment Center Project for Liquid and Wet Radioactive Waste in Slovakia

    International Nuclear Information System (INIS)

    Kravarik, K.; Stubna, M.; Pekar, A.; Krajc, T.; Zatkulak, M.; Holicka, Z.; Slezak, M.

    2006-01-01

    The Final Treatment Center (FTC) for Mochovce nuclear power plant (NPP) is designed for treatment and final conditioning of radioactive liquid and wet waste produced from plant operation. Mochovce NNP uses a Russian VVER-440 type reactor. Treated wastes comprise radioactive concentrates, spent resin and sludge. VUJE Inc. as an experienced company in field of treatment of radioactive waste in Slovakia has been chosen as main contractor for technological part of FTC. This paper describes the capacity, flow chart, overall waste flow and parameters of the main components in the FTC. The initial project was submitted for approval to the Slovak Electric plc. in 2003. The design and manufacture of main components were performed in 2004 and 2005. FTC construction work started early in 2004. Initial non-radioactive testing of the system is planned for summer 2006 and then radioactive tests are to be followed. A one-year trial operation of facility is planned for completion in 2007. SE - VYZ will be operates the FTC during trial operation and after its completion. SE - VYZ is subsidiary company of Slovak Electric plc. and it is responsible for treatment with radioactive waste and spent fuel in the Slovak republic. SE - VYZ has, besides of other significant experience with operation of Jaslovske Bohunice Treatment Centre. The overall capacity of the FTC is 870 m 3 /year of concentrates and 40 m 3 /year of spent resin and sludge. Bituminization and cementation were provided as main technologies for treatment of these wastes. Treatment of concentrate is performed by bituminization. Concentrate and bitumen are metered into a thin film evaporator with rotating wiping blades. Surplus water is evaporated and concentrate salts are embedded in bitumen. Bitumen product is discharged into 200 l steel drums. Spent resin and sludge are decanted, dried and mixed with bitumen. These mixtures are also discharged into 200 l steel drums. Drums are moved along bituminization line on a roller

  15. NPP Mochovce nuclear safety enhancement program

    International Nuclear Information System (INIS)

    Cech, J.; Baumester, P.

    1997-01-01

    Nuclear power plant Mochovce is currently under construction and an extensive nuclear safety enhancement programme is under way. The upgrading and modifications are based on IAEA documents and on those of the Nuclear Regulatory Authority of the Slovak Republic. Based on a contract concluded with Riskaudit from the CEC, safety examinations of the Mochovce design were performed. An extensive list of technical specifications of safety measures is given. (M.D.)

  16. Slovak Electric, plc, Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    2000-01-01

    In this popular scientific brochure a brief description of history construction of Bohunice Nuclear Power Plant is presented. The chart of electricity generation in WWER 440/V-213 nuclear power plant is described. Operation and safety improvements at Mochovce NPP as well as environment protection are presented. Basic data of Mochovce NPP are included

  17. EGP contribution to Mochovce completion, safety enhancement and operation

    International Nuclear Information System (INIS)

    Letko, A.; Matula, P.

    2000-01-01

    The Re-Evaluation Programme of Mochovce NPP was created in 1995 as an integral part of the completion of the Unit 1 and Unit 2. This program analyzed the general fulfillment of the principle of nuclear safety in the NPP Mochovce project. The analysis has required new corrections of the project, so that the project met the higher safety requirements when starting production. 87 safety measures represent the 'Program'. The basis for their creation were the international missions from 1992 to 1995 which defined. The final safety aim was represented by 'The Technical Specification of the Safety Measures' supported by The Nuclear Power Plant Research Institute and recommended by The Nuclear Regulatory Authority of the Slovak Republic. The technical specification served as a qualified base for the next steps in the pre-project, project and realization stages. (author)

  18. Regulatory requirements for demonstration of the achieved safety level at the Mochovce NPP before commissioning

    International Nuclear Information System (INIS)

    Lipar, M.

    1997-01-01

    A review of regulatory requirements for demonstration of the achieved safety level at the Mochovce NPP before commissioning is given. It contains licensing steps in Slovakia during commissioning; Status and methodology of Mochovce safety analysis report; Mochovce NPP safety enhancement program; Regulatory body policy towards Mochovce NPP safety enhancement; Recent development in Mochovce pre-operational safety enhancement program review and assessment process; Licensing steps in Slovakia during commissioning

  19. National Radwaste Repository Mochovce

    International Nuclear Information System (INIS)

    2000-01-01

    In this leaflet the National Radioactive Waste Repository in Mochovce (Repository) is described. The Mochovce National Radioactive Waste Repository is a surface multi-barrier type storage facility for solid and treated solidified radioactive wastes generated from the Slovak Republic nuclear power plants operation and decommissioning, research institutes, laboratories and hospitals. The Repository comprises a system of single- and double-row storage boxes. The first double-row is enclosed by a steel-structure building. The 18 x 6 x 5.5 m storage boxes are made of reinforced concrete. The wall thickness is 600 mm. Two-double-rows, i.e. 80 storage boxes were built as part of Stage I (1 row = 20 storage boxes). Each storage box has a storage capacity of 90 fibre concrete containers of 3.1 m 3 volume. The total storage capacity is 7200 containers with the overall storage volume of 22320 m 3

  20. The confirmation audit in Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Andlova, Z.

    2004-01-01

    Mochovce NPP, as the first plant of the Slovenske elektrarne, a. s., has obtained certificate for the environmental management system (EMS) in September 2002, which was established according to the standard STN ISO 14 001:1996. The Audit EMS was executed by the Det Norske Veritas. Mochovce NPP has obtained the EMS Certificate after compliance of process requests and it is valid for three years. After expire of this period the certification process must be repeated. (author)

  1. Actual status of project Mochovce NPP units 3 and 4 completion

    International Nuclear Information System (INIS)

    Niznan, S.

    2005-01-01

    In this presentation author deals with actual status of project Mochovce NPP units 3 and 4 completion. Present state of Mochovce NPP, Units 3 and 4 enables real assumption to completion. It is expected that such supplier companies can be used which are experienced in field of nuclear projects. Based on budget of 2002, it seems that completion costs of 45 billions SKK are real. These figures were confirmed by study performed by TRACTEBEL in 2004. Based on experience from Bohunice NPP completion as well as from Mochovce NPP, Units 1 and 2 completion and if decision milestone and project start up deadlines will be observed according to modified preliminary schedule of Mochovce NPP Units 3 and 4 completion, it seems as real that Unit 3 will be completed till 06/2011 and Unit 4 - till 12/2011.

  2. Polish media and public opinion on NPP Mochovce commissioning

    International Nuclear Information System (INIS)

    Latek, Stanislaw

    1999-01-01

    The so called 'Mochovce Problem' was one of the major topics in Polish media in the period from May to July 1998. The nuclear power plant commissioning caused an unexpectedly strong reaction, especially in the newspapers, slightly less so in electronic media. Faced with clearly hostile media reaction to Mochovce NPP, the National Atomic Energy Agency representatives, together with atomic and nuclear experts, undertook to change these attitudes. In numerous interviews, letters to the editors and talks with journalists, they attempted to correct the mistakes, explain the true safety situation in the nuclear power plant, by whom it was constructed, who supervised and tested the systems and so on. The completion of Mochovce NPP construction improved significantly the electricity balance in Slovakia, thus decreasing the pressure for continuing the operation of older Bohunice V1 units beyond their design lifetime. For this reason, as well as in view of striving for improvement in environmental factors beyond Polish southern border, especially after Kyoto/97 decisions on greenhouse gases emissions, the public opinion in Poland should support the Mochovce NPP construction. In 1996 Poland has signed with Slovakia a bilateral inter-governmental agreement on the prompt notification on nuclear accidents and on the cooperation in the nuclear safety and radiological protection matters. On the basis of this agreement the experts from Polish National Atomic Energy Agency are in perpetual contact with Slovakian Nuclear Regulatory Body and in each and every moment can obtain full and comprehensive information on the plant parameters iportant for nuclear safety. The experts explanations, together with the NAEA top management visit to the plant itself, brought some results. The media became less aggressive, and Polish public and authorities - contrary to the Austrians - do not protest loudly against the commissioning of this newest European NPP. Now, in December 1998, the tune of

  3. Preparation of physics commissioning of Mochovce units 3 and 4

    International Nuclear Information System (INIS)

    Sedlacek, M.; Chrapciak, V.

    2010-01-01

    The Project 'Mochovce Units 3 and 4 Completion' started in 2009 and it will be finished in 2013. VUJE, Inc. is one of the five main Project contractors for the Nuclear Island and it is responsible, inter alia, for Mochovce Units 3 and 4 commissioning. The commissioning of Units 3 and 4 includes the stages of Physics Commissioning and Power Commissioning. This paper deals with the preparation of Mochovce Units 3 and 4 Physics Commissioning. In the paper there is presented a preparation of some commissioning documents, e.g. 'Quality Assurance Programme', 'Commissioning Programme', 'Stage Programme for Physics Commissioning', 'Test working programmes', 'Neutron-physics characteristics for Physics and Power Commissioning', etc. The scope of Physics Commissioning is presented by list of tests. For assessment of tests results so-called three-level acceptance criteria will be applied: realization, design and safety criteria. In the paper there are also presented computer codes, which will be used for neutron-physics characteristics calculation and the fuel loading scheme for the reactor core of Mochovce Unit 3. (Authors)

  4. The commission of independent experts has labeled Mochovce as safe

    International Nuclear Information System (INIS)

    Grujbar, V.

    1998-01-01

    An independent commission of experts, appointed by IAEA, said that it did not find any faults concerning the integrity of the pressure vessel of the reactor in first block of the NPP Mochovce. The commission, comprising experts from the U.S.A., Belgium, Finland, Germany and Russia, was given the same documents as the Austrian mission, appointed by the office of the Austrian Chancellor, in May. The Austrian experts then expressed two serious concerns about the security of the first block in Mochovce.The experts of the IAEA agreed that the real condition of Mochovce is a lot better that shown in the technical documentation and they did not find any faults. IAEA was in this case, for the first time, an arbiter solving an international dispute about security of a NPP

  5. Development and implementation of symptom based EOP for Mochovce NPP

    International Nuclear Information System (INIS)

    Zold, T.

    1999-01-01

    In this lecture the history and problems concerning the development and implementation of symptom based emergency operating procedures at the Mochovce NPP are reviewed. In order to increase the safety of nuclear installations and their operation at Mochovce a new programme of Safety measures has been worked out, the core of which are the safety rules administratively labeled as OP-02 introducing the symptom - oriented Emergency operating procedures. Following the selection of partners by the Slovenske Elektrarne power Company a contract was signed with US Westinghouse to work out symptom - based EOPs for the Mochovce power plant to be certified by a letter of approval by Westinghouse in November 1998. Subsequent phases of whole programme for development of EOPs were divided as follows: Phase 1 - Preparation phase; Phase 2 - Emergency operating guideline development and Phase 3 - Emergency operating procedures development and validation

  6. Safety improvement and results of commissioning of Mochovce NPP WWER 440/213

    International Nuclear Information System (INIS)

    Lipar, M.

    1998-01-01

    Mochovce NPP is the last one of this kind and compared to its predecessors, it is characterized by several modifications which contribute to the improvement of the safety level. In addition based on Nuclear Regulatory Authority requirements and based on documents: - IAEA - Safety Issues and their ranking for NPP WWER 440/213, - IAEA - Safety Improvement of Mochovce NPP Project Review Mission, - Riskaudit - Evaluation of the Mochovce NPP Safety Improvements. Additional safety measures have been implemented before commissioning. The consortium EUCOM (FRAMATOME - SIEMENS), SKODA Praha, ENERGOPROJEKT Praha, Russian organizations and VUJE Trnava Nuclear Power Plants research institute were selected for design and implementation of the safety measures. The papers summarized, safety requirements, safety measures implemented, results of commissioning and results of safety analysis report evaluation. (author)

  7. NPP Mochovce units 1 and 2 diagnostic systems

    International Nuclear Information System (INIS)

    Heidenreich, S.

    1997-01-01

    In this paper the diagnostic systems (leak detection monitoring, vibration monitoring, lose parts monitoring, fatigue monitoring) of NPP Mochovce units 1 and 2 are presented. All of the designed diagnostic systems are personal computer based systems

  8. Summary revaluation of energetic start-up of the unit 1 of nuclear power plant Mochovce

    International Nuclear Information System (INIS)

    Sarvaic, I.; Miskolci, M.

    1998-01-01

    The document contents stage revaluation of energetic start-up of the unit 1 of nuclear power plant Mochovce. Test results of the stage of energetic start-up are summarized in the document, valuation of important systems and block devices as well as fulfilling the operation limits and conditions has been performed. On that base conclusions and recommendations for start-up the unit 2 and for commercial operation of the unit 1 are elaborated. The valuation has been elaborated by a scientific management for start-up nuclear power plant Mochovce of nuclear safety of nuclear power facilities. Scientific management for start-up of nuclear power plant Mochovce performed continuous valuation of individual power levels after ending of each individual level and it gave its valuation to energy power level with recommendations and conditions for further start-up process and operation. Scientific management finished its activity at the unit 1 of nuclear power plant Mochovce according to a statute of scientific management for start-up after successful completion of conclusive block run. Scientific management group was founded in February 1998 at nuclear power plant Mochovce. Its members are experts from Slovak, Czech, Russian and French organizations which are participating in power plant completion. Members are listed in a supplement No. 2

  9. Review of accident analyses performed at Mochovce NPP

    International Nuclear Information System (INIS)

    Siko, D.

    2000-01-01

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

  10. Mochovce Nuclear Power Plant. How was it? Starting of the first block by the eyes of participants in the construction operation

    International Nuclear Information System (INIS)

    Blaha, M.; Bucha, T.

    2008-01-01

    This book is published at 10 th anniversary of commissioning of Mochovce NPP. It consists of two parts: Part I. Story completion of the first block Mochovce nuclear power plant. Part II. Interviews with interested politicians and managers of Mochovce NPP.

  11. Pavol Rusko brings up Mochovce again

    International Nuclear Information System (INIS)

    Janoska, J.

    2003-01-01

    Minister of Economy of the Slovak Republic Pavol Rusko would like to see the power plant in Mochovce finished. Press agency SITA quoted his statement that in case of privatisation of Slovenske elektrarne (SE), a.s., Bratislava investor should be searched that would be willing to complete the third and fourth blocks of the nuclear power plant. Last week a tender for sale of a 49-percent stake in SE was repeatedly launched when a privatisation advertisement was published in local and international press. Through a resolution announced last summer the cabinet allowed other companies to participate in the tender (as a reaction interest shown by Czech CEZ). CEZ would be interested in all areas of SE and not only in its conventional part as the other prospects. It is well possible that the number of prospects interested in nuclear energy may increase. Boss of SE, Miroslav Rapsik shares this view and last week announced that there would be probably at least two or three prospects that may be interested in SE as a whole. Amongst them some Russian companies. General Manager and Chairman of Board of Directors, Jaroslav Mil does not wasn't to speculate on under what conditions CEZ may agree with completing of Mochovce. He adds that building any source of nuclear power anywhere in Europe is very difficult without a clear support of wide political spectrum of the specific country. And he needs another assurance: that the cabinet would guarantee that it would eliminate all political pressure from side of the European Union.' In regards to a semi-finished source, according to J. Mil, it made a difference whether this was offered free or with all the fixed costs. 'First we have to see the figures,' he adds. Works on the third and fourth block were stopped in 1992 due to lack of funds. Based on the advise of privatisation advisor the semi-finished blocks were taken out of the privatisation. According to latest analysis the finalization would cost up to 43 billion Sk (1.04 billion

  12. Health state of population in vicinity of the Mochovce nuclear power plant. Epidemiologic study

    International Nuclear Information System (INIS)

    Celko, M.; Durov, M.; Letkovicova, M.; Holy, R.; Sedliak, D.; Zrubec, M.; Kristufek, P.; Machata, M.; Prikazsky, V.; Rehak, R.; Stehlikova, B.; Vladar, M.

    1999-01-01

    Results of epidemiologic study of health state of population in vicinity of the Mochovce nuclear power plant (Slovak Republic) are presented. This report is reported under the headings: (1) Introduction; (2) Basic information about Mochovce NPP; (3) Assessment of population exposition by environmental factors; (4) Basic conceptions and principles of epidemiologic study; (5) Demography and health state of population; (6) Characterisation of databases and data; (7) Description of demographic and health indicators; (8) Calculation of demographic and health indicators in vicinity of the Mochovce NPP and in control areas; (9) Calculated indicators; (10) Statistical methods and evaluation of calculated indicators; (11) Summary and conclusions; (12) References; Appendixes: Literature review of similar epidemiologic studies; Quantities and units in radiation protection; Definitions of indicators calculation - specification of method

  13. Criticality safety analysis of spent fuel storage for NPP Mochovce using MCNP5

    International Nuclear Information System (INIS)

    Farkas, G.; Hascik, J.; Lueley, J.; Vrban, B.; Petriska, M.; Slugen, V.; Urban, P.

    2011-01-01

    The paper presents results of nuclear criticality safety analysis of spent fuel storage for the first and second unit of NPP Mochovce. The spent fuel storage pool (compact and reserve grid) was modeled using the Monte Carlo code MCNP5. Conservative approach was applied and calculation of k eff values was performed for normal and various postulated emergency conditions in order to evaluate the final maximal k eff values. The requirement of current safety regulations to ensure 5% subcriticality was met except one especially conservative case. (Authors)

  14. EDF Contribution to the Mochovce completion and safety upgrading project

    International Nuclear Information System (INIS)

    Norvez, G.

    1997-01-01

    The challenge that SE a.s. took up in April 1996 to start Mochovce units 1 and 2 within a very demanding time frame and in satisfactory conditions is on the way to being wined. EMO managed to put in place an organisation able to ensure the continuity of the design and construction works and to integrate the requirements of modern safety. EDF is proud and happy to contribute to this effort by making available its expertise and experience in building and operating nuclear power plants. The success of Mochovce will not only contribute to the Slovak electricity needs coverage, but will be the first demonstration of a soviet design nuclear power plant brought to international safety standards. (author)

  15. Summary revaluation of cold testing of the first block of nuclear power plant Mochovce; Suhrnne zhodnotenie neaktivneho vyskusania 1. bloku jadrovej elektrarne Mochovce

    Energy Technology Data Exchange (ETDEWEB)

    Miskolci, M; Sarvaic, I [Nuclear Power Plants Research Institute Trnava, Inc., Okruzna 5, 918 64 Trnava (Slovakia)

    1998-04-03

    The document contents summary revaluation of the stage of cold testing of the first unit of nuclear power plant Mochovce. The valuation is processed in individual systems with safety significance. The process and results of system testing and their conclusions for the block readiness for active testing are summarized in the document. The valuation has been elaborated by a scientific management for start-up of nuclear power plant Mochovce as an independent conductor assistance for activation check from the nuclear safety point of view. The valuation of the activation results of systems in the first unit of nuclear power plant was processed as of 15.3.1998 61 figs., 44 tabs., `Translation to english is available from OMEGA INFO, Vysehradska 33, SK-84215 Bratislava, Slovak Republic, E-Mail: kuruc at fns.uniba.sk`

  16. Preparation phase of Mochovce NPP unit 3 and 4 construction completion

    International Nuclear Information System (INIS)

    Cillik, I.; Tvaroska, V.; Liska, P.; Ziman, V.

    2005-01-01

    In this presentation authors deal with preparation phase of Mochovce NPP unit 3 and 4 construction completion. The preparation phase of the Mochovce unit 3 and 4 construction completion gives following main outputs: (a) Detail Safety Concept gives definitive complex safety and technical improvement of MO34, more precise analysis of the total cost of construction completion, a list of potential suppliers and construction completion time schedule; (b) Appendices of Basic Design Documentation and Preliminary SAR serves as basic documentation for UJD SR decision making according to Law No. 541 for start of Realization Phase; (c) The Preparation Phase represents effective tool for start of MO34 construction completion Realization Phase.

  17. External hazards analysis approach to level 1 PSA of Mochovce NPP - Slovakia

    International Nuclear Information System (INIS)

    Stojka, Tibor

    2000-01-01

    Analyses of external events had been first time performed at the design stage of the Mochovce NPP showing sufficiently low contribution of external hazards to core damage frequency. But, based on IAEA document 'Safety problems of WWER-440/213 NPPs and the categorization' (IAEA-EBP-WWER-03, 1996), the need of new reassessment arose due to discrepancy of some origin recommendations in compare with present IAEA ones. Mochovce NPP Nuclear Safety Improvements Program elaborated at the same time included the IAEA recommendations and following improvements were proposed to perform in context of external events. 1. Seismic project and new locality seismic evaluation This safety improvement includes also some 'on site' technical improvements in seismic stability of structures and equipment. 2. Unit specific analyses of extreme meteorologic conditions. This safety improvement focuses on impact of feasible extreme conditions on NPP systems caused by rain, snow and hail storms, frost, winds, low and high temperatures. 3. Analyses of external hazards caused by humans. In this safety improvement were specified: feasible sources of explosions; analyses of hydrogen, gas and propane-calor gas depots; air crash risk. The results of these implemented safety improvements were considered in the PSA study. The External hazards analysis is also part of Level 1 PSA Mochovce NPP performed by PSA Department of VUJE Trnava Inc., Engineering, Design and Research Organization, Slovakia. Some partial analyses are performed in cooperation with following companies DS and S - SAIC, USA and Geophysical Institute Academy of Science, Slovakia Relko, Slovakia. Basic documents are: NUREG/CR-2300 'PRA Procedures Guide - A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants' and IAEA SS No. 50-P-7 'Treatment of External Hazards in PSA for NPPs. The external hazards analysis consists of following parts: 1. Geography and plant locality; 2. Nearby industry; 3. Extreme

  18. Evaluation of power commissioning of the Mochovce Unit 1 demonstration run

    International Nuclear Information System (INIS)

    Sarvaic, I.; Miskolci, M.

    1998-01-01

    The document contains evaluation of the 144 hour demonstration run of the Mochovce Unit 1. In the document, the courses and results of additional tests in this phase of power commissioning are summarized, evaluation of the performance of important systems and equipment of the unit is carried out, as well as of the compliance with Limits and Conditions in the course of the demonstration run. On this basis, conclusions are drawn and recommendations given for the unit to by ready for trial operation. The evaluation was developed by the scientific management of the Mochovce commissioning providing an independent support for the operators for supervising the commissioning tasks from the point of nuclear safety

  19. Slovakia: Mochovce NPP. Project control. Annex 10

    International Nuclear Information System (INIS)

    Bodorik, K.

    1999-01-01

    This annex deals with project control. Mochovce NPP suffered considerable delay primarily due to lack of money. This situation was corrected and construction resumed in 1996. Throughout the 'dormant' period the plant received considerable support from the major contractors, who maintained skeleton staff at site. Significant safety and managerial improvements are being introduced and a strategic plan for the plant has been developed. (author)

  20. Level 1 shutdown and low power operation of Mochovce NPP, Unit 1, Slovakia

    International Nuclear Information System (INIS)

    Halada, P.; Cillik, I.; Stojka, T.; Kuzma, M.; Prochaska, J.; Vrtik, L.

    2004-01-01

    The paper presents general approach, used methods and form of documentation of the results that have been applied within the shutdown and low power PSA (SPSA) study for Mochovce NPP, Unit 1, Slovakia. The SPSA project was realized by VUJE Trnava Inc., Slovakia in 2001-2002 years. The Level 1 SPSA study for Mochovce NPP Unit 1 covers internal events as well as internal (fires, floods and heavy load drop) and external (aircraft crash, extreme meteorological conditions, seismic event and influence of surrounding industry) hazards. Mochovce NPP consists of two operating units equipped with VVER 440/V213 reactors safety upgraded before construction finishing and operation start. 87 safety measures based on VVER 440 operational experience and international mission insights were implemented to enhance its operational and nuclear safety. The SPSA relates to full power PSA (FPSA) as a continuation of the effort to create a harmonized level 1 PSA model for all operational modes of the plant with the goal to use it for further purposes as follows: Real Time Risk Monitor, Maintenance Optimization, Technical Specifications Optimization, Living PSA. (author)

  1. Fire protection at the Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Molnarova, Zuzana; Zeman, Peter

    2009-01-01

    A succinct account is given of current situation in fire prevention at the Mochovce NPP and of past fire events. The fact is stressed that no fire ever occurred at any technological facility of the plant since the startup of the reactor units. Steps required to improve fire safety at a nuclear power plant are highlighted. (orig.)

  2. Experience with drilling and blasting work during construction of Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Mraz, M.; Vojta, A.; Podel, R.

    1986-01-01

    The results are discussed of four years of investigating the technical and economic parameters of drilling and blasting equipment employed on the building site of the Mochovce nuclear power plant. The technical and operating characteristics are given of tested breaking and drilling sets manufactured by various foreign companies. The final choice was based on output, hard currency prices, power demand, operating reliability and number of personnel required for operation. The optimal set consists of two Hausherr HBM 70 drilling systems (holes with a diameter of 130 to 150 mm) and two ROC 601-02 Atlas Copco machines (auxiliary work, breaking foundation holes for nuclear reactors). (J.C.)

  3. Some experience from seismic check-ups of components of Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Masopust, R.

    1987-01-01

    The first Czechoslovak nuclear power plant with the so-called partial anti-seismic design will be built in Mochovce. The evaluation of seismic resistance is prescribed only for equipment and systems which secure the safe reactor shutdown, the withdrawal of residual heat and prevent uncontrolled release of radioactivity into the environment. The following variants were compared in the calculation analysis of the primary loop of the WWER-440 reactor for the Mochovce nuclear power plant: the seismically unsecured loop of a usual design for WWER-440 nuclear power plants, the loop provided with mechanical or hydraulic dampers and the loop provided with viscose shock absorbers. The tests showed that technically most suitable is the use of viscose shock absorbers which do not completely block the movement of the system during the earthquake but absorb it intensively. The viscose shock absorbers are also much cheaper than the dampers. Briefly described is experience with the experimental evaluation of the seismic resistance of components of the Mochovce nuclear power plant. Great difficulty was encountered by the non-existence in Czechoslovakia of a seismic table allowing simultaneous excitation in the vertical and horizontal directions. (Z.M.). 18 refs

  4. Rad-waste treatment

    International Nuclear Information System (INIS)

    1996-01-01

    The spent fuel coming from Slovak NPPs have partially been transported to the former Soviet Union, and a part of it is stored in an interim spent fuel wet storage. In compliance with the worldwide practices, further medium-term possibilities of storing in dry storages are under preparation. Disposal of a spent fuel and other high-level active wastes in a deep geological formation repository is the final solution. At present, there are geological investigations of possible sites in progress in Slovakia. Mochovce repository is a factory for a final disposal of compacted low and intermediate level radioactive wastes coming from the Slovak NPPs. This is a near-surface facility of a construction similar to the one used for disposal of radioactive wastes in France, Spain, Japan, Czech Republic, U.S.A, etc. Quality of the design, construction and functioning of the Mochovce's repository was assessed by an international team of experts within a special IAEA programme (WATRP). Having familiarized with the final report of the IAEA mission, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) issued its position early in 1995, in which NRA SR required additional adjustment of the repository itself. Based on the NRA SR's position, Mochovce NPP invited experts from a number of institutions in September 1995 to discuss the NRA SR's requirements. Following was recommended by the experts: (1) to perform a complementary engineering-geological investigation on the site, (2) to use geophysical methods to verify existence of geological faults. In the next part a radioactive wastes that were treated at radioactive waste treatment lines in 1995 are listed. In 1995, the Chief Inspector of NRA SR issued an instruction that radioactive waste department should start inspections of radioactive waste treatment right in hospitals, research institutes and industries. Therefore, a total of 14 such workplaces were incorporated into a plan of inspections in 1995

  5. Commissioning of Mochovce 1 - Important achievement of the world's nuclear industry

    International Nuclear Information System (INIS)

    Holy, Robert; Petrech, Rastislav

    1999-01-01

    The nuclear power industry has been recently perceived by the general public as a specific industrial branch stretching its activities far beyond the conventional industrial standard. Similarly, the stage of testing and commissioning of a nuclear power plant is perceived as a specific stage in the plant life-cycle. This is a complicated process not only in technical terms, but in the context of nowadays, it is also one of the key periods in terms of public relations and public acceptance. The stage of commissioning unit 1 of Mochovce Nuclear Power Plant evoked a real communication media war between defenders and opponents of the nuclear industry started early in 1998 in Slovakia, as well as in other, mostly neighbouring countries. It should be noted, however, that the Mochovce plant has never been a technical problem as confirmed a number of international regulatory missions and audits, even though its construction was stopped in early 90's. The result of the war between the opponents and 'nuclear experts' was more or less clear to a thinking human being - a compromise could have been the only result. The compromise which is in fact a victory of the side of technical development, and loss of those lobbying for a nuclear-reactor-free central Europe. This article brings a review of events that accompanied commissioning activities of Mochovce NPP unit I which were important in terms of public relations

  6. Completion of Mochovce 1 and 2 nuclear power plant project

    International Nuclear Information System (INIS)

    Valach, J.

    2000-01-01

    Commissioning of the Mochovce Nuclear Power Plant unit 2 fully completed the Mochovce unit 1 and 2 project. The power plant construction passed through a complicated evolution since early 80's. The genesis started with the change of the plant location due to a seismic resistance requirement raised by the former Czechoslovak Atomic Energy Commission, change of the design and contractor of the Instrumentation and Control system in early 90's, halt of construction in 1993 till 1996 due to a lack of funding, as well as a series of international reviews of safety aspects. All the obstacles had been overcome in the end, and completion works were re-started in 1996. Looking back to the unit 1 and 2 completion project, I would like to highlight some aspects of the project, particularly the level of safety, technical and organisational conditions, and terms of funding. The most important argument for completion of the plant was that VVER 440/213 reactor units were distinguished with very high level of passive safety, even overcoming Western-type PWR's in some aspects. The replacement of the original I and C system was another important contribution to the initial level of safety. International safety reviews performed at Mochovce NPP between 1990 and 1995 (Siemens, EdF, IAEA, RlSKAUDIT) confirmed the high level of safety of VVER 440/213 reactors, however, pointed out at some safety issues which had not been dealt with in the design. Those included e.g. the 'external risks', primary-to-secondary leaks, qualification of pressurizer safety valves, and others. It is necessary to stress that the Safety Improvement Programme defined for Mochovce NPP to comply with international standards did not become the most important part of the completion project due to external pressures, but based on natural requirements on nuclear power plant safety level generally accepted in 90's. The good example could be the seismic resistance of the plant which, though designed as seismic resistant

  7. Radwaste treatment and disposal

    International Nuclear Information System (INIS)

    Ehn, L.; Breza, M.; Pekar, A.

    2000-01-01

    In this lecture is given the basic information, that is concerning on the RAW treatment and long term disposal of the treated RAW in repository at Mochovce. Then here is given the basic technical and technological information, that is concerning bituminization, plant, the vitrification unit, center for the RAW-treatment (BSC) and repository at Mochovce. (authors)

  8. Role of the team of scientific and technical commissioning support (TSTCS) during Mochovce NPP unit 3 and 4 commissioning

    International Nuclear Information System (INIS)

    Hermansky, J.; Prachar, M.; Sedlacek, M.; Petenyi, V.

    2011-01-01

    The Team of Scientific and Technical Commissioning Support (TSTCS) shall provide an independent support for the Mochovce NPP 3 and 4 Commissioning Department during Mochovce Units 3 and 4 commissioning. This independent support will be in line with the Mochovce NPP 3 and 4 Directive 'Non-active tests and commissioning' and it will be carried out in form of professional and expert works focusing on supervision of fulfilment of requirements for nuclear safety observance. The TSTCS duty to provide for such services during NPP commissioning is specified by Slovak Regulatory Body legislation. The independent TSTCS will supervise; - fulfilment of requirements for nuclear safety during preparation and implementation of commissioning tests; -scientific and technical level of commissioning programmes, and reflection on nuclear safety requirements in commissioning programmes,- commissioning process and test results. Main standpoints of the Team activities for individual unit commissioning stages will be; - assesment of the selected programs of functional tests in installations having an impact on nuclear safety and evaluation of the results of these tests; - assesment of the programs of physics and power commissioning, - assesment of the unit preparedness before fuel loading start; - assesment of the unit preparedness for performing initial criticality and low power commissioning and power commissioning stages; - evaluation of the results of physics and power commissioning stages and sub-stages; - final evaluation of the results from implementing the physics and power commissioning stages. The paper also presents a short description of the Team scope activities, the Team organisation, and a procedure for issuing of standpoints to individual unit commissioning stages. (Authors)

  9. Mochovce NPP safety improvement and completion

    International Nuclear Information System (INIS)

    1997-01-01

    6th Nuclear society information meeting dealt with the completion of the Mochovce NPP with regard to implementation of safety measures. It was aimed to next problems: I. 'Survey' presentation on the situation of the nuclear power industry in partner countries; II. Basic technical presentations; III. Presentations of operators of the other VVER 440/213 NPPs on their activities in the field of safety improvement in relation to IAEA recommendations; IV. Technical solutions of safety improvements ranked with IAEA degree 3 (Report SC 108 VVER); V: Technical solutions of selected Safety Measures ranked with IAEA degree 2 and 1 (Report SC 108 VVER)

  10. Press travel to the Mochovce power plant in Slovakia

    International Nuclear Information System (INIS)

    1998-07-01

    This press dossier gives, first, a general presentation of the Mochovce power plant of the republic of Slovakia (history, technical characteristics, safety aspects, technical particularities of VVER 440/213 reactors (safety analysis, recent improvements), financing of the modernization project). Then, the activities of the Framatome group in central and eastern Europe are presented (partnerships, cooperation agreements and contracts). (J.S.)

  11. Summary revaluation of cold testing of the first block of nuclear power plant Mochovce

    International Nuclear Information System (INIS)

    Miskolci, M.; Sarvaic, I.

    1998-01-01

    The document contents summary revaluation of the stage of cold testing of the first unit of nuclear power plant Mochovce. The valuation is processed in individual systems with safety significance. The process and results of system testing and their conclusions for the block readiness for active testing are summarized in the document. The valuation has been elaborated by a scientific management for start-up of nuclear power plant Mochovce as an independent conductor assistance for activation check from the nuclear safety point of view. The valuation of the activation results of systems in the first unit of nuclear power plant was processed as of 15.3.1998

  12. Status of the seismic upgrading programme at Mochovce NPP

    International Nuclear Information System (INIS)

    Zajicek, T.; Dolnik, R.; Stevko, M.

    2001-01-01

    The paper provides an overview of the seismic characterisation of the Mochovce site in Slovakia. Particularly, emphasis is given to differences between the original siting and design procedures and the re-evaluation approach, much more based on the data from the micro-earthquake monitoring system installed at the site. Details are also provided for the seismic monitoring of the buildings, as confirmation of the design assumptions. (author)

  13. Slovenske elektrarne, a.s., Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    1998-01-01

    In this booklet the uranium atom nucleus fission as well as electricity generation in a nuclear power plant (primary circuit, reactor, reactor pressure vessel, fuel assembly, control rod and reactor power control) are explained. Scheme of electricity generation in nuclear power plant and Cross-section of Mochovce Nuclear Power Plant unit are included. In next part a reactor scram, refuelling of fuel, instrumentation and control system as well as principles of nuclear safety and safety improvements are are described

  14. Health state of population in the locality of the Mochovce nuclear power plant after four years of operation

    International Nuclear Information System (INIS)

    Letkovicova, M.; Letkovicova, H.; Letkovic, M.

    2002-01-01

    The Mochovce NPP was put into the operation in 1998. Authors monitor the health state of the population in its vicinity since 1993. The authors recorded this health state also in before-operational safety report of Mochovce NPP. The authors show in the presentation the evaluation of nine years, five before putting of Mochovce NPP into the operation and four during its operation. The aim of the authors is to evaluate the state of chosen health indicators in individual villages in whole monitored region and to try to found out the differences between of their size before and after putting the Mochovce NPP into the operation. Authors used the methods of so-called population epidemiology, where they evaluate the health risks by the system of multidimensional mathematical-statistical methods, by using of the theory of fuzzy sets. The Mochovce region belongs for the long period to the regions with very unfavourable health state. Its very general comparison with one year all Slovak values of the relevant indicators in 2000 are following: more newborn on thousand inhabitants (in 12 per cent) (consequence of wholly older population), higher general mortality of population (in 11 per cent), higher premature mortality of population (in 17 per cent), higher mortality from selected causes, thus malignant tumours of digestive tract (in 20 per cent), higher mortality from malignant tumours of lungs (in 25 per cent), higher mortality from malignant tumours of leukaemia (in 25 per cent). However the authors found out very positive findings in the evaluation of the trends: in the case of fifteen most serious health indicators in the vicinity of Mochovce NPP authors state also mathematically visible influence on the surroundings, which is registerable only in positive meaning. There are created the demonstrable clusters of the villages with low general, also premature women mortality. This locality was far off the industrial and cultural centres, there were always historically higher

  15. Current situation of the project of 3. and 4. block of nuclear power plant Mochovce

    International Nuclear Information System (INIS)

    Suchy, L.

    2006-01-01

    The contribution shows the basic information about the crucial milestone of 3. building and the current situation of the project of 3. and 4. block of the nuclear power plant Mochovce. Contribution also shows what activities were realized and what material in area of designation of the technical and safety standard of the project was elaborated in the past, the main activities planned for 2006 have been described, support for Feasibility Study elaborated by ENEL and description of the integrated management system. The basic thesis crucial for the next steps on the project of 3. and 4. block of Nuclear Power Plant Mochovce is presented in the conclusion

  16. Theoretical parameter histories of dynamic tests during power commissioning of Mochovce units power level up to 100 % Nnom

    International Nuclear Information System (INIS)

    Jagrik, J.; Mraz, M.; Rapant, M.; Stefanovic, P.; Kotasek, J.; Gieci, A.; Macko, J.; Mosny, J.

    1998-01-01

    Theoretical histories of selected parameters for dynamic tests carried out in the course of power commissioning of the Mochovce Unit 1 at the power level 100% N nom are shown in the report. The expected histories given were developed based on calculations performed by means of simulator in Nuclear Power Plants Research Institute Trnava, Inc., simulator in EGU Praha and simulator at the Mochovce plant, as well as based on similar tests at both Bohunice and Dukovany plants

  17. Radiation exposure of the population from 222Rn and other natural radionuclides around Mochovce nuclear power plant, Slovakia

    International Nuclear Information System (INIS)

    Bulko, Martin; Holy, Karol; Mullerova, Monika; Bohm, Radoslav; Pohronska, Zofia; Hola, Olga

    2017-01-01

    In this article, the effective dose to the population from natural sources of ionizing radiation in the vicinity of Mochovce nuclear power plant in Slovakia is presented. All major contributions to the effective dose were taken into account, including the contributions from gamma radiation of soil and rocks, cosmic radiation, and indoor and outdoor radon and thoron. On the basis of recent indoor radon measurements in Slovak cities and publicly available data about radon concentration in the soil air, a roughly linear relationship was found between these variables. Consequently, the annual effective dose from indoor radon and thoron was conservatively estimated. For the area of interest, a map of conservatively estimated potential effective doses was created. For the villages in the vicinity of Mochovce, the conservatively estimated effective dose to the population from natural sources ranged from 5.4 to 14.6 mSv, which is four orders of magnitude higher than the contribution of radioactive discharges from Mochovce nuclear power plant. (authors)

  18. Transport structures and water reservoir for the Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Farkas, J.; Klacansky, T.

    1986-01-01

    The projects are described which were implemented by Doprastav Bratislava within the preparation of the site for the Mochovce nuclear power plant. This includes a railway siding in a length of 11.2 kilometres which includes a railway bridge, two other bridges and the reconstruction of the Kalna nad Vahom railway terminal. Also reconstructed or newly built were road communications in a total length of 23.3 km. The said project included the construction of a road flyover over the railway track and the construction of five other smaller bridges. In order to provide the utility water supply to the Mochovce nuclear power plant, a large reservoir is being built at Velke Kozmalovce. The reservoir will have a total capacity of 2.6 mill. m 3 of water, of this the effective capacity will be 2.1 mill. m 3 on a flooded area of some 90 ha. Part of the reservoir will be a small hydro-power plant, the reservoir will also be used for irrigation on the fields of the neighbouring farms. (Z.M.)

  19. Analysis of the methodical component of core power density field calculation error on the basis of Mochovce-1 commissioning tests

    International Nuclear Information System (INIS)

    Brik, A.

    2009-01-01

    In the first decade of June 2008, during the power commissioning of the reactor at the Mochovce NPP unit 1, the experiment with reducing the thermal power of core almost to the balance-of-plant (BOP) needs was performed. After the reactor has operated for seven hours at low power (about 200 220 MW (thermal)), its power was increased (at a rate of about 0.25% of N nom /min) to the initial level, close to 107% (1471 MW). During the experiment, core parameters, which were subsequently used for comparing the measured data with the results of experiment simulation calculations, were recorded in the reactor in-core monitoring system database. Calculated and measured levels of critical concentrations of boric acid were compared, along with power density distributions by fuel elements and assemblies obtained both by the KRUIZ in-core monitoring system and on the basis of calculations simulating reactor operation in accordance with the given core power variation schedule. The final stage consisted of assessing the methodical component of power density micro- and macro-fields calculation error in the core of Mochovce-1 reactor operating with varying load. (author)

  20. Analysis of the methodical component of core power density field calculation error on the basis of Mochovce-1 commissioning tests

    International Nuclear Information System (INIS)

    Brik, A.

    2009-01-01

    In the first decade of June 2008, during the power commissioning of the reactor at Mochovce NPP unit 1, the experiment with reducing the thermal power of core almost to the balance-of-plant needs was performed. After the reactor has operated for seven hours at low power (about 200 220 MW (thermal)), its power was increased (at a rate of about 0.25% of N nom /min) to the initial level, close to 107% (1471 MW). During the experiment, core parameters, which were subsequently used for comparing the measured data with the results of experiment simulation calculations, were recorded in the reactor in-core monitoring system's database. Calculated and measured levels of critical concentrations of boric acid were compared, along with power density distributions by fuel elements and assemblies obtained both by the KRUIZ in-core monitoring system and on the basis of calculations simulating reactor operation in accordance with the given core power variation schedule. The final stage consisted of assessing the methodical component of power density micro- and macro-fields' calculation error in the core of Mochovce-1 reactor operating with varying load. (Authors)

  1. Human reliability analysis approach to level 1 PSA - shutdown and low power operation of Mochovce NPP, Unit 1, Slovakia

    International Nuclear Information System (INIS)

    Stojka, Tibor; Holy, Jaroslav

    2003-01-01

    The paper presents general approach, used methods and form of documentation of the results as have been applied within the Human Reliability Analysis (HRA) task of the shutdown and low power PSA (SPSA) study for Mochovce nuclear power plant, Unit 1, Slovakia. The paper describes main goals of the HRA task within the SPSA project, applied methods and data sources. Basic steps of the HRA task and human errors (HE) classification are also specified in its first part. The main part of the paper deals with pre-initiator human errors, human-induced initiators and response to initiator human errors. Since the expert judgment method (SLIM) was used for the last type of human errors probability assessment, also related activities are described including preparation works (performance shaping factors (PSFs) selection, development of PSF classification tables, preparation of aid tools for interview with plant experts), qualitative analysis (sources of information and basic steps) and quantitative analysis itself (human errors classification for final quantification including criteria used for the classification, description of structure of the spreadsheet used for quantification and treatment with dependencies). The last part of the paper describes form of documentation of the final results and provides some findings. (author)

  2. Evaluation of power commissioning of the Mochovce Unit 1 power level up to 100 % Nnom

    International Nuclear Information System (INIS)

    Sarvaic, I.; Mickolci, M.

    1998-01-01

    The document contains an evaluation of the power phase of power commissioning of the Mochovce Unit 1 in the phase up to the power level of 100 % N nom .In the document, the courses and results of tests in this phase of power commissioning are summarized, evaluation of the performance of important systems and equipment of the unit is carried out, and the compliance with Limits and Conditions in the course of the phase is assessed. On this basis, conclusions are drawn and recommendations for the unit to be ready for subsequent phases of the power commissioning. The evaluation was developed by the scientific management of the Mochovce commissioning providing an independent support for the operators for supervising the commissioning tasks from the point of nuclear safety

  3. Mochovce NPP experience in the certification and the use of full scope simulator

    International Nuclear Information System (INIS)

    Krenicky, L.

    1999-01-01

    The paper presents some of the Mochovce NPP experience in the full-scope simulator certification process, simulator training programs development, implementation and evaluation, the use of simulator in the all-plant emergency exercises as well as the experience in validation of plant operational procedures.(author)

  4. Natural and artificial radioactivity in the area of the Mochovce regional radioactive waste store

    International Nuclear Information System (INIS)

    Bezak, J.; Daniel, J.; Moravek, J.

    2000-01-01

    The results of monitoring of natural and artificial radioactivity in the area of the Mochovce regional radioactive waste store before commission are presented. The concentrations of uranium, thorium, potassium, and cesium, as well as radon volume activity were measured

  5. Start. Slovak power stations, Nuclear Power Plants Mochovce (Annual report 1998)

    International Nuclear Information System (INIS)

    1999-01-01

    A brief account of activities carried out by the Nuclear power plants Mochovce in 1998 is presented. These activities are reported under the headings: (1) Director's foreword; (2) Power plant management; (3) Highlights of 1998; (4) Quality system; (5) Electricity and heat generation; Maintenance; Capital construction; (6) Radiation safety; Environmental impacts of operations; (7) List of balances; Human resources; (8) International co-operation; Public relations

  6. Slovak power stations, Nuclear Power Plants Mochovce (Annual report 1997)

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Mochovce in 1997 is presented. These activities are reported under the headings: (1) Director's foreword; (2) Power plant management; (3) Highlights of 1997; (4) Capital construction; (5) Nuclear safety; (6) Radiation safety; (7) Work safety and health protection at work; (9) Fire protection; (10) Units upgrading - safety measures; (11) Maintenance; (12) Operation; (13) Environmental impacts of operations; (14) List of balances; (15) Human sources; (16) International co-operation; (17) Public relations

  7. Study of environmental impact assessment for Mochovce NPP Units 3 and 4. Executive summary. September 2007

    International Nuclear Information System (INIS)

    Anon

    2007-09-01

    SE/ENEL, on a voluntary basis, has prepared new EIA Study for the completion of Units 3 and 4 of Mochovce Nuclear Power Plant (MO34 NPP) according to International current practices and European Directives. The results of the analysis, according to SE/ENEL Environment and Corporate Social Responsibility policies, will be provided to local Communities and Public Authorities. The Environmental Impact Assessment is performed: - in compliance with appendix 11 of Slovak Act. No. 24/2006 'On the assessment of the effects on the environment and on the modification and enlargement of some laws'; - meeting the requirements of the Exhibit II 'Illustrative list of potential social and environmental issues to be addressed in the Social and Environmental Assessment documentation' as reported in the document 'Equator Principles' of 2006 July developed by the International Finance Corporation (IFC). The area of Mochovce NPP is situated in Central Europe in the south-western region of the Slovak Republic (SR) at the western border of the Levice district. The area lies in the south-western part of the Kozmalovske hills mainly in the Hron highlands. From the point of view of the terrestrial and administrative organization of the SR, Mochovce NPP is situated in the eastern part of the Nitra region, in the north-western part of the Levice district, close to the border with the Nitra and Zlate Moravce districts. Mochovce NPP is approx. 12 km from the district capital Levice, which is the largest town within a 20 km distance from the power plant. Initial site preparation began in August 1983. In April 1998 the first fuel was loaded into Unit 1 of Mochovce NPP. The operation started in August 1998. Unit 2 started operation in January 2000. The original Construction Permit No. Vyst. 2010/86 for MO 34 was issued by the District National Committee in Levice on the basis of the Land Planning Decisions on 12 November 1986. This Permit has been renewed firstly on 5 May 1997 by letter of the

  8. Fiddle at financing of Mochovce NPP

    International Nuclear Information System (INIS)

    Beer, G.

    2003-01-01

    Slovak police found out and documented racket in financing of third and fourth block of Mochovce NPP. Damage should be 144 millions Slovak crowns. Investigator consequently accused twenty-three Slovaks from foundation, trump up and supporting of criminal group and deception. Two persons are suggested to be taken to custody. Skoda Praha, which was general supplier of construction for 1,5 billions Slovak crowns, in 2001 allowed to create a connection to let the finances between Slovenske elektrarne, a.s., Bratislava as investor and Skoda as subcontractor to be paid through three mediator companies. Companies got authorization to balance the relationship among all interested subjects. Confused network of 118 treaties was created. They invoiced reward from money current based on these treaties. Reward represented up to 70 per cent of transferred resources in some cases. According to Minister of Domestic Affairs Vladimir Palko it will be necessary to find out where is actually the money. For the time being nobody from NPP is among accused. (Author)

  9. Feasibility study for NPP Mochovce Units 3 and 4 completion

    International Nuclear Information System (INIS)

    Tomik, L.; Chakraborty, S.; Hoffelner, W.; Stoian, A.

    2004-01-01

    The system dynamic approach presented in this study by modelling the behaviour of Slovak market on the basis of system dynamic model (Forrester model), enables real mix in the extend of 12 years and helps understanding of the market limits. In addition this tool can be used for sensitivity calculations depending on many parameters to develop possible trends in the economic development of the Slovak Republic. If both nuclear power options are maintained then it becomes obvious that electric excess energy is produced and could be exported. This export option remains for the situation that a strong growth of the gross national product is assumed without any increase in energy efficiency. Between these extremes is the scenario that Bohunice 1, 2 off is balanced by Mochovce 3, 4 on and increasing demand this will lead to more moderate but still not negligible potential of CO 2 increase. Switching off Bohunice 1, 2 and not switching on Mochovce 3, 4 leads to energy need which must be counterbalanced either by investments in other power plants or by import energy. As far as domestic production is concerned even assuming 50 % CHP production leads to partly remarkable additional CO 2 -production which might infringe on a long term basis with the Kyoto goals. Assuming additional CO 2 -emissions from increasing traffic real problems can be expected in such a case. To maintain national nuclear capabilities in Slovakia is very important for today and for future of nuclear energy option in enlarged European Union. (authors)

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  12. 'HSE protection through safe work'. Mochovce NPP is the holder of ISO 14001:2004 and CSN OHSAS 18001 certificates

    International Nuclear Information System (INIS)

    Molnarova, Zuzana; Torda, Anton

    2009-01-01

    The article provides information on the safety of the Mochovce NPP related to occupational health and safety and environmental protection. The facility has earned EN ISO 140001 and OHSAS 18001 certificates. (orig.)

  13. Participation of Skoda Praha a.s. in completion of NPP Mochovce

    International Nuclear Information System (INIS)

    Poukar, F.

    1997-01-01

    The history of the construction of the Mochovce nuclear power plant is briefly described. In 1995, after obtaining promises of loans from Czech banks the Slovak government decided that the completion of the mechanical and electrical parts of units 1 and 2 would be placed with Skoda Praha in the position of general supplier; Skoda together with Siemens and Framatome would also be charged with implementing the safety measures necessary to reach European standards. Evaluation of safety studies and risk audits, and elaboration of safety measures are now under way. (M.D.)

  14. Implementation of computer codes for performance assessment of the Republic repository of LLW/ILW Mochovce

    International Nuclear Information System (INIS)

    Hanusik, V.; Kopcani, I.; Gedeon, M.

    2000-01-01

    This paper describes selection and adaptation of computer codes required to assess the effects of radionuclide release from Mochovce Radioactive Waste Disposal Facility. The paper also demonstrates how these codes can be integrated into performance assessment methodology. The considered codes include DUST-MS for source term release, MODFLOW for ground-water flow and BS for transport through biosphere and dose assessment. (author)

  15. Completion of the VVER 440/213 NPP Mochovce incorporation enhanced safety features

    International Nuclear Information System (INIS)

    Charbonneau, S.; Eckert, G.

    1996-01-01

    The cooperation between the western countries and the countries of ex-eastern block in the field of nuclear safety is recent and still limited. The main reasons for this situation are limited or non existent capabilities of these countries for financing as well as non acceptable legal conditions concerning the third party nuclear liability in this part of Europe. Nevertheless, Framatome and Siemens associated in the consortium named EUCOM, have signed in April 1996 the contract of about 100 million US dollars with Slovak electricity company (SLOVENSKE ELEKTRARNE-SE) for upgrading the Units 1 and 2 of Mochovce Nuclear Power Plant according to the western safety standards. This is the first important project involving west-european companies in the modernisation of Russian type of pressurized water reactor (VVER 440/213). The consortium will cooperate with other partners involved in the project: Slovak, Czech and Russian. The financing of the project will be provided mainly form Slovak and Czech sources. The safety upgrading will be financed through French and German buyer credits. French company Electricite de France (EDF) will be the consultant for SE. The safety upgrading measures have been elaborated taking into account the recommendation of Vienna International Atomic Energy Agency (IAEA) and the evaluation of the safety realised by RISKAUDIT, the common organization of German and French safety authorities (GSR and IPSN). Hence all guaranties have been taken to fulfil the western safety criteria for Nuclear Power Plant Mochovce. (author)

  16. Mochovce power plant units 3 and 4

    International Nuclear Information System (INIS)

    Cuba, J.

    2003-01-01

    The report gives the basic technical data and history of the construction of the units 3 and 4 of the Mochovce NPP.The current status of the units completion according to the original plan is: civil part - 70%; mechanical part - 30%; electric and IC equipment - 1%. Strategic plan for the preservation of the units 3 and 4 has been developed in accordance with TECDOC-1110. In implementation of the plan preservation activities are performed for the components located and built-in on the site and in storehouses. Preservation with dryers and protective coatings is applied. The factors of possible component degradation are determined. Ventilation components are used for improving the climate conditions in the primary part of the reactor building. Temperature and humidity measurements are done and temperature control is set. Special pre-service inspections beyond the basic scope of preservation and protection works are conducted of steam generator and reactor pressure vessel. The implementation of the design data protection and enhancement is discussed. The feasibility study of units 3 and 4 completion funding has been developed in 2002

  17. Ejected control rod and rods drop measurements during Mochovce startup physical tests

    International Nuclear Information System (INIS)

    Minarcin, Miroslav; Elko, Marek

    1998-01-01

    Paper deals with measurements of asymmetric reactivity insertion into the reactor core that were carried out during physical startup tests of Mochovce Unit 1 in June 1998. Control rods worth measurements with one and two rods s tucked in upper limit and worth measurement of one control rod from group 6 'ejected' from the reactor core are discussed. During the experiments neutron flux was measured by four ionisation chambers (three of them were placed symmetrically around the reactor core). Results of measurements and influence of asymmetric reactivity influence on ionisation chambers response are presented in the paper. (Authors)

  18. Jevgenij V. Doc: We do not want to build a monument at Mochovce

    International Nuclear Information System (INIS)

    Janoska, J.

    2004-01-01

    In this paper the interview with the General Manager of Inter RAO JES - Jevgenij V. Doc is published. Inter RAO JES applies for the privatisation of Slovenske elektrarne (Slovak Electric - SE). According to the General Manager of Inter RAO JES, the company does not need a foreign partner to provide financial support after the privatisation of SE, but rather it requires a political support. Plans about Bohunice NPP and of completion of the Mochovce NPP as well as of privatisation of the SE by the Inter RAO JES are presented

  19. Seismic re-evaluation of Mochovce nuclear power plant. Seismic reevaluation of civil structures

    International Nuclear Information System (INIS)

    Podrouzek, P.

    1997-01-01

    In this contribution, an overview of seismic design procedures used for reassessment of seismic safety of civil structures at the Mochovce NPP in Slovak Republic presented. As an introduction, the objectives, history, and current status of seismic design of the NPP have been explained. General philosophy of design methods, seismic classification of buildings, seismic data, calculation methods, assumptions on structural behavior under seismic loading and reliability assessment were described in detail in the subsequent section. Examples of calculation models used for dynamic calculations of seismic response are given in the last section. (author)

  20. Further experience in simulation of rod drop experiments in the Loviisa and Mochovce reactors

    International Nuclear Information System (INIS)

    Siltanen, P.; Kaloinen, E.; Tanskanen, A.; Mattila, R.

    2001-01-01

    Simulations of reactor scram experiments using the 3-dimensional kinetics code HEXTRAN have been updated for the initial cores of Loviisa-1 and 2 Mochovce-1 and have been extended to burned cores of Loviisa-1. In these simulations, the entire experiment is simulated dynamically, including the behaviour of the core, the signal of the ionization chamber, and the inverse point kinetics of the reactivity meter. The predicted output of the reactivity meter is compared with the output observed during the experiment (Authors)

  1. Eco information 4. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within April 2014

    International Nuclear Information System (INIS)

    2014-05-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within February 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 1.011 GBq of tritium (1.011 for the period January - April 2014 (0.36% of AL)) and summary of gamma-radionuclides 0.479 GBq (0.944 GBq for the period January - April 2014 (24.21% of AL)). The radioactive effluents into hydrosphere within April 2014 for FS KRAO were: 62 kBq of 90 Sr (62 kBq for the period January - March 2014 (0.003% of AL)), 0.003 kBq of summary alpha (0.003% of AL) and 1847 kBq of 14 C (1847 kBq for the period January - March 2014). The radioactive effluents into hydrosphere within April 2014 for RU RAO were: 0.568 MBq of tritium (4.544 MBq for the period January - April 2014 (0.024% of AL)); 0.004 MBq of 137 Cs (0.033 MBq for the period January - April 2014 (0.145% of AL)); 0.119 MBq of 90 Sr - the value of the quarterly (0.119 MBq for the period January - March 2014 (0.049% of AL)); 0.008 MBq of 60 Co (0.031 MBq for the period January - April 2014 (0.138% of AL)); 0.005 MBq of 239 Pu (0.005 MBq for the period January - March (0.892% of AL)). Volume of liquid effluents in April 2014 was 227 m 3 (186 m 3 for the period January - April 2014). The radioactive effluents into atmosphere within April 2014 for FS KRAO were: 0.0005 MBq of gamma radionuclides (0.0018 MBq for the period January - April 2014, that is 0.0023% of annually limit (AL)); 0.022 MBq of alpha radionuclides (0.022 MBq for the period January - March (0.0022% of AL)), and 0.149 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.149 MBq for the period January - March 2014 (0.0075% of AL)).

  2. Eco information 2. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within February 2014

    International Nuclear Information System (INIS)

    2014-03-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within February 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.0000 GBq of tritium (9.0000 for the period January - February 2014 (0.00% of AL)) and summary of gamma-radionuclides 0.0000 GBq (0.0000 GBq for the period January - February 2014 (0.00% of AL)). The radioactive effluents into hydrosphere within February 2014 for FS KRAO were: 0.000 kBq of 90 Sr (0.000% of AL)), 0.000 kBq of summary alpha (0.000% of AL) and 0.000 kBq of 14 C (0.000% of AL). The radioactive effluents into hydrosphere within February 2014 for RU RAO were: 2.272 MBq of tritium (3.976 MBq for the period January - February 2014 (0.021% of AL)); 0.017 MBq of 137 Cs (0.029 MBq for the period January - February 2014 (0.127% of AL)); 0.00 MBq of 90 Sr - the value of the quarterly (0.00 MBq for the period January - March 2013 (0.000% of AL)); 0.014 MBq of 60 Co (0.023 MBq for the period January - February 2014 (0.103% of AL)); 0.000 of 239 Pu (0.000 MBq for the period January - March 2014 (0.000% of AL)). Volume of liquid effluents in February 2014 was 908 m 3 (1589 m 3 for the period January - February 2014). The radioactive effluents into atmosphere within February 2014 for FS KRAO were: 0.0002 MBq of gamma radionuclides (0.0007 MBq for the period January - February 2014, that is 0.0009% of annually limit (AL)); 0.000 MBq of alpha radionuclides (0.000 MBq for the period January - March 2014 (0.000% of AL)), and 0.000 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.000 MBq for the period January - March 2014 (0.000% of AL)).

  3. Eco information 3. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within March 2014

    International Nuclear Information System (INIS)

    2014-04-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within March 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.056 GBq of tritium (0.056 for the period January - March 2014 (0.2% of AL)) and summary of gamma-radionuclides 0.465 GBq (0.465 GBq for the period January - March 2014 (11.92% of AL)). The radioactive effluents into hydrosphere within January - March 2014 for FS KRAO were: 0.000 kBq of 90 Sr (0.000% of AL)), 0.000 kBq of summary alpha (0.000% of AL) and 0.000 kBq of 14 C (0.000% of AL). The radioactive effluents into hydrosphere within March 2014 for RU RAO were: 0.000 MBq of tritium (3.976 MBq for the period January - March 2014 (0.021% of AL)); 0.000 MBq of 137 Cs (0.029 MBq for the period January - March 2014 (0.127% of AL)); 0.00 MBq of 90 Sr - the value of the quarterly (0.00 MBq for the period January - March 2014 (0.000% of AL)); 0.000 MBq of 60 Co (0.023 MBq for the period January - March 2014 (0.103% of AL)); 0.000 MBq of 239 Pu (0.000 MBq for the period January - March 2014 (0.000% of AL)). Volume of liquid effluents in March 2014 was 0 m 3 (1589 m 3 for the period January - March 2014). The radioactive effluents into atmosphere within March 2014 for FS KRAO were: 0.0006 MBq of gamma radionuclides (0.0013 MBq for the period January - March 2014, that is 0.0016% of annually limit (AL)); 0.00 MBq of alpha radionuclides (0.000 MBq for the period January - March 2014 (0.000% of AL)), and 0.000 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.000 MBq for the period January - March 2014 (0.000% of AL)).

  4. Eco information 1. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within January 2014

    International Nuclear Information System (INIS)

    2014-02-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within January 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.0000 GBq of tritium (0.0000 GBq for the period January - January 2014 (0.000% of AL)) and summary of gamma-radionuclides 0.0000 GBq (0.0000 GBq for the period January - January 2014 (0.000% of AL)). The radioactive effluents into hydrosphere within January 2014 for FS KRAO were: 1,704 kBq of 90 Sr (0.009% of AL)), 0.012 kBq of summary alpha (0.053% of AL) and 0.000 kBq of 14 C (0.000% of AL). The radioactive effluents into hydrosphere within January 2014 for RU RAO were: 0.009 MBq of tritium (1.704 MBq for the period January - January 2014 (1.704% of AL)); 0.012 MBq of 137 Cs (0.012 MBq for the period January - January 2014 (0.053% of AL)); 0.000 MBq of 90 Sr - the value of the quarterly (0.000 MBq for the period January - January 2014 (0.000% of AL)); 0.009 MBq of 60 Co (0.009 MBq for the period January - January 2014 (0.04% of AL)); 0.000 MBq of 239 Pu (0.000 MBq for the period January - January 2014 (0.000% of AL)). Volume of liquid effluents in January 2014 was 681 m 3 (4681m 3 for the period January - January 2014). The radioactive effluents into atmosphere within January 2014 for FS KRAO were: 0.0005 MBq of gamma radionuclides (0.0005 MBq for the period January - January 2014, that is 0.0006% of annually limit (AL)); 0.000 MBq of alpha radionuclides (0.000 MBq for the period January - January 2014 (0.000% of AL)), and 0.000 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.000 MBq for the period January - January 2014 (0.000% of AL)).

  5. Advanced breaking technology on the Mochovce nuclear power plant building site

    International Nuclear Information System (INIS)

    Mraz, M.; Podel, R.; Vojta, A.

    1982-01-01

    Observing the given deadlines of the construction of the Mochovce nuclear power plant and the required volumes of breaking to the total value of 6.2 million m 3 of rock, the required output was derived for the 7th five year plan to the value of 200,000 m 3 per month, i.e., 10,000 m 3 per day and 700 m 3 per hour. The basic task is to build a flat building site with an area of 2,300 by 700 m 2 which requires the removal of a masiff of rocks rising to a height of 37 m, and by compacting the mined rock to build heaps to a height of 20 m. The rocks were disintegrated by blasting. Surface blasting was used for mining faces and ribs. POLONIT 2 or PERMON DAP 1 were mainly used for blasting (ammonium nitrate explosives). The Danubit 1 detonator was used in holes flooded with water. For drilling a combination was used of drilling machines HBM 70 Hausherr with a drilling diameter of 130 to 155 mm and Ingersol Rand ECM 350 with a drilling diameter of 80 mm. The compressors used are Atlas Copco XRHS 350 Dd and PTS 900 Dd. As the optimal combination of machines for the removal of disengaged material for the daily output of 15,000 m 3 the combination was used of 6 excavators with a shovel volume of 2.5 m 3 ORENSTEIN-KOPPEL RH 25 with 12 Kockum 445 trucks and 18 ORENSTEIN-KOPPEL RH 40 excavators with a shovel volume of 4 m 3 and a total of 64 Caterpillar 769 C, Belaz 548 A, Tatra T 200 and T 138 S1 trucks. The planned targets are being fulfilled and the work performed up to now on the Mochovce site equals 2.5 million m 3 of excavated and removed rock. (B.S.)

  6. Advanced breaking technology on the Mochovce nuclear power plant building site

    Energy Technology Data Exchange (ETDEWEB)

    Mraz, M; Podel, R; Vojta, A [Vyskumny Ustav Inzinierskych Stavieb, Bratislava (Czechoslovakia)

    1982-10-01

    Observing the given deadlines of the construction of the Mochovce nuclear power plant and the required volumes of breaking to the total value of 6.2 million m/sup 3/ of rock, the required output was derived for the 7th five year plan to the value of 200,000 m/sup 3/ per month, i.e., 10,000 m/sup 3/ per day and 700 m/sup 3/ per hour. The basic task is to build a flat building site with an area of 2,300 by 700 m/sup 2/ which requires the removal of a masiff of rocks rising to a height of 37 m, and by compacting the mined rock to build heaps to a height of 20 m. The rocks were disintegrated by blasting. Surface blasting was used for mining faces and ribs. POLONIT 2 or PERMON DAP 1 were mainly used for blasting (ammonium nitrate explosives). The Danubit 1 detonator was used in holes flooded with water. For drilling a combination was used of drilling machines HBM 70 Hausherr with a drilling diameter of 130 to 155 mm and Ingersol Rand ECM 350 with a drilling diameter of 80 mm. The compressors used are Atlas Copco XRHS 350 Dd and PTS 900 Dd. As the optimal combination of machines for the removal of disengaged material for the daily output of 15,000 m/sup 3/ the combination was used of 6 excavators with a shovel volume of 2.5 m/sup 3/ ORENSTEIN-KOPPEL RH 25 with 12 Kockum 445 trucks and 18 ORENSTEIN-KOPPEL RH 40 excavators with a shovel volume of 4 m/sup 3/ and a total of 64 Caterpillar 769 C, Belaz 548 A, Tatra T 200 and T 138 S1 trucks. The planned targets are being fulfilled and the work performed up to now on the Mochovce site equals 2.5 million m/sup 3/ of excavated and removed rock.

  7. Mathematical Analysis of Malfunctions Caused by Seepage Water to the Republic Radioactive Waste Dump in Mochovce

    Directory of Open Access Journals (Sweden)

    Jozef Kuzma

    2007-01-01

    Full Text Available The storage of radioactive waste and the problem of assuring the low and medium radioactive waste is an actual interdisciplinary problem. An important factor influencing on a complex approach to solving these problems is also a creation of suitable technical conditions for its long-term storage. In this article we mathematically analyze an influence of the break covering and its effect on the long-term stability and reliable serviceability of the Republic radioactive waste dump in Mochovce.

  8. Completion of Units 3 and 4 at Mochovce NPP

    International Nuclear Information System (INIS)

    Aquilanti, G.

    2009-01-01

    After the completion of a feasibility study, SE/ENEL decided to complete Mochovce Nuclear Power Plant Units 3 and 4 in April 2007. In July 2008, after a revision of the Basic Design that led to the inclusion of additional safety improvements, the European Commission issued a positive viewpoint on the decision. In August 2008 the Slovak Nuclear Regulatory Authority issued a permit for 'modification of a construction project prior to its completion', approving the Basic Design modifications: the kick-off of site activities was on November 2008. In December 2008, SE initiated the Environmental Impact Assessment (EIA) procedure aimed at obtaining the Operational License by submitting the EIA intent to the Ministry of Environment. A multi contractual strategy was adopted for the completion works: the total number of foreseen contracts is about 250 (90 main and additional 160 minor). In the following the present status of the project is presented: in particular, the Project Management system implemented by SE/ENEL is described and the progress of the engineering, fabrication and construction activities is analyzed. (author)

  9. Eco information 10. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within October 2014

    International Nuclear Information System (INIS)

    2014-11-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within October 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.512 GBq of tritium (8.464 GBq for the period January - October 2014 (2.82% of AL)) and summary of gamma-radionuclides 0.147 GBq (2.904 GBq for the period January - October 2014 (64.13% of AL)). The radioactive effluents into hydrosphere within July - September 2014 for FS KRAO were: 60 kBq of 90 Sr (489 kBq for the period January - September), 0.003 kBq of summary alpha (0.030 kBq of annually value) and 1920 kBq of 14 C for the period July - September (39367 kBq of annually value). The radioactive effluents into hydrosphere within October 2014 for RU RAO were: 0 MBq of tritium (13.064 MBq for the period January - October 2014 (0.069% of AL)); 0 MBq of 137 Cs in October 2014 (0.092 MBq for the period January - August 2014 (0.404% of AL)); 0.128 MBq of 90 Sr - the value within July - September 2014 (0.324 MBq for the period January - September 2014 (0.13% of AL)); 0 MBq of 60 Co in October 2014 (0.093 MBq for the period January - October 2014 (0.415% of AL)); 0.006 MBq of 239 Pu (0.016 MBq for the period April - June 2014 (2.86% of AL)). Volume of liquid effluents in October 2014 was 0 m 3 (5221 m 3 for the period January - October 2014). The radioactive effluents into atmosphere within October 2014 for FS KRAO were: 0.0007 MBq of gamma radionuclides (0.0055 MBq for the period January - October 2014, that is 0.0068% of annually limit (AL)); 0.025 kBq of alpha radionuclides within July - September 2014 (0.071 kBq for the period July - September 2014 (0.0071% of AL)), and 0.161 kBq of 89 Sr and 90 Sr - the value within July - September 2014 (0.465 kBq for the period January

  10. Eco information 4. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within April 2016

    International Nuclear Information System (INIS)

    2016-05-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within April 2016 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.642 GBq of tritium (0.649 GBq for the period January - April 2016 (0.213% of AL)) and summary of gamma-radionuclides 0.000 GBq (0.000 GBq for the period January - April 2016 (0.0% of AL)). The radioactive effluents into hydrosphere within January - January 2016 for FS KRAO were: 0 kBq of 90 Sr (0 kBq for the period January - March 2016), 0.024 kBq of summary alpha (0.024 kBq of annually value) and 10.817 kBq of 14 C for the period January - March 2016 (01.817 kBq of annually value). The radioactive effluents into hydrosphere within April 2016 for RU RAO were: 0.000 MBq of tritium (2.840 MBq for the period January - April 2016 (0.015% of AL)); 0.000 MBq of 137 Cs in April 2016 (0.026 MBq for the period January - April 2016 (0.114% of AL)); 0.248 MBq of 90 Sr - the value within January - March 2016 (0.248 MBq for the period January - April 2016 (0.102% of AL)); 0.000 MBq of 60 Co in April 2016 (0.018 MBq for the period January - April 2016 (0.080% of AL)); 0.009 MBq of 239 Pu (0.009 MBq for the period January - March 2016 (1.607% of AL)). Volume of liquid effluents in January 2016 was 0 m 3 (1135 m 3 for the period January - April 2016). The radioactive effluents into atmosphere within April 2016 for FS KRAO were: 0.0010 MBq of gamma radionuclides (0.0041 MBq for the period January - April 2016, that is 0.0039% of annually limit (AL)); 0.027 kBq of alpha radionuclides within January - March 2016 (0.027 kBq for the period January - March 2016 (0.0027% of AL)), and 0.179 kBq of 89 Sr and 90 Sr - the value within January - March 2016 (0.179 kBq for the period January - March

  11. Eco information 2 Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within February 2016

    International Nuclear Information System (INIS)

    2016-03-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within February 2016 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.007 GBq of tritium (0.000 GBq for the period January - February 2016 (0.02% of AL)) and summary of gamma-radionuclides 0.215 GBq (0.215 GBq for the period January - February 2016 (5.51% of AL)). The radioactive effluents into hydrosphere within January - March 2016 for FS KRAO were: 0 kBq of 90 Sr (0 kBq for the period January - March 2016), 0 kBq of summary alpha (0 kBq of annually value) and 0 kBq of 14 C for the period January - March 2016 (0 kBq of annually value). The radioactive effluents into hydrosphere within January 2016 for RU RAO were: 2.272 MBq of tritium (2.272 MBq for the period January - March 2016 (0.012% of AL)); 0.018 MBq of 137 Cs in February 2016 (0.018 MBq for the period January - March 2016 (0.079% of AL)); 0.000 MBq of 90 Sr - the value within January - March 2016 (0.000 MBq for the period January - March 2016 (0.000% of AL)); 0.013 MBq of 60 Co in February 2016 (0.013 MBq for the period January - March 2016 (0.058% of AL)); 0.000 MBq of 239 Pu (0.000 MBq for the period January - March 2016 (0.00% of AL)). Volume of liquid effluents in February 2016 was 908 m 3 (908 m 3 for the period January - February 2016). . The radioactive effluents into atmosphere within February 2016 for FS KRAO were: 0.0009 MBq of gamma radionuclides (0.002 MBq for the period January - February 2016, that is 0.0025% of annually limit (AL)); 0.000 kBq of alpha radionuclides within January - March 2016 (0.000 kBq for the period January - March 2016 (0.000% of AL)), and 0.000 kBq of 89 Sr and 90 Sr - the value within January - March 2016 (0.000 kBq for the period January

  12. Computerized information system of the Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Holik, V.

    1986-01-01

    The computer-based information system for the Mochovce nuclear power plant has a hierarchic structure which incorporates SM 1804 microcomputers and SM 1420 minicomputers. With regard to operation it is divided into two levels: the information system at the level of power plant units and the information system t the level of the whole power plant. The information system of a unit provides the collection of information on the technological equipment of each unit for the operative control of the unit and documentation on unit operation. Each unit has its own independent computer information system. The actual nucleus of each unit information system consists of two computer complexes based on SM 1420 twin computers, mutually substitutional. The power plant level information system provides the processing and output of information for personnel in the central control room of the power plant and for other managerial staff. It uses preprocessed information from the unit information systems and direct information from non-unit installations and from dosimetric control rooms of the power plant units. This information system is also based on a computer complex with two SM 1420 computers. (Z.M.)

  13. Review of selected contributions of the conference 'Integrated quality management systems in completion of units 3 and 4 Mochovce'

    International Nuclear Information System (INIS)

    2009-04-01

    There were 14 contributions presented of the conference focused on the integrated quality management systems in completion EMO34. Contributions were focused both on theoretical problems from the project management area and on the applications in practice in management systems implementation in accordance with the standards: STN EN ISO 9001:2000, STN EN ISO 14 001:2005, and OHSAS 18 001:1999 at the completion of the Nuclear Power Plant Mochovce of units 3 and 4

  14. Hydrobiological survey of some surface waters in the area of Mochovce nuclear power plant and their saprobiological assessment

    International Nuclear Information System (INIS)

    Kovacik, L.

    1987-01-01

    The results are presented of a hydrobiological study of three flows and one retention reservoir in the surroundings of the Mochovce nuclear power plant (Western Slovakia) performed in June 1982 and May 1983. The research was aimed at obtaining necessary information on the species composition of the algal flora (include blue-green algae) and selected groups of invertebrate hydrofauna (Sarcodina, Rotatoria, Cladocera, Copepoda, Oligochaeta and Chironomidae) in this territory. Natural waters were classified on the basis of the species composition of water organisms according to saprobiological criteria. (author). 4 refs

  15. Unit 1 and Unit 2 Nuclear Power Plant Mochovce construction finishing from primary contractor of technological part. Skoda Praha a. s. point of view

    International Nuclear Information System (INIS)

    Horky, F.

    2000-01-01

    In this paper the history of delivery of technological part for NPP V-1 Mochovce as well as of reconstruction and safety improvements by the Skoda Praha a.s. is presented. Primary contractor of technological part Skoda Praha together with its final suppliers proved ability to realize under hard conditions such a complicated work what was indisputedly Units 1 and 2 finishing. Company proved capability to conform itself flexibly in the course of work to requirements of customer for realization of safety measures which means that Units 1 and 2 fully satisfy international standards. By fulfilment of primary contractor of technology obligations and above all by takeover of complex responsibility for both Units putting in operation including responsibility for 'past' Skoda Praha put away one of basic problems which occurred in decision making to whom will be assigned construction finishing contract. These facts fully qualify Skoda Praha to be selected for possible Units 3 and 4 construction finishing as one of chief construction finishing participant

  16. Results of physics start-up tests of Mochovce and Bohunice units with 2-nd generation Gd fuel (average enrichment 4.87 %)

    International Nuclear Information System (INIS)

    Polakovic, F.

    2015-01-01

    There are presented main features of the fuel and the list of experimental neutron-physical characteristics measured during physics start-up tests.All together there were carried out 14 physics start-ups at Bohunice and Mochovce Units with the new type of fuel. Differences between theoretical and experimental neutron-physical characteristics were statistically processed and compared with the tests acceptance criteria. There are summarized results of reactor physics start-ups with 2-nd generation Gd fuel usage [ru

  17. Requirements and possible upgrading concept for the WWER-440/213: Mochovce NPP structures under seismic conditions

    International Nuclear Information System (INIS)

    Freiman, M.

    1993-01-01

    The Mochovce-Nuclear Power Plant is one of the WWER-440/213 plants which has been designed against earthquake. Nevertheless, the design earthquake has not been assessed adequately to the seismic hazard at the site. A new seismic design shall include an increased seismic input and assure an acceptable standard of safety. This contribution is related to some design aspects of civil structures for this nearly finished plant, such as: existing design and its margins with regard to the employed codes; requirements for a new design concept; effects to be expected by an increased design earthquake; applicable design methods; use of inelastic design spectra, behavior factors and capacity design; feasible upgrading measures. (author)

  18. Level 1 PSA study of Mochovce unit 1 NPP (SM AA 10 and 08)

    International Nuclear Information System (INIS)

    Cillik, I.

    1997-01-01

    This paper presents genesis of Level 1 PSA project preparation for all operational modes of Mochovce NPP unit 1 including the description of its' main objectives, scope and working method. The PSA study which includes full power (FPSA) as well as shutdown and low power conditions (SPSA) Level 1 PSA has to support the nuclear safety improvements of the unit. They evaluate the basic design and the benefits of all improvements, which were found necessary to be incorporated before the start-up of the unit. The study includes internal events (transients and under-loss of coolant accident, LOCAs), internal hazards as fires and floods and selected external hazards as earthquake, influence of external industry, extreme meteorological conditions and aircraft crash.The PSA (both FPSA and SPSA) models is developed using the RISK SPECTRUM PSA code. (author)

  19. Mochovce NPP safety measures evaluation from point of view of operational safety enhancement

    International Nuclear Information System (INIS)

    Cillik, I.; Vrtik, L.

    2000-01-01

    Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing. (author)

  20. Radwaste Treatment Centre Jaslovske Bohunice

    International Nuclear Information System (INIS)

    2000-01-01

    In this leaflet the Bohunice Radwaste Treatment Centre (BSC RAO) is presented. BSC RAO is designed to process and treat liquid and solid radwaste, arising from the NPP A-1 decommissioning, from NPPs V-1, V-2, and Mochovce operations, as well as institutional radwaste of diverse institutional (hospitals, research institutes) in the Slovak Republic. Transport, sorting, incineration, compacting, concentration and cementation of radwaste as well as monitoring of emission are described

  1. Current situation of the project finishing of the building of 3 and 4 block of the nuclear power plant Mochovce

    International Nuclear Information System (INIS)

    Niznan, S.

    2005-01-01

    In the contribution there is the basic information mentioned about history of building and the current situation at the finishing of the building of 3 and 4 block of the Nuclear Power Plant Mochovce with the use of project digitization. Further on the contribution shows what kinds of supporting material has been elaborated, what kind of decisions have been issued to the finishing of the building, way of financing and also the assumption of investment return under the defined conditions. An orientation time schedule of the finishing of the building and the crucial steps for its security are presented in the conclusion

  2. Chapter 7. Radioactive wastes

    International Nuclear Information System (INIS)

    2000-01-01

    The inspection and assessment activities of Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on minimization of activity and the quantity of produced radioactive waste (RAW), and on increasing safety of waste management. The general scheme of rad-waste management in the Slovak Republic is presented. The radioactive wastes produced during the operation of NPP V-1, NPP V-2 and NPP Mochovce in 1999 are listed.Liquid RAW was treated and conditioned into a solid form at the nuclear facility Technology for treatment and conditioning of RAW. In 1999 combustible solid waste was treated at the nuclear facility Incinerator of VUJE Trnava. Produced liquid and solid RAW are stored at designed equipment at individual nuclear installations (in case of NPP V-1, NPP V-2 Bohunice and NPP Mochovce in compliance with the Regulation No. 67/1987 Coll. law).The status of free capacity of these storages as of 31.121999 is presented. Storage solidified product built the SE-VYZ was fully filled at the end of 1999. In 1999 there was a significant improvement in the process of radioactive waste management by: (A) issuing approval for commissioning the National Repository for RAW, (B) issuing approval for commissioning the Treatment and Conditioning Center for RAW, (C) having the application for approval to transport conditioned RAW to the National repository Mochovce in the final stage of evaluation. At the beginning of 2000 it is realistic to expect that RAW conditioned in the Conditioning center of RAW will start to be disposed at the National repository of RAW in Mochovce

  3. PSA analysis focused on Mochovce NPP safety measures evaluation from operational safety point of view

    International Nuclear Information System (INIS)

    Cillik, I.; Vrtik, L.

    2001-01-01

    Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing.(author)

  4. Ecological impacts and damage - comparison of selected components for nuclear and conventional power plants (example of Mochovce nuclear power plant)

    International Nuclear Information System (INIS)

    Bucek, M.

    1984-01-01

    A comparison is given of ecological damage for the nuclear power plant in Mochovce and a conventional power plant with the same power. Ecological effects and damage are divided into three groups: comparable damage, ecological damage caused only by conventional power plants and ecological damage caused only by nuclear power plants. In the first group the factors compared are land requisition, consumption of utility water and air consumption. In the second group are enumerated losses of crops (cereals, sugar beet, potatoes, oleaginous plants) and losses caused by increased disease rate owing to polluted environment by conventional power plants. In the third group health hazards are assessed linked with ionizing radiation. Also considered are vent stack escapes. (E.S.)

  5. Participation of SKODA JS in the construction of the Temelin and Mochovce nuclear power plants

    International Nuclear Information System (INIS)

    Svec, A.; Zach, J.; Ruzicka, P.

    2000-01-01

    SKODA JS is the traditional manufacturer of WWER type reactor equipment and also supplier of the primary circuits and of equipment for the transport, refuelling and storage of fuel for Ver type nuclear power plants built in the Czech and Slovak Republics. The paper deals with activities of the company SKODA JS at two power plants whose reactor units are close to completion, viz. the Mochovce NPP in the Slovak Republic (4 x Ver 440 MW; unit 1 was put in operation in 1998, unit 2 is in the stage of commissioning, units 3 and 4 are not to be completed) and the Temelin NPP in the Czech Republic (2 x Ver 1000 MW, commissioning of units 1 and 2 is expected in 2001 and 2002, respectively). The scope of supplies to the two nuclear power plants (detailed design, delivery of equipment, installation, commissioning) and the course of construction from SKODA JS's viewpoint are described. The most important design changes and improvements made during the construction are highlighted. (author)

  6. The nuclear regulatory authority of the Slovak Republic and start-up of the Mochovce NPP

    International Nuclear Information System (INIS)

    Seliga, Mojmir

    1999-01-01

    The important aspect is testing if the nuclear energy in the Slovak Republic is due to obligatory rules acceptable and its operation is regulated by the state through the independent institution - The Nuclear Regulatory Authority of the Slovak Republic (UJD). UJD considers the whole area of public relations an essential component of its activity. UJD intends to serve the public true, systematic, qualified, understandable and independent information regarding nuclear safety of nuclear power plants, as well as regarding methods and results of UJD work. Generally, public information is considered as significant contribution to the creation of confidence into the regulatory work. The public relations are understood as attempts to establish, keep and improve UJD-s good relations to its neighbours through purposeful informing. An Information centre at the offices of UJD was built and opened in October 1995 with IAEA Director General as the first visitor. NPP Mochovee is an example of international co-operation in achieving internationally acceptable safety standards. Companies from France, Germany, USA, Russian Federation, Czech Republic and Slovakia and last, but not least also the IAEA participated significantly on increasing the safety level of this NPP. We have been fully aware of the importance of good communication with press, TV and radio broadcasting in this pre-operation and operation period about nuclear safety, nuclear standard and other nuclear aspects commissioning of the NPP Mochovce in the UJD. The information policy of the UJD was in this period focused on the preparation an actual press releases for general and specialised news- paper and national press agencies. Very important were the frequent presentations the requirement safety stages of the NPP Mochovce inIV and radio broadcasting by headquarters of the UJD. UJD as the state authority provides information related to its competence, namely information on safety of operation of nuclear installations

  7. Treatment and conditioning of solid and liquid raw

    International Nuclear Information System (INIS)

    Jakubec, R.

    2015-01-01

    Jadrova a vyradovacia spolocnost, a.s. (JAVYS) implements activities within the processes of treatment and conditioning of radioactive waste (RAW) at two nuclear facilities, one of them located in Bohunice - Technologies for treatment and conditioning of RAW. This nuclear facility includes: Bohunice RAW treatment centre, bituminization lines, waste water purification station and technologies for sorting, fragmentation and decontamination of metallic RAW. The Bohunice RAW treatment centre (BRTC) in Bohunice processes and conditions liquid and solid radioactive waste produced during the A1 NPP and V1 NPP decommissioning, waste from the operation of V2 NPP in Bohunice as well as from the operation of NPP EMO 1,2 in Mochovce. The BRTC includes the following technological facilities: sorting, high-pressure compaction, incineration, concentration and cementation. Treatment of radioactive wastes in the BRTC is described. (authors)

  8. The design preparation for radiation monitoring system in the frame of completion NPP Mochovce Units 3 and 4

    International Nuclear Information System (INIS)

    Sevecka, S.; Slavik, O.; Kapisovsky, V.

    2009-01-01

    In 1985 a Basic Design of Radiation Monitoring System (RMS) has been elaborated for Mochovce NPP unit 3 and 4 construction. Due to construction interruption in the following years this design solution became obsolete. A new solution of RMS have been developed with conception following that of original Basic Design accommodating also safety measures implemented in RMS of NPP EMO units 1 and 2, and based on modem instrumentation and computer technique. Following the updating of Basic Design documentation the preparation of elaboration of RMS detailed design was carried on. In the frame of this preparation a review of possible suppliers of instrumentation satisfying the conception of radiation monitoring system and the extension of required deliveries has been made. Also criteria on RMS suppliers selection have been determined. The types of monitoring systems and equipment, as well as their quantities, have been specified based on updated Basic Design requirements and production profiles and possibilities of potential suppliers. The required parameters of measurements (including measurement geometry) have been evaluated, as well as requirements of legislation and requirements of proposed RMS architecture. (authors)

  9. The experience from operation of electronic personal dosimetry system at Dukovany, Temelin and Mochovce NPPs after repair of Siemens dosemeters eliminating false doses

    International Nuclear Information System (INIS)

    Malysak, J.; Kocvara, S.; Jurochova, B.; Zelenka, Z.; Schacherl, M.; Zrubec, M.; Kaiser, H.

    2003-01-01

    This presentation summarizes the operational experience of the Electronic Personal Dosimetry Systems installed at Dukovany, Temelin and Mochovce NPPs. The system consists of three basic parts: Electronic personal dosemeters (EPD); Physical layer (HW); Logical layer (SW). Number of false doses before and after correction is presented. This presentation has demonstrated the possibilities of SEOD system and the possibility of easy dose comparison between the individual NPPs after introducing this electronic dosimetry system. Basically, the results of film and electronic dosimetry systems are according to our findings nearly identical. Electronic dosemeter sensitivity to interfering electromagnetic fields is a problem which is easily re-movable. In addition, if we know this problem, these false doses in the SEOD system can be easily revealed (e.g. by investigation of histograms) and repaired

  10. SE-VYZ - Decommissioning of Nuclear Installations, Radioactive Waste and Spent Fuel Management

    International Nuclear Information System (INIS)

    Anon

    2004-01-01

    In this presentations processes of radioactive waste treatment in the Bohunice Radioactive Waste Processing Center (SE-VYZ), Jaslovske Bohunice are presented. Decommissioning of the A-1 NPP is also presented. Disposal of conditioned radioactive waste in fibre concrete containers (FCC) are transported to Mochovce from Jaslovske Bohunice by the transport truck where are reposited in the National radioactive waste repository Mochovce. The Interim spent fuel storage facility (ISFSF) is included into this presentation

  11. The management of safety within the completion of units 3. and 4. in NPP Mochovce

    International Nuclear Information System (INIS)

    Ocenas, M.

    2009-01-01

    The contribution defines the way of management of safety and protection of health and protection against the fire during completion of units 3. and 4. in NPP Mochovce. The creation of the management of safety raised from the legal and other requirements applied in the civil activities and mainly from the requirements for coordination of safety on the site. The whole system is methodically managed through the 5 basic documents so-called 'Building rules': 1) Safety-technical conditions of performance in SE, Inc. Bratislava (project MO34); 2) MO34/1/MNA-003.00-02 the elaboration of the integrated safety plan; 3) MO34/1/NA-003.00-03 risks analyse; 4) PNM3460100 Integrated safety plan for completion of Units 3.and 4 in NPP Mochovce; 5) Project of construction organization. The system itself of the management of the safety prevention must by provided by the supplier in compliance with the standard OHSAS 18 001 and ISO 14001, and in compliance with the requirement of the builder applied in the technical specification for the contract. Most of necessary related documentation of Safety plan for the site is usually part of the documentation for quality management of contractor. Therefore it is necessary to put the reference in each chapter of the Safety plan for site and the standpoint how to apply it for the particular specific situation. The coordinator is mandatory to manage the prevention for the part of safety of specified site and to coordinate the activity of suppliers during the works tie in this way, that the each contractor shall meet the safety requirements given by safety plan and also to identify and to eliminate the risks menaced in the particular work places or the suppliers each other. The builder established its own control system and for this purpose he settled the data base so-called 'The system of corrective and precautionary activities'. The system registers in its data base all discrepancies determined during the regular controls of the head workers

  12. Researches of a thermodynamic behaviour of bubbling vacuum system bubble condenser NPP 'Mochovce'

    International Nuclear Information System (INIS)

    Rjeznikov, Iu.V.; Lifshitz, E.V.; Kouznetsov, M.V.; Antropov, V. N.; Doulepov, U. N.; Suchanek, M.

    1997-01-01

    During joint development and designing of the bubbling vacuum system (BVS) equipment for localization of under-loss of coolant accident (LOCA) consequences on NPPs with WWER 440/213, a large volume of experimental and calculational activities have been performed by VTI and SverdNIIchimmash for the substantiation of functionality of this system, and in particular, for bubbler-condenser (BC) design, as a part of BVS. However, not looking on broad introduction of BVS on 16-th NPP units with WWER 440/213, its functionality was subjected to a doubt from experts of different countries. Sequentially, that promoted issue of the IAEA, document and OECD document. Therefore, before commissioning of the NPP 'Mochovce' unit 1 it was decided to execute additional experimental and computational researches for Safety Analysis Report preparation. Within the framework of these BVS thermodynamic behavior researches, in particular the following problems were chosen: (1) The check of a capability of valves DN 250 blocking in an opened position, as a result of return pressure differential on BC, during vent clearing process of the hydro-lock, that can sequentially result in an a drop of efficiency of stem condensation in BC pool; (2) To provide by direct measurements the absence of pressure oscillations dangerous for strength of a BC design in different modes of steam condensation in BC and to execute computational researches of instability of steam condensation processes (for such mode as 'chugging'); (3) Study influences of pool swell and water carry over through check valves DN 500 in the air traps on a BVS functionality; (4) To determine by a computational way the maximum pressure in NPP premises during LOCA, with taking into consideration additional failures of the BC equipment: absence of a water on two and more BC plates and DN 250 valves have blocked in an opened position (conservative conditions). (authors)

  13. Alternatives of Treatment and Final Disposition of the Solid Hospital residuals

    International Nuclear Information System (INIS)

    Meza Monge, K.

    1998-01-01

    The current handling, treatment and final disposition of the hospital solid waste in Costa Rica are considered inadequate or at least insufficient. This situation represents a serious danger for the population's health and the environment, because they are exposed to infectious agents, toxic substances and even radioactive products that are generated among the residuals of the centers of health. This work, alternatives propose for the treatment and adequate final disposition of the solid waste produced in the hospitals of the country. They take into consideration the characteristics that present these residuals, the advantages and disadvantages of each one of the existent techniques and the technical and economic possibilities of the country. For this purpose, in first instance, a revision about the properties, the quality and the quantity of the solid waste produced by the national hospital centers was carried out. Also, a diagnostic of the current situation of the treatment and final disposition of these residuals in some of the most important hospitals of the country, as well as of the possibilities of physical space with that they count on was carried out. Then, the existent different treatment techniques and final disposition for the solid waste that comes from the centers of health are described, as well as their advantages and disadvantages and a comparative analysis of the same ones is carried out. The objective is completed, since alternatives of treatment and final disposition that are considered appropriate for this type of residuals are planned. Nevertheless, in the future, more detailed investigations and studies of feasibility, with the purpose of developing handling programs and elimination of the solid waste for each one of the hospital centers in Costa Rica should be carried out. (Author) [es

  14. Case law

    International Nuclear Information System (INIS)

    2015-01-01

    This section treats of the two following case laws: Slovak Republic: Further developments in cases related to the challenge by Greenpeace Slovakia to the Mochovce nuclear power plant; United States: Judgment of the Nuclear Regulatory Commission denying requests from petitioners to suspend final reactor licensing decisions pending the issuance of a final determination of reasonable assurance of permanent disposal of spent fuel

  15. Report on the evaluation under the Act No 24/2006 of Coll. Environmental Impact Assessment Law Extension of National Radioactive Waste Repository in Mochovce for disposal low-level radioactive waste and construction of very low-level radioactive waste repository

    International Nuclear Information System (INIS)

    Hanusik, V.; Moravek, J.; Kusovska, Z.

    2011-01-01

    The report elaborated assessment of the environmental impact of extension of the National Radioactive Waste Repository in Mochovce for disposal of low and intermediate level radioactive wastes. Within this repository also the premises for very low level radioactive waste deposition should be built. The assessment report was prepared according to the Act no. 24/2006 Coll, as amended 'On the assessment of environmental impacts' Annex No. 11 upon The scope of assessment issued by the competent authority on the basis of assessment of Intent for this action. The report was prepared in VUJE, Inc. Trnava for Nuclear and Decommissioning Company, Inc. Bratislava (JAVYS).

  16. Treatment and final storage of radioactive wastes from the nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Krause, H [Kernforschungszentrum Karlsruhe (Germany, F.R.)

    1977-05-01

    Types, amounts and activity concentrations of the radioactive wastes arising from the different sections of the fuel cycle are described as well as the methods of their treatment and final disposal. By conversion to glass products, highly active fission product solutions can be transferred into a form well suited for final disposal. Low and medium level waste waters are purified so far that safe discharge or reuse is possible. The concentrates thus produced are incorporated into concrete or bitumen. Baling lends itself for treatment of non-combustible solid wastes. Combustible wastes can be incinerated, the residues are incorporated into concrete. For final storage of the conditioned wastes, salt formations in the deep underground are chosen in the Federal Republic of Germany. They offer a series of favourable preconditions for this purpose and guarantee the isolation of the radionuclides from the biocycle over secular periods of time.

  17. Experience gained during commissioning and trial operation of Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    GaL, P.; Adamica, T.; Marosik, V.; Rehak, A.

    2000-01-01

    In this paper authors describe the experience gained during commissioning and trial operation of Mochovce NPP (EMO). The first year of EMO operation from the point of view of safety and reliability was successful. Evidently we were challenged with certain problems characteristic to this stage of operation which resulted in automatic reactor shutdown. There were 11 automatic shutdowns in 1998 by action of the quick emergency protection AO-1 and two manual shutdowns by the AO-1 key. In 1999, there were 6 automatic shutdowns by action of the quick emergency protection AO-1. Three of them was connected to the falsely activated binary signal of MCP switch of, in two cases the reason came out from the turbo-generator (TG) cooling water system. Very positive trend in the operation of both units shows the fact that during all commissioning period of the second unit there were only three automatic reactor shutdowns by the signal AO-1. All these actions were done in frame of commissioning tests. All causes which activated the automatic unit shutdowns were found out and rectified, the overall tuning of the cooling water system is on the process now. The solution of this problem is possible only power commissioning, and in the stage of the trial operation had no direct impacts on the nuclear, radiation, or technical safety respectively. In 1998 two events according to the INES scale after second unit commissioning because of two unit links of the cooling water system. The operational events during the commissioning tests, start-up tests, physical commissioning, were ranked the category 1 ('Action of SIS U040 p po <8,34 MPa at the system 2 and 3' and 'Breaching the L and C'). In 1999 only events occurred that were ranked in the category safety insignificant events and lower (category 0, or off the scale respectively). In the frame of the safety culture principles adopted, such as critical attitude, exact and careful approach, and communication, these problems were given the

  18. Chemical mode control in nuclear power plant decommissioning during operation of technologies in individual radioactive waste processing plants

    International Nuclear Information System (INIS)

    Horvath, J.; Dugovic, L.

    1999-01-01

    Sewage treatment of nuclear power plant decommissioning is performed by system of sewage concentration in evaporator with formation of condensed rest, it means radioactive waste concentrate and breeding steam. During sewage treatment plant operation department of chemical mode performs chemical and radiochemical analysis of sewage set for treatment, chemical and radiochemical analysis of breeding steam condensate which is after final cleaning on ionization filter and fulfilling the limiting conditions released to environment; chemical and radiochemical analysis of heating steam condensate which is also after fulfilling the limiting conditions released to environment. Condensed radioactive concentrate is stored in stainless tanks and later converted into easy transportable and chemically stable matrix from the long term storage point of view in republic storage Mochovce. The article also refer to bituminous plant, vitrification plant, swimming pool decontamination plant of long term storage and operation of waste processing plant Bohunice

  19. Alternatives of Treatment and Final Disposition of the Solid Hospital residuals; Alternativas de Tratamiento y Disposicion Final de los Residuos Solidos Hospitalarios

    Energy Technology Data Exchange (ETDEWEB)

    Meza Monge, K

    1998-07-01

    The current handling, treatment and final disposition of the hospital solid waste in Costa Rica are considered inadequate or at least insufficient. This situation represents a serious danger for the population's health and the environment, because they are exposed to infectious agents, toxic substances and even radioactive products that are generated among the residuals of the centers of health. This work, alternatives propose for the treatment and adequate final disposition of the solid waste produced in the hospitals of the country. They take into consideration the characteristics that present these residuals, the advantages and disadvantages of each one of the existent techniques and the technical and economic possibilities of the country. For this purpose, in first instance, a revision about the properties, the quality and the quantity of the solid waste produced by the national hospital centers was carried out. Also, a diagnostic of the current situation of the treatment and final disposition of these residuals in some of the most important hospitals of the country, as well as of the possibilities of physical space with that they count on was carried out. Then, the existent different treatment techniques and final disposition for the solid waste that comes from the centers of health are described, as well as their advantages and disadvantages and a comparative analysis of the same ones is carried out. The objective is completed, since alternatives of treatment and final disposition that are considered appropriate for this type of residuals are planned. Nevertheless, in the future, more detailed investigations and studies of feasibility, with the purpose of developing handling programs and elimination of the solid waste for each one of the hospital centers in Costa Rica should be carried out. (Author) [Spanish] El actual manejo, tratamiento y disposicion final de los desechos solidos hospitalarios en Costa Rica se considera inadecuado o cuando menos

  20. Request for modification of 200 Area effluent treatment facility final delisting

    International Nuclear Information System (INIS)

    Bowman, R.C.

    1998-01-01

    A Delisting Petition submitted to the U.S. Environmental Protection Agency in August 1993 addressed effluent to be generated at the 200 Area Effluent Treatment Facility from treating Hanford Facility waste streams. This Delisting Petition requested that 71.9 million liters per year of treated effluent, bearing the designation 'F001' through 'F005', and/or 'F039' that is derived from 'F001' through 'F005' waste, be delisted. On June 13, 1995, the U.S. Environmental Protection Agency published the final rule (Final Delisting), which formally excluded 71.9 million liters per year of 200 Area Effluent Treatment Facility effluent from ''being listed as hazardous wastes'' (60 FR 31115 now promulgated in 40 CFR 261). Given the limited scope, it is necessary to request a modification of the Final Delisting to address the management of a more diverse multi-source leachate (F039) at the 200 Area Effluent Treatment Facility. From past operations and current cleanup activities on the Hanford Facility, a considerable amount of both liquid and solid Resource Conservation and Recovery Act of 1976 regulated mixed waste has been and continues to be generated. Ultimately this waste will be treated as necessary to meet the Resource Conservation and Recovery Act Land Disposal Restrictions. The disposal of this waste will be in Resource Conservation and Recovery Act--compliant permitted lined trenches equipped with leachate collection systems. These operations will result in the generation of what is referred to as multi-source leachate. This newly generated waste will receive the listed waste designation of F039. This waste also must be managed in compliance with the provisions of the Resource Conservation and Recovery Act

  1. Request for modification of 200 Area effluent treatment facility final delisting

    Energy Technology Data Exchange (ETDEWEB)

    BOWMAN, R.C.

    1998-11-19

    A Delisting Petition submitted to the U.S. Environmental Protection Agency in August 1993 addressed effluent to be generated at the 200 Area Effluent Treatment Facility from treating Hanford Facility waste streams. This Delisting Petition requested that 71.9 million liters per year of treated effluent, bearing the designation 'F001' through 'F005', and/or 'F039' that is derived from 'F001' through 'F005' waste, be delisted. On June 13, 1995, the U.S. Environmental Protection Agency published the final rule (Final Delisting), which formally excluded 71.9 million liters per year of 200 Area Effluent Treatment Facility effluent from ''being listed as hazardous wastes'' (60 FR 31115 now promulgated in 40 CFR 261). Given the limited scope, it is necessary to request a modification of the Final Delisting to address the management of a more diverse multi-source leachate (F039) at the 200 Area Effluent Treatment Facility. From past operations and current cleanup activities on the Hanford Facility, a considerable amount of both liquid and solid Resource Conservation and Recovery Act of 1976 regulated mixed waste has been and continues to be generated. Ultimately this waste will be treated as necessary to meet the Resource Conservation and Recovery Act Land Disposal Restrictions. The disposal of this waste will be in Resource Conservation and Recovery Act--compliant permitted lined trenches equipped with leachate collection systems. These operations will result in the generation of what is referred to as multi-source leachate. This newly generated waste will receive the listed waste designation of F039. This waste also must be managed in compliance with the provisions of the Resource Conservation and Recovery Act.

  2. SE-VYZ

    International Nuclear Information System (INIS)

    Anon

    2004-01-01

    On this CD compact disc 6 video-films (A-1 NPP; Bituminization; Cementation; Pressing; The Interim spent fuel storage facility; Transport into the National radioactive waste repository Mochovce; Ignition; and Vitrification). In these films process of radioactive waste treatment in the Bohunice Radioactive Waste Processing Center (SE-VYZ) is presented. 2 presentations about radioactive wastes treatment in the SE-VYZ are included

  3. Final height and body mass index after treatment for childhood acute lymphoblastic leukemia

    Directory of Open Access Journals (Sweden)

    Tadej Battelino

    2006-03-01

    Full Text Available Background: Newer and more agressive forms of chemotherapy and newer protocols in the treatment have increased the survival rate of children with malignancies. Improved survival rates in children treated for acute lymphoblastic leukemia have focused attention on late effects including disorders of growth and puberty, and development of overweight or obesity.Methods: The height and weight expressed as body mass index (BMI of 47 patients (29 girls, 18 boys long-term survivors of childhood lymphoblastic leukemia was retrospectively analyzed. Height standard deviation score (HSDS according to Tanner and body mass index standard deviation scores (BMISDS before treatment and at follow-up were calculated. At the time of analysis all patients remained in first remission. Twenty-eight patients had cranial radiation with 12–18 Gy and 15 with 20–30 Gy. Four patients had no radiotherapy. All patients were treated with standard chemotherapy including intrathecal Methotrexat. Mean age (SD at the diagnosis was 5 5/12 (3 2/12 years, range (5/12 – 12 5/12 and at the time of evaluation 17 11/12 (3 9/12 years, range (10 1/12 – 31 6/12.Results: We observed significant decrease in HSDS from diagnosis to the final height in both radiation groups (p < 0.01 but the decrement in final height was similar with both radiation dose regimens. The decrement in final height SDS was greater in patients treated at a younger age (Pearson, p < 0.01. Girls treated with higher radiation dose (20–30 Gy were more severely affected than boys. In both radiation dose treatment groups there was a significant increase in BMISDS between diagnosis and final height (p < 0.0001 with no significant difference between treatment groups. Menarche occurred earlier in girls than normal with no significant difference between both radiation dose regimens.Conclusions: We observed significant deterioration in HSDS and increment in BMISDS regardless to the radiation dose.

  4. Personnel Training

    International Nuclear Information System (INIS)

    Tokar, M.

    2012-01-01

    The professional training of employees for Units 3 and 4 of the Mochovce Power Plant is approaching finals. At the beginning, in particular the main control room operators were trained, later all the other employees needed for power plant commissioning and operation. In June, the second phase of the project will start; it will be focused on the new equipment of the Units under commissioning. (author)

  5. VUJE experience with cementation of liquid and wet radioactive waste

    International Nuclear Information System (INIS)

    Kravarik, Kamil; Holicka, Zuzana; Pekar, Anton; Zatkulak, Milan

    2011-01-01

    Liquid and wet LLW generated during operation as well as decommissioning of NPPs is treated with different methods and fixed in a suitable fixation matrix so that a final product meets required criteria for its disposal in a final repository. Cementation is an important process used for fixation of liquid and wet radioactive waste such as concentrate, spent resins and sludge. Active cement grout is also used for fixation of low level solid radioactive waste loaded in final packing containers. VUJE Inc. has been engaged in research of cementation for long. The laboratory for analyzing radioactive waste properties, prescription of cementation formulation and estimation of final cement product properties has been established. Experimental, semi-production cementation plant has been built to optimize operation parameters of cementation. VUJE experience with cementation of liquid and wet LLW is described in the presented paper. VUJE has assisted in commissioning of Jaslovske Bohunice Treatment Centre. Cement formulations for treatment of concentrate, spent resins and sludge have been developed. Research studies on the stability of a final concrete packaging container for disposal in repository have been performed. Gained experience has been further utilized for design and manufacture of several cementation plants for treatment of various liquid and wet LLW. Their main technological and technical parameters as well as characterization of treated waste are described in the paper. Applications include the Mochovce Final Treatment Centre, Movable Cementation Facility utilizing in-drum mixing for treatment of sludge, Cementation Facility for treatment of tritiated water in Latvia and Cementation Facility for fixation of liquid and solid institutional radioactive waste in Bulgaria, which utilizes lost stirrer mixer. (author)

  6. Characterize and Model Final Waste Formulations and Offgas Solids from Thermal Treatment Processes - FY-98 Final Report for LDRD 2349

    Energy Technology Data Exchange (ETDEWEB)

    Kessinger, Glen Frank; Nelson, Lee Orville; Grandy, Jon Drue; Zuck, Larry Douglas; Kong, Peter Chuen Sun; Anderson, Gail

    1999-08-01

    The purpose of LDRD #2349, Characterize and Model Final Waste Formulations and Offgas Solids from Thermal Treatment Processes, was to develop a set of tools that would allow the user to, based on the chemical composition of a waste stream to be immobilized, predict the durability (leach behavior) of the final waste form and the phase assemblages present in the final waste form. The objectives of the project were: • investigation, testing and selection of thermochemical code • development of auxiliary thermochemical database • synthesis of materials for leach testing • collection of leach data • using leach data for leach model development • thermochemical modeling The progress toward completion of these objectives and a discussion of work that needs to be completed to arrive at a logical finishing point for this project will be presented.

  7. Part II. Chapter VII. Lack of knowledge has generated misconceptions about WWER in Western Europe

    International Nuclear Information System (INIS)

    Bucha, T.

    2008-01-01

    In this interview Mr. Giancarlo Aquilanti (Project Director Mochovce NPP, Unit-3 and Unit-4, the Slovenske elektrarne, a. s., a member of ENEL) evaluates reactor safety in Mochovce NPP. Perspectives of development of nuclear energy in the Slovak Republic and Italia are discussed.

  8. MASTICATION, PHONETICS AND ESTHETICS AS A FINAL RESULT OF PARTIAL OR COMPLETE DENTURE TREATMENT.

    Directory of Open Access Journals (Sweden)

    Kalina Georgieva

    2015-08-01

    Full Text Available Three target groups- dentists/ dental students, dental technicians and patients were asked to fill in an anonymous questionnaire about their satisfaction of the final results after prosthetic treatment with removable dentures using a scale from 1 to 5 (1- completely dissatisfied, 2-dissatisfied, 3-indifferent, 4-satisfied, 5-completely satisfied. The mean results (including colour, shape and size of artificial teeth, arrangement of front teeth, colour of artificial gums, phonetics, mastication, natural smile, enough space for tongue for all three groups of respondents were compared. Dental technicians (4,34 are more satisfied than dentists/dental students (3,62 and patients (3,53. A successful outcome of prosthetic treatment depends on one hand on the professional approach of the dental team and on the other hand on the patient’s motivation and cooperation. The predictive final results and realistic expectations lead to satisfaction of all participants in the treatment process.

  9. Calculation of external exposure during transport and disposal of radioactive waste arisen from dismantling of steam generator

    International Nuclear Information System (INIS)

    Hornacek, M.; Necas, V.

    2014-01-01

    The dismantling of large components (reactor pressure vessel, reactor internals, steam generator) represents complex of processes involving preparation, dismantling, waste treatment and conditioning, transport and final disposal. To optimise all of these activities in accordance with the ALARA principle the prediction of the exposure of workers is an essential prerequisite. The paper deals with the calculation of external exposure of workers during transport and final disposal of heat exchange tubes of steam generator used in Slovak nuclear power plant V1 in Jaslovske Bohunice. The type of waste packages, the calculation models of truck and National Radioactive Waste Repository in Mochovce are presented. The detailed methodology of radioactive waste disposal is showed and the degree of influence of time decay (0, 5 and 10 years) on the radiological conditions during transport and disposal is studied. All of the results do not exceed the limits given in Slovak and international regulatory documents. (authors)

  10. Regulation of radioactive waste management

    International Nuclear Information System (INIS)

    2002-01-01

    This bulletin contains information about activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD). In this leaflet the regulation of radioactive waste management of the UJD are presented. Radioactive waste (RAW) is the gaseous, liquid or solid material that contains or is contaminated with radionuclides at concentrations or activities greater than clearance levels and for which no use is foreseen. The classification of radioactive waste on the basis of type and activity level is: - transition waste; - short lived low and intermediate level waste (LlLW-SL); - long lived low and intermediate level waste (LlLW-LL); - high level waste. Waste management (in accordance with Act 130/98 Coll.) involves collection, sorting, treatment, conditioning, transport and disposal of radioactive waste originated by nuclear facilities and conditioning, transport to repository and disposal of other radioactive waste (originated during medical, research and industrial use of radioactive sources). The final goal of radioactive waste management is RAW isolation using a system of engineered and natural barriers to protect population and environment. Nuclear Regulatory Authority of the Slovak Republic regulates radioactive waste management in accordance with Act 130/98 Coll. Inspectors regularly inspect and evaluate how the requirements for nuclear safety at nuclear facilities are fulfilled. On the basis of safety documentation evaluation, UJD issued permission for operation of four radioactive waste management facilities. Nuclear facility 'Technologies for treatment and conditioning contains bituminization plants and Bohunice conditioning centre with sorting, fragmentation, evaporation, incineration, supercompaction and cementation. Final product is waste package (Fibre reinforced container with solidified waste) acceptable for near surface repository in Mochovce. Republic repository in Mochovce is built for disposal of short lived low and intermediate level waste. Next

  11. Nanomaterial Case Studies: Nanoscale Titanium Dioxide in Water Treatment and in Topical Sunscreen (Final)

    Science.gov (United States)

    EPA announced the availability of the final report, Nanomaterial Case Studies: Nanoscale Titanium Dioxide in Water Treatment and in Topical Sunscreen. This report is a starting point to determine what is known and what needs to be known about selected nanomaterials as par...

  12. Training of personnel

    International Nuclear Information System (INIS)

    1997-01-01

    Selected staffs (in the area of NPPs) are examined by the State Examining Committee established by Nuclear Regulatory Authority of the Slovak Republic (NRA SR's) chairman. The committee consists of representatives of NRA SR , Bohunice NPPs, Mochovce NPP, Research Institute of Nuclear Energy and experts from the Faculty of Electrical Engineering and Information Technology of the Slovak Technical University. The review of selected personnel of NPP V-1, V-2 and Mochovce NPP which passed exams in 1996 is given. NRA SR paid attention to the upgrading training process of individual categories of staff for V-1, V-2 and Mochovce NPPs, simulator training and training with computerized simulation system according to the United criteria of nuclear installation personnel training that started in 1992. During the year, an inspection was performed focused on examination of technical equipment of the simulator of Mochovce NPP, professional eligibility and overall preparation of simulator training including simulator software. Throughout the year launching works continued at the simulator with the deadline of commissioning to trial use operation in the first half of 1997

  13. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    International Nuclear Information System (INIS)

    Warner, C.L.

    1979-07-01

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described

  14. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Warner, C.L. (comp.)

    1979-07-01

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described.

  15. Slovak National Prize for Quality 2004

    International Nuclear Information System (INIS)

    Steflik, Marian

    2009-01-01

    Competition for the Slovak National Prize for Quality is a milestone in the history of the Mochovce NPP. The Mochovce NPP won the prize in 2004. The article describes in detail the preparatory efforts including not only technological issues but also various administrative challenges. The impacts of this achievement on the plant's subsequent development are also highlighted. (orig.)

  16. We should use nuclear power plants as good as possible

    International Nuclear Information System (INIS)

    Kaplanova, J.

    2004-01-01

    In this paper visit of Austrian journalist Christian Hunger (redactor of the Austrian broadcast OE1) on the Jaslovske Bohunice NPP and Mochovce NPP is described. Upgrade of the Jaslovske Bohunice NPP and finishing of a building of the Mochovce NPP as well as shut-down of the first and second blocks of the Jaslovske Bohunice NPP are discussed

  17. A treatment of the final-state interaction for photonuclear reactions

    International Nuclear Information System (INIS)

    Eden, J.A.; Thompson, M.N.

    1991-01-01

    The final state interaction is considered for the Gottfried factorized cross section. Numerical examples are presented for the 40 Ca(γ,pn) and 40 Ca(γ,n) reactions. The surface refraction process, allowing photonucleons to refract as they emerge from the nuclear potential well, cannot change the magnitude of the total cross section, but may redistribute the strength in the angular dependence of the differential cross section. The absorption process accounts for the loss of photonucleons as a result of inelastic collisions while escaping the nucleus. The surface refraction correction is calculated in a plane-wave Born approximation and the absorption correction is presented as a simple development of earlier phenomenological treatments. 12 refs., 7 figs

  18. Evaluation of doses during the handling and transport of radioactive wastes containers

    International Nuclear Information System (INIS)

    Kubik, I.; Kusovska, Z.; Hanusik, V.; Mrskova, A.; Kapisovsky, V.

    2000-01-01

    Radioactive waste products from the nuclear power plants (NPPs) must be isolated from contact with people for very long period of time. Low and intermediate-level waste will be disposed of in Slovakia in specially licensed Regional disposal facility which is located near the NPP Mochovce site. Radioactive waste accumulated in the Jaslovsk. Bohunice site, during the decommissioning process of the NPP A-1 and arising from the NPP V-1 and NPP V-2 operation, will be processed and shipped in standard concrete containers to the Mochovce Regional disposal facility. The treatment centre was build at the NPP Jaslovsk? Bohunice site which is in the trial operation now. It is supposed that radioactive waste containers will be transported by train from the treatment centre Jaslovsk? Bohunice to the site of Radioactive Waste Repository at Mochovce and by truck in the area of repository. To estimate the occupational radiation exposure during the transport the calculations of dose rates from the containers are necessary. The national regulations allow low level of radiation to emanate from the casks and containers. The maximum permissible volume radioactivity of wastes inside the container is limited in such a way that irradiation level should not exceed 2 mGy/h for the contact irradiation level and 0,1 mGy/h at 2-meter distance. MicroShield code was used to analyse shielding and assessing exposure from gamma radiation of containers to people. A radioactive source was conservatively modelled by homogenous mixture of radionuclides with concrete. Standard rectangular volume source and shield geometry is used in model calculations. The activities of the personnel during the transport and storage of containers are analysed and results of the evaluation of external dose rates and effective doses are described. (author)

  19. National Report

    International Nuclear Information System (INIS)

    Lipar, M.

    2001-01-01

    Power production in Slovak Republic is presented. The safety at the NPPs Bohunice V-1, V-2 and Mochovce is discussed. The events - Automatic Reactor Scram at Bohunice 1 and Power Reduction - Home Load at Bohunice 2 due to short circuit in the external grid on 22 May 2001 and Manual Reactor Scram at Mochovce 2 NPP due to Loss of Offsite Power on 30 May 2001 are described

  20. Final height after gonadotrophin releasing hormone agonist treatment for central precocious puberty : The Dutch experience

    NARCIS (Netherlands)

    Mul, D; Oostdijk, W; Otten, BJ; Rouwe, C; Jansen, M; Delemarre-van de Waal, HA; Waelkens, JJJ; Drop, SLS

    Final height (FH) data of 96 children (87 girls) treated with GnRH agonist for central precocious puberty were studied. In girls mean FH exceeded initial height prediction by 7.4 (5.7) cm (p <0.001); FH was significantly lower than target height, but still in the genetic target range. When treatment

  1. Report on the evaluation under the Act No 24/2006 of Coll. Environmental Impact Assessment Law Extension of National Radioactive Waste Repository in Mochovce for disposal low-level radioactive waste and construction of very low-level radioactive waste repository; Sprava o hodnoteni v zmysle zakona NR SR c.24/2006 o posudzovani vplyvov na ZP. Rozsirenie RU RAO v Mochovciach pre ukladanie NSAO a vybudovanie uloziska pre VNAO

    Energy Technology Data Exchange (ETDEWEB)

    Hanusik, V; Moravek, J; Kusovska, Z [VUJE, a.s., 91864 Trnava (Slovakia)

    2011-11-30

    The report elaborated assessment of the environmental impact of extension of the National Radioactive Waste Repository in Mochovce for disposal of low and intermediate level radioactive wastes. Within this repository also the premises for very low level radioactive waste deposition should be built. The assessment report was prepared according to the Act no. 24/2006 Coll, as amended 'On the assessment of environmental impacts' Annex No. 11 upon The scope of assessment issued by the competent authority on the basis of assessment of Intent for this action. The report was prepared in VUJE, Inc. Trnava for Nuclear and Decommissioning Company, Inc. Bratislava (JAVYS).

  2. Change in contrast enhancement of HCC on 1-month follow-up CT after local radiotherapy: An early predictor of final treatment response

    International Nuclear Information System (INIS)

    Kim, Eun Young; Choi, Dongil; Lim, Do Hoon; Lee, Won Jae; Yoo, Byung Chul; Paik, Seung Woon

    2009-01-01

    Background: The purpose of this study was to evaluate the change in contrast enhancement of HCC on 1-month follow-up CT after local radiotherapy (RT) as an early predictor of final treatment response. Materials: Fifty patients who underwent local RT for HCCs had both pre-RT and post-RT CT scans including 1-month follow-up CT. We assessed the final treatment response by using the change in maximal tumor size on 6-12-month follow-up CT scan after RT. We also evaluated the change in tumor enhancement between pre-RT and 1-month follow-up CT scans. Results: A final treatment response was achieved in 27 (54%) of 50 patients, who showed either a complete response (n = 11) or a partial response (n = 16). Compared with non-responsive patients (n = 23), responsive patients showed a significant decrease in tumor enhancement on 1-month follow-up CT after RT in both objective and subjective analyses (each P < 0.001). Conclusion: The change in contrast enhancement of HCC seen on the 1-month follow-up CT in patients after local RT may be used as an early predictor of final treatment response.

  3. Nuclear installations in Slovakia accords to the convention definition

    International Nuclear Information System (INIS)

    1998-01-01

    In this part the nuclear power plants Bohunice - Units V-1 and V-2 and NPP Mochovce (description of units, safety reports and safety improvement programs) are described. Description of Bohunice A-1, history and current status of the NPP A-1 and NPP decommissioning program are included. In next parts interim spent fuel storage, technologies of Raw processing and treatment, and treated and solid Raw storage sites are described

  4. Comparative analysis of rationale used by dentists and patient for final esthetic outcome of dental treatment.

    Science.gov (United States)

    Reddy, S Varalakshmi; Madineni, Praveen Kumar; Sudheer, A; Gujjarlapudi, Manmohan Choudary; Sreedevi, B; Reddy, Patelu Sunil Kumar

    2013-05-01

    To compare and evaluate the perceptions of esthetics among dentists and patients regarding the final esthetic outcome of a dental treatment. Esthetics is a matter of perception and is associated with the way different people look at an object. What constitutes esthetic for a particular person may not be acceptable for another. Hence it is subjective in nature. This becomes more obvious during the post-treatment evaluation of esthetics by dentist and the concerned patient. Opinion seldom matches. Hence, the study is a necessary part of the process of understanding the mind of dentist and patient regarding what constitutes esthetics. A survey has been conducted by means of a questionnaire consisting of 10 questions, on two groups of people. First group consists of 100 dentists picked at random in Kanyakumari district of Tamil Nadu, India. Second group consisted of 100 patients who required complete denture prosthesis. The second group was divided into two subgroups A and B. Subgroup A consisting of 50 men and subgroup B consisting of 50 women. In each subgroup 25 patients were selected in age group of 40 to 50 and 25 patients were selected in the age group of 50 to 60. The questionnaire was given to both the groups and asked to fill up, which was then statistically analyzed to look for patterns of thought process among them. Results were subjected to statistical analysis by Student's t-test. Perceptions of esthetics differs from dentist who is educated regarding esthetic principles of treatment and a patient who is not subjected to such education. Since, the questions were formulated such that patients could better understand the underlying problem, the final outcome of survey is a proof that dentists need to take into account what the patient regards as esthetics in order to provide a satisfactory treatment. CLINICAL AND ACADEMIC SIGNIFICANCE: The current study helps the dentist to better educate the patient regarding esthetics so that patient appreciates the final

  5. Liquid waste treatment system. Final report

    International Nuclear Information System (INIS)

    Baker, M.N.; Houston, H.M.

    1999-01-01

    Pretreatment of high-level liquid radioactive waste (HLW) at the West Valley Demonstration Project (WVDP) involved three distinct processing operations: decontamination of liquid HLW in the Supernatant Treatment System (STS); volume reduction of decontaminated liquid in the Liquid Waste Treatment System (LWTS); and encapsulation of resulting concentrates into an approved cement waste form in the Cement Solidification System (CSS). Together, these systems and operations made up the Integrated Radwaste Treatment System (IRTS)

  6. Irradiation temperature measurement of the reactor pressure vessel surveillance specimen in the programmes of radiation degradation monitoring

    International Nuclear Information System (INIS)

    Kupca, L.; Stanc, S.; Simor, S.

    2001-01-01

    The information's about the special system of irradiation temperature measurement, used for reactor pressure vessel surveillance specimen, which are placed in reactor thermal shielding canals are presented in the paper. The system was designed and realized in the frame of Extended Surveillance Specimen Programme for NPP V-2 Jaslovske Bohunice and Modern Surveillance Specimen Programme for NPP Mochovce. Base design aspects, technical parameters of realization and results of measurement on the two units in Bohunice and Mochovce NPPs are presented too. (Authors)

  7. Ukraine is nuclear Great Power

    International Nuclear Information System (INIS)

    Svolik, S.

    2005-01-01

    In this paper the interview with Mr. Jaroslav Holubec - the Director of the Mochovce NPP is published. MR. Jaroslav Holubec with Mr. Stefan Niznan - the Director of the 3 r d and 4 th blocks of the Mochovce NPP - took part in opening commissioning of blocks on the Rovno NPP and Khmelnitskaya NPP, both with installed reactors 1,000 MW. Development of nuclear energetics in the Ukraine is discussed. The share of nuclear energy on the production of the Ukraine constitutes 42 %

  8. VUJE capabilities for participation in the development of Slovak power sector

    International Nuclear Information System (INIS)

    Liska, P.

    2004-01-01

    In this presentation author deals with VUJE Trnava, Inc. capabilities for participation in the development of Slovak power sector. It is concluded that VUJE supports the completion of Mochovce units 3 and 4 as the most effective option; VUJE calls of the Slovak government to revive negotiations on a revision of a commitment to close V1 units Bohunice NPP in 2006 or 2008 respectively; VUJE is prepared to be an important participant in supply system for Mochovce NPP Units 3 and 4

  9. Low level radioactive waste disposal

    International Nuclear Information System (INIS)

    Balaz, J.; Chren, O.

    2015-01-01

    The Mochovce National Radwaste Repository is a near surface multi-barrier disposal facility for disposal of processed low and very low level radioactive wastes (radwastes) resulting from the operation and decommissioning of nuclear facilities situated in the territory of the Slovak Republic and from research institutes, laboratories, hospitals and other institutions (institutional RAW) which are in compliance with the acceptance criteria. The basic safety requirement of the Repository is to avoid a radioactive release to the environment during its operation and institutional inspection. This commitment is covered by the protection barrier system. The method of solution designed and implemented at the Repository construction complies with the latest knowledge and practice of the repository developments all over the world and meets requirements for the safe radwaste disposal with minimum environmental consequences. All wastes are solidified and have to meet the acceptance criteria before disposal into the Repository. They are processed and treated at the Bohunice RAW Treatment Centre and Liquid RAW Final Treatment Facility at Mochovce. The disposal facility for low level radwastes consists of two double-rows of reinforced concrete vaults with total capacity 7 200 fibre reinforced concrete containers (FCCs) with RAW. One double-row contains 40 The operation of the Repository was started in year 2001 and after ten years, in 2011 was conducted the periodic assessment of nuclear safety with positive results. Till the end of year 2014 was disposed to the Repository 11 514 m 3 RAW. The analysis of total RAW production from operation and decommissioning of all nuclear installation in SR, which has been carried out in frame of the BIDSF project C9.1, has showed that the total volume estimation of conditioned waste is 108 thousand m 3 of which 45.5 % are low level waste (LLW) and 54,5 % very low level waste (VLLW). On the base of this fact there is the need to build 7

  10. Chapter 9. Personnel qualification and training

    International Nuclear Information System (INIS)

    2001-01-01

    The overall training system and the development of projects for training of all categories of NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce staff were the subject of Nuclear Regulatory Authority of the Slovak Republic (UJD) attention. During 2000, the following inspections were carried out on nuclear personnel training: (a) NPP Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff ; (b) NPP Mochovce: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; an inspection focused on verifying the simulator aided training; an inspection focused on checking the preparedness of NPP Mochovce operation and technical personnel for NPP Mochovce Unit 2 operation; (c) Technology for treatment and conditioning of radioactive waste Bohunice (BSC): an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff; VUJE Trnava: verification of technical equipment and professional skills of VUJE Trnava staff and tasks arising out of the 'Authorisation on nuclear installation staff training'. Examinations of selected personnel were scheduled according to the plan of examining committee meetings. For each examined person written tests are generated by the computer from the database of test questions at the Training Centre of VUJE Trnava for individual positions - categories of selected staff of NPP V-1 and NPP V-2 Bohunice and NPP Mochovce so that the examination questions both in written and oral part equally cover individual facilities and regimes of operation of NPP. The database is continuously updated, thereby containing new questions resulting from the recent changes carried out at NPPs. A part of the examination in case of promotion to a higher position is the practical part, which is conducted under

  11. Assessment of spent WWER-440 fuel performance under long-term storage conditions

    Energy Technology Data Exchange (ETDEWEB)

    Kupca, L [VUJE Inc. (Slovakia)

    2012-07-01

    In the Slovak Republic are under operation 6 units (4 in the Jaslovske Bohunice site, and 2 in the Mochovce), 2 units are under construction in Mochovce site. All units are WWER-440 type. The fresh fuel is imported from the Russian Federation. The spent fuel assemblies are stored in wet conditions in Bohunice Interim Storage Spent Fuel Facility (SFIS). By 15 July 2008, there were 8413 assemblies in SFIS. The objectives are: 1) Wet AR storage of spent fuel from the NPP Bohunice and Mochovce: Surveillance of conditions for spent fuel storage in the at-reactor (AR) storage pools of both NPP's (characteristics of pool water, corrosion product data); Visual control of storage pool components; Evaluation of storage conditions with respect to long-term stability (corrosion of fuel cladding, structural materials); 2) Wet SFIS storage at Bohunice: Measurement of spent fuel conditions during the long-term wet storage, activity data in the storage casks and amount of crud; Surveillance program for SFIS structural materials.

  12. Evaluation of effects of phenol recovery on biooxidation and tertiary treatment of SRC-I wastewater. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, J.W.; Watt, J.C.; Cowan, W.F.; Schuyler, S.E.

    1983-09-01

    Addition of phenol recovery to the wastewater treatment scheme in the Baseline Design for the SRC-I Demonstration Plant was evaluated as a major post-Baseline effort. Phenol recovery affects many downstream processes, but this study was designed to assess primarily its effects on biooxidation and subsequent tertiary treatment. Two parallel treatment schemes were set up, one to treat dephenolated wastewaters and the other for processed nondephenolated wastewaters, a simulation of the Baseline Design. The study focused on comparisons of five areas: effluent quality; system stability; the need for continuous, high-dose powdered activated carbon (PAC) augmentation to the bioreactor; minimum bioreactor hydraulic residence time (HRT); and tertiary treatment requirements. The results show that phenol recovery improves the quality of the bioreactor effluent in terms of residual organics and color. With phenol recovery, PAC augmentation is not required; without phenol recovery, PAC is needed to produce a comparable effluent. Dephenolization also enhances the stability of biooxidation, and reduces the minimum HRT required. With tertiary treatment, both schemes can meet the effluent concentrations published in the SRC-I Final Envivornmental Impact Statement, as well as the anticipated effluent limits. However, phenol recovery does provide a wider safety margin and could eliminate the need for some of the tertiary treatment steps. Based solely on the technical merits observed in this study, phenol recovery is recommended. The final selection should, however, also consider economic tradeoffs and results of other studies such as toxicology testing of the effluents. 34 references, 30 figures and 26 tables.

  13. 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

  14. Report of influence on environment 2006

    International Nuclear Information System (INIS)

    2007-01-01

    The joint stock company Jadrova a vyradovacia spolocnost, a. s. (JAVYS) has established in the Slovak power engineering industry just recently. According to transaction documents about privatisation of the joint stock company Slovenske elektrarne, a. s. (SE), on 6-th July 2005 there was established state-owned organisation GovCo from which VYZ plants and V1 power plant were separated. Since 1-st April 2006, the company GovCo assumed responsibility for JE V1 plant, decommissioning of nuclear facilities in Slovakia, processing, treatment and storage of radioactive waste and care for spent nuclear fuel. Seat of the company changed to operation from Jaslovske Bohunice and, on 7-th August, also the company's name changed to Jadrova vyradovacia spolocnost, a.s.. Since March 2007, the company's name is Jadrova a vyradovacia spolocnost, a. s. Starting position of the company in the Slovak power engineering sector developed from achieved results of long- term operation of plants of the company SE, a. s. - VYZ and EBO V1. Apart from operation of currently only one block of V1 nuclear power plant, the company carries out the first phase of the A1 nuclear power plant decommissioning project, operates radioactive waste processing centre in Bohunice (Bohunicke spracovatelske centrum radioaktivnych odpadov), bitumen and vitrification line of radioactive waste processing and fragmentation plant for metal radioactive waste. Currently, new facility - final processing of liquid radioactive waste in Mochovce is being put into operation. This chain is crowned by safe storage of processed low and medium-active waste in Republic's Repository of Radioactive Waste (Republikove ulozisko RAO) in Mochovce. The company also operates spent nuclear fuel in-process store in Jaslovske Bohunice, which is resistant to seismic activity and compacted. This Report contains the results of monitoring of the environment in JAVYS, a.s. in 2006

  15. Project investigation and analysis of soil-structure interaction effects in seismic response of NPPs EBO, EMO, Slovakia. Final report

    International Nuclear Information System (INIS)

    Juhasova, E.

    1999-01-01

    The work described in this report was devoted to investigation of expected seismic response of the structures of WWER-440/213 type NPPs, namely Mochovce and Bohunice. Special attention was devoted to the properties of subsoil materials and the transfer of seismic waves from the bedrock to the foundation structures. Theoretical background was elaborated and discussed for wave propagation of surface waves. Alternative procedure was derived for non-linear media accounting for complex modulus theory. Material characteristics of subsoils were investigated for both NPPs. The obtained results were used as a basis for forecasting and calculation of expected seismic response when the time history records from Paks explosion were used an input. It was pointed out that the used procedure, together with previous calculation of subsoil transfer characteristics completed well the comparison with experimental results

  16. Mechanical properties of nickel-titanium archwire used in the final treatment phase of Tip-Edge Plus technique: an in vitro study.

    Science.gov (United States)

    Shen, Xiao; Sun, Xin-hua; Tian, Hua; Zhang, Chun-bo; Yan, Kuo; Guo, Yong-liang

    2013-01-01

    As the only active component in final treatment phase of Tip-Edge Plus technique, the activation of nickel-titanium orthodontic archwires is one of the factors that affect the torque expression. It is necessary to evaluate the mechanical properties of the nickel-titanium wire used in the final treatment phase in simulated oral environments to forecast the treatment outcomes. The mechanical properties of 171 thermal nickel-titanium wires of 0.35 mm (0.014-in) in diameters with different deflection of 40 mm in length were investigated with three-point bending test. The samples were divided into 2 groups: as-received and bended groups. In the bended group, samples were divided into 7 subgroups according to the amounts of deflection and named by the canine angulations (-25°, -19°, -13°, -7°, -1°, +5°, +11°). The deflection of wires was made by inserting the wires into the deep tunnel of Tip-Edge Plus brackets positioned in plaster casts with different canine angulations to mimic the use of nickel-titanium wires in the final treatment phase. Immersed the bended group in artificial saliva (pH 6.8) and preserved at 37.0°C. Eight durations of incubation were tested: 1 to 8 weeks. Three analogous samples of each group and subgroups were tested per week. Stiffness (YS:E) and the load-deflection characteristics of unloading plateau section were obtained. Significant changes in specific mechanical properties were observed in long-term immersed and large deflected wires compared with as-received groups. Both immersion time and deflection affected the mechanical properties of wires in the simulated oral environment, and the two factors had synergistic effect. In groups -25°, -19° and -13°, stiffness (YS:E) increased then decreased and average plateau force and ratio of variance decreased then increased correspondingly at specific time. In the final treatment phase of Tip-Edge Plus technique, the mechanical properties of nickel-titanium wire are associated with the

  17. Finalizing a measurement framework for the burden of treatment in complex patients with chronic conditions

    Directory of Open Access Journals (Sweden)

    Eton DT

    2015-03-01

    Full Text Available David T Eton,1,2 Jennifer L Ridgeway,1,2 Jason S Egginton,1,2 Kristina Tiedje,3 Mark Linzer,4,5 Deborah H Boehm,4 Sara Poplau,6 Djenane Ramalho de Oliveira,7 Laura Odell,8 Victor M Montori,1,9 Carl R May,10 Roger T Anderson11 1Division of Health Care Policy and Research, Department of Health Sciences Research, Mayo Clinic, Rochester, MN, USA; 2Robert D and Patricia E Kern Center for the Science of Health Care Delivery, Mayo Clinic, Rochester, MN, USA; 3Department of Sociology and Anthropology, Université Lumière Lyon 2, Lyon, France; 4Division of General Internal Medicine, Hennepin County Medical Center, Minneapolis, MN, USA; 5University of Minnesota Medical School, University of Minnesota, Minneapolis, MN, USA; 6Minneapolis Medical Research Foundation, Minneapolis, MN, USA; 7Department of Social Pharmacy, Universidade Federal de Minas Gerais, Belo Horizonte, Minas Gerais, Brazil; 8Pharmacy Services, Mayo Clinic, Rochester, MN, USA; 9Knowledge and Evaluation Research Unit, Mayo Clinic, Rochester, MN, USA; 10Faculty of Health Sciences and NIHR CLAHRC Wessex, University of Southampton, Southampton, UK; 11School of Medicine, University of Virginia, Charlottesville, VA, USA Purpose: The workload of health care and its impact on patient functioning and well-being is known as treatment burden. The purpose of this study was to finalize a conceptual framework of treatment burden that will be used to inform a new patient-reported measure of this construct. Patients and methods: Semi-structured interviews were conducted with 50 chronically ill patients from a large academic medical center (n=32 and an urban safety-net hospital (n=18. We coded themes identifying treatment burden, with the themes harmonized through discussion between multiple coders. Four focus groups, each with five to eight participants with chronic illness, were subsequently held to confirm the thematic structure that emerged from the interviews. Results: Most interviewed patients (98

  18. Combined methods for liquid radioactive waste treatment. Final report of a co-ordinated research project 1997-2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-02-01

    The report contains 13 papers presented at the final research co-ordination meeting of the CRP. The subjects covered include processes and technologies for treatment and conditioning of liquid radioactive wastes. It quite often includes the application of several steps, such as filtration, precipitation, sorption, ion exchange, evaporation and/or membrane separation to meet the requirements both for the release of decontaminated effluents into the environment and the conditioning of waste concentrates for disposal. Combination of the processes and their consecutive or simultaneous application is also described. It results in an improved decontamination, waste volume reduction, safety and overall cost effectiveness in the treatment, conditioning and disposal of these wastes.

  19. Combined methods for liquid radioactive waste treatment. Final report of a co-ordinated research project 1997-2001

    International Nuclear Information System (INIS)

    2003-02-01

    The report contains 13 papers presented at the final research co-ordination meeting of the CRP. The subjects covered include processes and technologies for treatment and conditioning of liquid radioactive wastes. It quite often includes the application of several steps, such as filtration, precipitation, sorption, ion exchange, evaporation and/or membrane separation to meet the requirements both for the release of decontaminated effluents into the environment and the conditioning of waste concentrates for disposal. Combination of the processes and their consecutive or simultaneous application is also described. It results in an improved decontamination, waste volume reduction, safety and overall cost effectiveness in the treatment, conditioning and disposal of these wastes

  20. Slovenske elektrarne and the environment

    International Nuclear Information System (INIS)

    Mihaly, B.

    2003-01-01

    In this paper the environmental impact from Slovenske elektrarne is reviewed. The Mochovce Nuclear Power Plant has obtained as the first plant in the Slovak Republic - the International certificate in environmental management according the norm ISO 14001:1996 for production and supply of electric energy from NPP. The Certification was awarded by the certification company Det Norske Veritas Slovensko according to the Dutch accreditation the Raad voor Accredative. Mochovce NPP has obtained the Certificate after compliance of process requests and it is active for three years. After expiration of this period the certification process must be repeated

  1. The biggest investment in the history of Slovakia

    International Nuclear Information System (INIS)

    Anon

    2009-01-01

    On 11 June 2009 the General Director and Chairman of the Board of Directors of Slovenske elektrarne Paolo Ruzzini and the Prime Minister of the Slovak Republic Robert Fico announced the signature of contracts with the main suppliers for the completion of units 3 and 4 of Mochovce Nuclear Power Plant. Planned investment of Eur 2.775 billion by 2013 for the Mochovce completion is an important commitment for us and especially in this time, such investment can mitigate the impact of global slowdown in economic growth which impacts Slovakia but also other economies of the world. (author)

  2. A pilot study for the extraction and treatment of groundwater from a manufactured gas plant site. Final report

    International Nuclear Information System (INIS)

    1997-12-01

    This report describes a pilot study involving treatment of contaminated groundwater at a former manufactured gas plant site on the eastern seaboard of the US. The work was performed in order to provide the design basis for a full-scale groundwater extraction and treatment system at the site, as well as to develop a generic approach to selection of groundwater treatment sequences at other MGP sites. It included three main components: hydrogeologic investigations, bench-scale treatability studies, and pilot-scale treatability studies. Technologies evaluated in bench-scale work included gravity settling, filtration, and dissolved air flotation (DAF) for primary treatment of nonaqueous phase materials; biological degradation, air stripping, and carbon adsorption for secondary treatment of dissolved organics; and carbon adsorption as tertiary treatment of remaining dissolved contaminants. Pilot-scale studies focused on collecting system performance data fore three distinct levels of contamination. Two treatment trains were evaluated. One consisted of DAF, fluidized-bed biotreatment, and filtration plus carbon adsorption; the other used the same steps except to substitute air stripping for fluidized bed treatment. The final effluents produced by both treatment sequences were similar and demonstrated complete treatment of the groundwater. Besides detailing system design and performance for the treatability studies, the report includes an analysis of groundwater treatment applications to MGP sites in general, including a discussion of capital and operating costs

  3. Nuclear Research Institute Rez view

    International Nuclear Information System (INIS)

    Biza, K.; Pazdera, F.; Vasa, I.; Zdarek, J.

    2004-01-01

    In this presentation author deals with the present state and perspectives of nuclear energy in the Czech Republic and in the Slovak Republic. It is concluded that lifetime extension and finalization of Mochovce NPP Units 3 and 4 is the cheapest solution for base load production of electricity and is in line with the European union energy challenges: - decrease of carbon dioxide emissions; dependence on energy sources from politically unstable regions; decrease import dependence on energy sources. Nuclear energy is one of important sources for long term sustainability in energy. GEN IV is successful with meet the new requirements after 2025. We should participate on this long term development effort

  4. Living near a nuclear power station

    International Nuclear Information System (INIS)

    Marcan, P.; Slovak, K.

    2007-01-01

    The need to expand nuclear power and its advantages are discussed publicly nearly each week. According to politicians and the nuclear lobby investing tens of billions Sk at Mochovce will bring Slovakia the often cited 'independence and energy self-sufficiency'. It will also mean profit for Slovenske elektrarne and the company's shareholders - the state and Italian company, Enel. In addition to the lively discussion on the pros and cons of nuclear energy, TREND was also interested in the living conditions around the concrete and strictly guarded, potentially dangerous plants and in the opinion of the people most affected by Mochovce and Jaslovske Bohunice on expansion of the existing and the building of new nuclear power plants. The construction of nuclear powers stations in these regions was not only about new jobs. The state 'prescribed' iodine pills and did not allow any construction in the region and, in the case of Mochovce, ordered the complete demolition of a village. The only thing that remained from Mochovce village was the church. 'And when it was found that the power plant would not reach it, it was even given a new roof. Former inhabitants, especially the older ones that had problems accepting the evacuation, used to visit it often,' explained Jan Foldy, the head of the local municipality in Kalna nad Hronom. After many years, life in the neighbouring villages is not bad. Their budgets are overflowing and so they can afford to spoil their inhabitants with free cable TV and high standard sport facilities, which should partly compensate for the fact that the people are living so close to a nuclear facility. (authors)

  5. Electrochemical Processes for In-Situ Treatment of Contaminated Soils - Final Report - 09/15/1996 - 01/31/2001

    Energy Technology Data Exchange (ETDEWEB)

    Huang, Chin-Pao

    2001-05-31

    This project will study electrochemical processes for the in situ treatment of soils contaminated by mixed wastes, i.e., organic and inorganic. Soil samples collected form selected DOE waste sites will be characterized for specific organic and metal contaminants and hydraulic permeability. The soil samples are then subject to desorption experiments under various physical-chemical conditions such as pH and the presence of surfactants. Batch electro-osmosis experiments will be conducted to study the transport of contaminants in the soil-water systems. Organic contaminants that are released from the soil substrate will be treated by an advanced oxidation process, i.e., electron-Fantan. Finally, laboratory reactor integrating the elector-osmosis and elector-Fantan processes will be used to study the treatment of contaminated soil in situ.

  6. The conference hybrid control room

    International Nuclear Information System (INIS)

    Gieci, A.; Caucik, J.; Macko, J.

    2008-01-01

    An original concept of a hybrid control room was developed for the Mochovce-3 and Mochovce-4 reactor units which are under construction. The basic idea underlying the concept is that the control room should be a main working place for the operators (reactor operator and turbine operator) and for the shift supervisor, designed as a comprehensive unit desk shaped so that all members of the control room crew are in a face-to-face contact constantly. The main desk consists of three clearly identified areas serving the operators and the unit supervisor as their main working places. A soft control system is installed at the main working places. A separate safety-related working place, designed as a panel with classical instrumentations at the conference hybrid control room, is provided in case of abnormal conditions or emergency situation. Principles of ergonomics and cognitive engineering were taken into account when designing the new conference hybrid control room for the Mochovce-3 and -4 reactor units. The sizes, propositions, shapes and disposition of the equipment at the control room have been created and verified by using virtual reality tools. (orig.)

  7. Safety improvement programme of WWER 440/230 units in Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Tomek, J.

    2000-01-01

    A brief overview is given of the power sources in Slovakia which include 6 operational reactor units (4 at Jaslovske Bohunice and 2 at Mochovce) and 2 units under construction (at Mochovce). The efforts undertaken in the past 10 years and aimed at upgrading the nuclear safety of the two older (V-230 Soviet type) units at Bohunice are highlighted. The relevant regulatory decisions are dealt with and the measures already carried out are listed. Also characterized are several IAEA international safety assessment missions and safety-aimed meetings which took place in 1998 and 1999 and are of concern to the older Bohunice units. (A.K.)

  8. Radioactive waste and the back part of fuel cycle of nuclear installations in Slovakia

    International Nuclear Information System (INIS)

    Koprda, V.

    2004-01-01

    This article is devoted to radioactive waste (RAW) management, an integrated system starting with collection and sorting of RAW through its storage, treatment, conditioning, handling and transport up to its disposal. Some notes will touch also the near surface depository of low level and intermediate level radioactive waste in Mochovce, and the long-term storage of waste improper for such type of disposal, and also some words will be addressed to the development and research of a deep geological depository for disposal spent fuel from nuclear power plant and long-lived radioactive waste. (author)

  9. Management, treatment and final disposal of solid hazardous hospital wastes

    International Nuclear Information System (INIS)

    Sebiani Serrano, T.

    2000-01-01

    Medical Waste is characterized by its high risk to human health and the environment. The main risk is biological, due to the large amount of biologically contaminated materials present in such waste. However, this does not mean that the chemical and radioactive wastes are less harmful just because they represent a smaller part of the total waste. Hazardous wastes from hospitals can be divided in 3 main categories: Solid Hazardous Hospital Wastes (S.H.H.W.), Liquid Hazardous Hospital Wastes (L.H.H.W.) and Gaseous Hazardous Hospital Wastes (G.H.H.W.) Most gaseous and liquid hazardous wastes are discharged to the environment without treatment. Since this inappropriate disposal practice, however, is not visible to society, there is no societal reaction to such problem. On the contrary, hazardous solid wastes (S.H.H.W.) are visible to society and create worries in the population. As a result, social and political pressures arise, asking for solutions to the disposal problems of such wastes. In response to such pressures and legislation approved by Costa Rica on waste handling and disposal, the Caja Costarricense de Seguro Social developed a plan for the handling, treatment, and disposal of hazardous solid wastes at the hospitals and clinics of its system. The objective of the program is to reduce the risk to society of such wastes. In this thesis a cost-effectiveness analysis was conducted to determine the minimum cost at which it is possible to reach a maximum level of reduction in hazardous wastes, transferring to the environment the least possible volume of solid hazardous wastes, and therefore, reducing risk to a minimum. It was found that at the National Children's Hospital the internal handling of hazard solid wastes is conducted with a high level of effectiveness. However, once out of the hospital area, the handling is not effective, because hazardous and common wastes are all mixed together creating a larger amount of S.H.H.W. and reducing the final efficiency

  10. Systems study 'Alternative Entsorgung'. Final report. Technical annex 6

    International Nuclear Information System (INIS)

    1984-08-01

    In the conditioning plant, fuel elements which have been stored for ten years are loaded into transport containers, unloaded, identified and welded into a dry storage box. The dry store barrel is introduced into a final storage container, which, after being closed, is packed in lost shielding. This so-called final storage barrel is finally placed in a transport container and leaves the conditioning plant in this form by rail for transport to the final storage mine. The fuel element method of treatment 'packing of three complete fuel elements' was used as the reference process. In addition, the method of treatment 'fuel elements dismantled into fuel rods' was also examined. The handling of fuel elements and secondary waste treatment in the reference process are described in detail. (orig./HP) [de

  11. Chapter No.6. Radioactive waste (RAW)

    International Nuclear Information System (INIS)

    2002-01-01

    UJD SR supervises all phases of radioactive waste management at nuclear installations and final phases of institutional radioactive waste management. Total concentrates generation and minimisation trends during recent period (for NPP V1, NPP V2 Bohunice and NPP Mochovce) as well as increasing of their conditioning are presented. So nearly 8000 m3 of concentrates were stored at the end of year 2001, representing 75.5% of storage capacity at Bohunice site. Total amount of solid waste stored at VVER NPPs reached 3500 m3 at December 2001. The solid waste storage capacity of NPP V1 Bohunice is spent. NPP A1 Bohunice with a heterogeneous reactor using natural uranium, moderated by heavy water and cooled by CO 2 had been in operation for 4 years. It was finally shut down in February 1977 after an accident (INES level 4). Main activities in 2001 were focused on an increasing of radwaste management safety by the waste solidification or storage improvement, especially in the case of inorganic spent fuel coolant. The total solid radwaste inventory in 2001 (including filters) represents cca 700 m3 of soft and pre-pressed not sorted waste, 700 m3 of sorted waste, more then 1 000 t of scrap and next 260 m3 of scrap in drums. The total volume of contaminated soils and concrete is more than 7200 m3. The volume of solid radwaste depends on the extent of dismantling works and following treatment, conditioning and disposal. The total volume is also increased by products of bituminization and cementation facilities in drums stored before conditioning at NPP A1 Bohunice site. The facilities focused only on treatment of radwaste from NPP A1 decommissioning are operated by the same operator as a part of this decommissioned nuclear installation. Experimental and research treatment plants are operated by VUJE. A facility for the treatment and conditioning of operational liquid radwaste from NPP Mochovce is under preparation and a start of construction is foreseen in 2004. The nuclear

  12. Tax treatment of cafeteria plans. Internal Revenue Service (IRS), Treasury. Final regulations.

    Science.gov (United States)

    2000-03-23

    This document contains final regulations relating to section 125 cafeteria plans. The final regulations clarify the circumstances under which a section 125 cafeteria plan election may be changed. The final regulations permit an employer to allow a section 125 cafeteria plan participant to revoke an existing election and make a new election during a period of coverage for accident or health coverage or group-term life insurance coverage.

  13. Comparative study of the methods used for treatment and final disposal of sewage sludge in European countries.

    Science.gov (United States)

    Kelessidis, Alexandros; Stasinakis, Athanasios S

    2012-06-01

    Municipal wastewater treatment results to the production of large quantities of sewage sludge, which requires proper and environmentally accepted management before final disposal. In European Union, sludge management remains an open and challenging issue for the Member States as the relative European legislation is fragmentary and quite old, while the published data concerning sludge treatment and disposal in different European countries are often incomplete and inhomogeneous. The main objective of the current study was to outline the current situation and discuss future perspectives for sludge treatment and disposal in EU countries. According to the results, specific sludge production is differentiated significantly between European countries, ranging from 0.1 kg per population equivalent (p.e.) and year (Malta) to 30.8 kg per p.e. and year (Austria). More stringent legislations comparing to European Directive 86/278/EC have been adopted for sludge disposal in soil by several European countries, setting lower limit values for heavy metals as well as limit values for pathogens and organic micropollutants. A great variety of sludge treatment technologies are used in EU countries, while differences are observed between Member States. Anaerobic and aerobic digestion seems to be the most popular stabilization methods, applying in 24 and 20 countries, respectively. Mechanical sludge dewatering is preferred comparing to the use of drying beds, while thermal drying is mainly applied in EU-15 countries (old Member States) and especially in Germany, Italy, France and UK. Regarding sludge final disposal, sludge reuse (including direct agricultural application and composting) seems to be the predominant choice for sludge management in EU-15 (53% of produced sludge), following by incineration (21% of produced sludge). On the other hand, the most common disposal method in EU-12 countries (new Member States that joined EU after 2004) is still landfilling. Due to the obligations

  14. Safety of nuclear power plants in Slovak Republic in the context of integration into the European Union

    International Nuclear Information System (INIS)

    Pillar, V.

    2001-01-01

    A review of the construction and operation of nuclear power plants in Slovak Republic which belong within Slovenske Elektrarne is made. Since 1993 with the applying of the Least Cost Planning Methods and Financial Feasibility Analysis the optimal variant, considering construction completion of the two units at Mochovce NPP, has been adopted and a project for safety enhancement has been implemented. Some changes have been made in siting project in order to meet the seismic requirements, following by change of the control system design and supplier. The most important result of the safety enhancement program, important not only for NPP Mochovce, but also for all NPPs of WWER 440/213 type, is the fact, that operability of containment with passive bubbler-condenser system for pressure suppression and its acceptability from safety point of view, has been fully confirmed. Results of safety enhancement program have been re-evaluated not only by International Atomic Energy Agency, but also by other international authorities and professional organisations with positive result. Especially significant is the conclusion of RISKAUDIT, which has carried out repeated evaluation of safety level of NPP Mochovce based on PHARE project and which is accepted by European Commission. A similar approach for enhancing the safety has been applied for the NPP V-1 units at Jaslovske Bohunice

  15. Final analysis of survival outcomes in the phase 3 FIRST trial of up-front treatment for multiple myeloma.

    Science.gov (United States)

    Facon, Thierry; Dimopoulos, Meletios A; Dispenzieri, Angela; Catalano, John V; Belch, Andrew; Cavo, Michele; Pinto, Antonello; Weisel, Katja; Ludwig, Heinz; Bahlis, Nizar J; Banos, Anne; Tiab, Mourad; Delforge, Michel; Cavenagh, Jamie D; Geraldes, Catarina; Lee, Je-Jung; Chen, Christine; Oriol, Albert; De La Rubia, Javier; White, Darrell; Binder, Daniel; Lu, Jin; Anderson, Kenneth C; Moreau, Philippe; Attal, Michel; Perrot, Aurore; Arnulf, Bertrand; Qiu, Lugui; Roussel, Murielle; Boyle, Eileen; Manier, Salomon; Mohty, Mohamad; Avet-Loiseau, Herve; Leleu, Xavier; Ervin-Haynes, Annette; Chen, Guang; Houck, Vanessa; Benboubker, Lotfi; Hulin, Cyrille

    2018-01-18

    This FIRST trial final analysis examined survival outcomes in patients with transplant-ineligible newly diagnosed multiple myeloma (NDMM) treated with lenalidomide and low-dose dexamethasone until disease progression (Rd continuous), Rd for 72 weeks (18 cycles; Rd18), or melphalan, prednisone, and thalidomide (MPT; 72 weeks). The primary endpoint was progression-free survival (PFS; primary comparison: Rd continuous vs MPT). Overall survival (OS) was a key secondary endpoint (final analysis prespecified ≥60 months' follow-up). Patients were randomized to Rd continuous (n = 535), Rd18 (n = 541), or MPT (n = 547). At a median follow-up of 67 months, PFS was significantly longer with Rd continuous vs MPT (hazard ratio [HR], 0.69; 95% confidence interval [CI], 0.59-0.79; P < .00001) and was similarly extended vs Rd18. Median OS was 10 months longer with Rd continuous vs MPT (59.1 vs 49.1 months; HR, 0.78; 95% CI, 0.67-0.92; P = .0023), and similar with Rd18 (62.3 months). In patients achieving complete or very good partial responses, Rd continuous had an ≈30-month longer median time to next treatment vs Rd18 (69.5 vs 39.9 months). Over half of all patients who received second-line treatment were given a bortezomib-based therapy. Second-line outcomes were improved in patients receiving bortezomib after Rd continuous and Rd18 vs after MPT. No new safety concerns, including risk for secondary malignancies, were observed. Treatment with Rd continuous significantly improved survival outcomes vs MPT, supporting Rd continuous as a standard of care for patients with transplant-ineligible NDMM. This trial was registered at www.clinicaltrials.gov as #NCT00689936 and EudraCT as 2007-004823-39. © 2018 by The American Society of Hematology.

  16. Irradiation as a phytosanitary treatment of food and agricultural commodities. Proceedings of a final research coordination meeting

    International Nuclear Information System (INIS)

    2004-11-01

    World trade in fresh horticultural produce, durables and ornamentals continues to grow. Accompanying increased trade in agricultural products is the increased risk for inadvertently transporting quarantine pests to countries or regions where they do not occur. Quarantined pests, including insects such as fruit flies, beetles, moths, scales, mealybugs, thrips, and mites, can seriously disrupt marketing of fresh agricultural products not only between countries, but also between geographical areas within countries (e.g. Florida to California; Hawaii to mainland USA; Queensland to Victoria, Australia; Okinawa to Japan) unless accepted postharvest quarantine treatments are available. Quarantine or phytosanitary treatments (such as fumigation, heat, cold or irradiation) disinfest host commodities of insect pests before they are moved through market channels to areas where the pests do not occur. Among the phytosanitary treatments, irradiation is recognized as a versatile treatment with broadspectrum activity against arthropod pests at dose levels that have minimal adverse effects on the quality of most commodities. The Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture, initiated in 1998 a Coordinated Research Project (CRP) on Irradiation as a Phytosanitary Treatment of Food and Agricultural Commodities. This CRP included 16 participants from Australia, Brazil, Chile, China (2), India, Islamic Republic of Iran, Japan, Malaysia, Philippines, Poland, Syrian Arab Republic, Thailand, Turkey and the USA (2). Research coordination meetings were held in Bangkok, Thailand, 29 March - 2 April 1999; Fresno, California, 13-16 November 2001; and Vienna, 2-4 November 2002. This CRP built on the achievements of two previous CRPs on Irradiation as a Quarantine Treatment of Fresh Fruits and Vegetables, (1986-1990), and Irradiation as a Quarantine Treatment of Mites, Nematodes and Insects other than Fruit Flies(1992-1997). This publication presents the research results

  17. Backfitting of Nuclear Power Plant Bohunice V1 in Slovakia

    International Nuclear Information System (INIS)

    Ferenc, M.

    1999-01-01

    Nuclear power plants in the Slovak Republic generate almost 55 % of electricity. The operating organization and the Nuclear Regulatory Authority of the Slovak Republic pay a great attention to safe and reliable operation of four units with VVER 440 reactors at Bohunices site and one in Mochovce side. Engineering and design organizations in cooperation with well known international companies prepare evaluation of safety conditions, safety analyses and projects for the implementation of modifications to upgrade the nuclear safety of the units in operation. A gradual safety upgrading (reconstruction) of the V-1 Bohunice plant has been in progress, a modernization of the V-2 Bohunice plant is being prepared. Simultaneously the commissioning of Unit 2 at the Mochovce plant is being implemented.(author)

  18. Present state of the design and realization of regional radioactive waste depositories and waste acceptance criteria for disposal. Soucasny stav reseni a realizace regionalnich ulozist RA odpadu a kriteria prijatelnosti techto odpadu k ukladani

    Energy Technology Data Exchange (ETDEWEB)

    Kortus, J [Chemoprojekt, Prague (Czechoslovakia)

    1988-06-01

    Surface type regional depositories for radioactive wastes from nuclear power plants are described in detail. The depository of the Mochovce nuclear power plant is located near the plant, that of the Dukovany nuclear power plant is directly on the premises of the plant. Particular attention is paid to the design of the monolithic reinforced concrete pits, draining of rainwater from their surface, draining of seeping rainwater from the pit environment by means of a double drainage system, and insulation of the pits against water. The construction of the Mochovce depository started in 1987; some experience gained from this activity is presented. The radioactive waste acceptance criteria for depositories of this kind, based on safety analysis, are given. (author). 2 figs.

  19. Present state of the design and realization of regional radioactive waste depositories and waste acceptance criteria for disposal

    International Nuclear Information System (INIS)

    Kortus, J.

    1988-01-01

    Surface type regional depositories for radioactive wastes from nuclear power plants are described in detail. The depository of the Mochovce nuclear power plant is located near the plant, that of the Dukovany nuclear power plant is directly on the premises of the plant. Particular attention is paid to the design of the monolithic reinforced concrete pits, draining of rainwater from their surface, draining of seeping rainwater from the pit environment by means of a double drainage system, and insulation of the pits against water. The construction of the Mochovce depository started in 1987; some experience gained from this activity is presented. The radioactive waste acceptance criteria for depositories of this kind, based on safety analysis, are given. (author). 2 figs

  20. Monitoring of covering model of the National radioactive waste repository

    International Nuclear Information System (INIS)

    Jezikova, M.

    2009-01-01

    The subject of this rigorous report is justification of cover model building at radioactive waste repository in Mochovce as a very important engineering barrier preventing significant release of radioactive substances into the environment and providing protection against ionizing radiation. This rigorous report includes a theoretical part, which describes radioactive waste characterization, radioactive waste management and summary of the preliminary activities prior to the building cover model, particularly involving the selection of appropriate variables and parameters and creation of monitoring plan during the long term monitoring for evaluation of this barrier in order to ensure minimization of any leak of radioactive substances from RAW. The next part includes evaluation of the values of parameters and variables to build cover model of RAW in Mochovce during 2006-2008 (author)

  1. Case law

    International Nuclear Information System (INIS)

    2014-01-01

    This section of the Bulletin brings together the texts of the following case laws: Canada: - Judgment of the Federal Court of Canada sending back to a joint review panel for reconsideration the environmental assessment of a proposed new nuclear power plant in Ontario. France : - Conseil d'etat, 24 March 2014 (Request No. 358882); - Conseil d'etat, 24 March 2014 (Request No. 362001). Slovak Republic: - Further developments in cases related to the challenge by Greenpeace Slovakia to the Mochovce nuclear power plant; - Developments in relation to the disclosure of information concerning the Mochovce nuclear power plant. United States: - Initial Decision of the Atomic Safety and Licensing Board Ruling in Favour of Nuclear Innovation North America, LLC (NINA) Regarding Foreign Ownership, Control or Domination

  2. Enel waiting for the state to act first

    International Nuclear Information System (INIS)

    Anon

    2005-01-01

    Enel will only answer the basic question whether Slovenske elektrarne will complete the reactors 3 and 4 in nuclear power plant in Mochovce next year. Initial analyses made by Enel indicate that the completion of Mochovce would cost over 60 billions Sk (1,54 billions EUR). Since National Property Fund has approved the strategic investment plan two more conditions have to be met before Enel can acquire Slovenske elektrarne. The first condition is that a part of the company assets has to taken over by state owned joint stock company GovCo. This regards reactor V-1 in nuclear power plant Jaslovske Bohunice that should be made ready for closure by end of 2008, damaged reactor A-1, nuclear equipment decommissioning and disposal unit VYZ and hydroelectric power plant in Gabcikovo. The other condition that still has to be fulfilled is passing of a new act on disposal of nuclear power generating equipment. The new act should distribute the fund's resources amongst the individual nuclear energy sources. M. Arcelli (regional manager of Enel for Slovakia) stresses that the money nuclear power station in Mochovce and V-2 earned and will earn during their time in operation will have to remain in the fund to cover their later liquidation i.e. should not be used on liquidation of reactors V-1 or A-1. (authors)

  3. Quality assurance

    International Nuclear Information System (INIS)

    1996-01-01

    The main efforts of Nuclear Regulatory Authority of the Slovak Republic (NRA SR) was focused on support of quality assurance programmes development at responsible organizations Bohunice V-1 and V-v and Mochovce NPPs and their inspection. Development of the level two documentation of a partial quality assurance programme for NPP operation continued at Mochovce NPP. Most of documentation has been submitted to NRA SR for comments and approval. NRA SR invited a mission of French experts to Mochovce NPP to review preparation and performance of internal audits that would be beneficial for improvement in this kind activities at the NPP. Bohunice NPP continued in development of a partial quality assurance programme for operation. The Quality Assurance Programme submitted to NRA SR for approval. Based on a request of Bohunice NPPs, NRA SR consulted the draft quality assurance programme developed by Siemens for stage of the 'Basic Design' of V-1 NPP upgrading. The programme had not been submitted for approval to NRA SR prior to completion of works by Siemens. Based on an internal audit that had been performed, corrective measures were proposed to meet requirements on review and approval of suppliers quality assurance programmes. Requirements related to the quality assurance at nuclear installations were prepared to be incorporated into principles of a act on peaceful use of nuclear power in Slovak Republic

  4. Chapter 9. Personnel qualification and training

    International Nuclear Information System (INIS)

    2000-01-01

    In 1999 the Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on the overall training system and on developing programmes for individual categories for NPP V-1 Bohunice, NPP V-2 Bohunice, NPP Mochovce and SE-VYZ. The fundamental theoretical and periodical training for both Bohunice and Mochovce NPPs personnel, simulator training for NPP Bohunice, and periodical simulator training for Bohunice personnel is carried out by the VUJE Training center in Trnava, whereas the simulator training and periodical training for NPP Mochovce is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues, a certificate on special professional skills of selected staff of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: (a)Shift manager for scientific start up with the right of manipulation; (b) Shift supervisor; (c) Unit supervisor; (d) Primary circuit operator; (e) Secondary circuit operator; (f) Reactor physicist; (g) Shift manager for scientific start up without the right of manipulation. Examination of selected personnel is described. Last year the examining committee held twelve session for oral theoretical examination. The number of licenses issued in 1999 and the total number of valid licenses is given.Conclusions from inspections carried out by UJD and inspections and tests carried out by the NPP operators in 1999, as well as results from operation and start up of nuclear units confirm that the standard of professional skills of the staff at nuclear installations a high standard of operational safety is being achieved on a permanent basis. Increasing the qualification of UJD staff was done in a form of training and courses scheduled in the plan of training for the staff for 1999. These training, composed of specialized qualification study, functional study, as well as study aimed at maintaining qualification. Training courses organized

  5. Integrated radwaste treatment system. Final report

    International Nuclear Information System (INIS)

    Baker, M.N.; Houston, H.M.

    1997-10-01

    In May 1988, the West Valley Demonstration Project (WVDP) began pretreating liquid high-level radioactive waste (HLW). This HLW was produced during spent nuclear fuel reprocessing operations that took place at the Western New York Nuclear Service Center from 1966 to 1972. Original reprocessing operations used plutonium/uranium extraction (PUREX) and thorium extraction (THOREX) processes to recover usable isotopes from spent nuclear fuel. The PUREX process produced a nitric acid-based waste stream, which was neutralized by adding sodium hydroxide to it. About two million liters of alkaline liquid HLW produced from PUREX neutralization were stored in an underground carbon steel tank identified as Tank 8D-2. The THOREX process, which was used to reprocess one core of mixed uranium-thorium fuel, resulted in about 31,000 liters of acidic waste. This acidic HLW was stored in an underground stainless steel tank identified as Tank 8D-4. Pretreatment of the HLW was carried out using the Integrated Radwaste Treatment System (IRTS), from May 1988 until May 1995. This system was designed to decontaminate the liquid HLW, remove salts from it, and encapsulate the resulting waste into a cement waste form that achieved US Nuclear Regulatory Commission (NRC) criteria for low-level waste (LLW) storage and disposal. A thorough discussion of IRTS operations, including all systems, subsystems, and components, is presented in US Department of Energy (DOE) Topical Report (DOE/NE/44139-68), Integrated Radwaste Treatment System Lessons Learned from 2 1/2 Years of Operation. This document also presents a detailed discussion of lessons learned during the first 2 1/2 years of IRTS operation. This report provides a general discussion of all phases of IRTS operation, and presents additional lessons learned during seven years of IRTS operation

  6. LESPRO - an expert system for the decision support in determination and suggestion of protective measures

    International Nuclear Information System (INIS)

    Bohunova, J.; Duranova, T.; Hatar, E.

    2000-01-01

    A prototype expert system for advising emergency procedures for nuclear regulatory authority has been developed. The expert system ESPRO is known as goal oriented rule-based knowledge system. The system is based on emergency procedures developed in VUJE Trnava, Inc. for use by the Emergency Response Centre (ERC) of the Slovak Nuclear Regulatory Authority (NRA). The operation interpretation module uses the knowledge base of emergency procedures for the evaluation of source term and determination and suggestion of protective measures which is represented in the form of a Petri net model. Its verification and validation was done on the basis of the results of two exercises: joint exercise of ERC staff with Slovak Army Headquarters and full scale Mochovce NPP emergency exercise with use of the Mochovce NPP simulator. (author)

  7. Protection of WWER type primary loops against extreme effects

    International Nuclear Information System (INIS)

    Podrouzek, J.; Rejent, B.

    1985-01-01

    Dynamic analyses of the WWER-440 primary loops for the Mochovce nuclear power plant showed that the unprotected primary loop is very soft with a first eigenfrequency of 0.38 Hz. Protection with amortisseurs and viscous shock absorbers was compared and the viscous shock absorber in all cases proved to be more suitable. GERB viscous absorbers will be installed at the Mochovce nuclear power plant. First calculations of the dynamic resistance of the WWER-1000 primary loops for the Temelin nuclear power plant to extreme events were also made. It was shown that the unprotected primary loop is rather soft with a first eigenfrequency of 0.9 Hz, or 0.6 Hz at the pressurizer branch. It will therefore be necessary to protect the primary loops with viscous shock absorbers. (Z.M.)

  8. Final report from VFL Technologies for the pilot-scale thermal treatment of Lower East Fork Poplar Creek floodplain soils. LEFPC appendices. Volume 6. Appendix VI-X

    International Nuclear Information System (INIS)

    1994-09-01

    This final report from VFL Technologies for the pilot-scale thermal treatment of lower East Fork Poplar Creek floodplain soils dated September 1994 contains LEFPC Appendices, Volume 6, Appendix VI - X. These appendices cover the following areas: chain of custody, miscellaneous process calculations (residence time and orifice plate calculations), waste management (mercury and radiation confirmatory testing before and after final verification run), health and safety (training, respirator fit test and radiation work permits), and transportation (soil receipt documentation)

  9. Future strategy of SE

    International Nuclear Information System (INIS)

    Arcelli, M.

    2006-01-01

    In this presentation author (General Director of Slovenske elektrarne, a. s.) presents structure and investment plans of SE. The feasibility study of construction of the blocks 3 and 4 of the Mochovce NPP is presented

  10. Final adult height in long-term growth hormone-treated achondroplasia patients.

    Science.gov (United States)

    Harada, Daisuke; Namba, Noriyuki; Hanioka, Yuki; Ueyama, Kaoru; Sakamoto, Natsuko; Nakano, Yukako; Izui, Masafumi; Nagamatsu, Yuiko; Kashiwagi, Hiroko; Yamamuro, Miho; Ishiura, Yoshihito; Ogitani, Ayako; Seino, Yoshiki

    2017-07-01

    The objective of this study was to evaluate the gain in final height of achondroplasia (ACH) patients with long-term growth hormone (GH) treatment. We analyzed medical data of 22 adult patients (8 males and 14 females) treated with GH at a dose of 0.05 mg/kg/day. Optionally, tibial lengthening (TL) was performed with the Ilizalov method in 15 patients and TL as well as femoral lengthening (FL) in 6 patients. Concomitant gonadal suppression therapy with buserelin acetate was applied in 13 patients. The mean treatment periods with GH were 10.7 ± 4.0 and 9.3 ± 2.5 years for males and females, respectively. GH treatment augmented the final height +0.60 ± 0.52 SD (+3.5 cm) and +0.51 ± 1.29 SD (+2.8 cm) in males and females compared to non-treated ACH patients, respectively. Final height of ACH patients that underwent GH and TL increased +1.72 ± 0.72 SD (+10.0 cm) and +1.95 ± 1.34 SD (+9.8 cm) in males and females, respectively. GH, TL, and FL increased their final height +2.97 SD (+17.2 cm) and +3.41 ± 1.63 SD (+17.3 cm) in males and females, respectively. Gonadal suppression therapy had no impact on final height. Long-term GH treatment contributes to 2.6 and 2.1% of final adult height in male and female ACH patients, respectively.

  11. Contribution of Mochovce Units completion

    International Nuclear Information System (INIS)

    Burdova, J.

    2013-01-01

    In spite of the on-going economic crisis in Europe, Slovakia is still showing economic growth. Slovenske elektrarne belong to the key companies within the Slovak economy. Not only because of its position in the electricity market, basis for the operation of companies and homes, but also because of its influence on the social and economic development of the country. (author)

  12. Part I. Chapter IV. Coldness is coming from Wienna

    International Nuclear Information System (INIS)

    Blaha, M.

    2008-01-01

    In this chapter author reviewed a political pressure of Austrian government and Austrian legislative assembly on Slovakia before fuel assembly insertion and commissioning of the Unit-1 of the Mochovce NPP. Mission of Walkdown II is described.

  13. Megavoltage conebeam CT cine as final verification of treatment plan in lung stereotactic body radiotherapy

    International Nuclear Information System (INIS)

    Kudithipudi, Vijay; Gayou, Olivier; Colonias, Athanasios

    2016-01-01

    To analyse the clinical impact of megavoltage conebeam computed tomography (MV-CBCT) cine on internal target volume (ITV) coverage in lung stereotactic body radiotherapy (SBRT). One hundred and six patients received lung SBRT. All underwent 4D computed tomography simulation followed by treatment via image guided 3D conformal or intensity modulated radiation. Prior to SBRT, all patients underwent MV-CBCT cine, in which raw projections are displayed as beam's-eye-view fluoroscopic series with the planning target volume (PTV) projected onto each image, enabling verification of tumour motion relative to the PTV and assessment of adequacy of treatment margin. Megavoltage conebeam computed tomography cine was completed 1–2 days prior to SBRT. Four patients (3.8%) had insufficient ITV coverage inferiorly at cine review. All four plans were changed by adding 5 mm on the PTV margin inferiorly. The mean change in PTV volumes was 3.9 cubic centimetres (cc) (range 1.85–6.32 cc). Repeat cine was performed after plan modification to ensure adequate PTV coverage in the modified plans. PTV margin was adequate in the majority of patients with this technique. MV-CBCT cine did show insufficient coverage in a small subset of patients. Insufficient PTV margins may be a function of 4D CT simulation inadequacies or deficiencies in visualizing the ITV inferior border in the full-inhale phase. MV-CBCT cine is a valuable tool for final verification of PTV margins.

  14. Chapter No.8. Personnel qualification and training

    International Nuclear Information System (INIS)

    2002-01-01

    The overall training system and the development projects of training the staff of all categories from NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce were the subject of UJD's attention. During 2001 following inspections were carried out on nuclear personnel training: - PP's Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff; - Mochovce NPP: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; - SE-VYZ: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff. Training the staff of the NPP's Bohunice: - The fundamental and periodical theoretical training as sure as the fundamental and periodical simulator training is carried out by the VUJE Training centre in Trnava. - The fundamental practical training in the workplace and training for the change work- rank is carried at Bohunice plant. Training of the staff of the NPP Mochovce: - The fundamental and periodical theoretical training is carried out by the VUJE Training centre in Trnava. The fundamental practical training in the workplace and training for the change work- rank as well as the fundamental and periodical simulator training is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues a certificate on special professional skills of selected staff members of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: 1. Scientific shift manager for start up with the right of manipulation; 2. Shift supervisor; 3. Unit supervisor; 4. Primary circuit operator; 5. Secondary circuit operator; 6. Reactor physicist; 7. Scientific shift manager for start up without the right of manipulation. Examinations of

  15. Expedited demonstration of molten salt mixed waste treatment technology. Final report

    International Nuclear Information System (INIS)

    1995-01-01

    This final report discusses the molten salt mixed waste project in terms of the various subtasks established. Subtask 1: Carbon monoxide emissions; Establish a salt recycle schedule and/or a strategy for off-gas control for MWMF that keeps carbon monoxide emission below 100 ppm on an hourly averaged basis. Subtask 2: Salt melt viscosity; Experiments are conducted to determine salt viscosity as a function of ash composition, ash concentration, temperature, and time. Subtask 3: Determine that the amount of sodium carbonate entrained in the off-gas is minimal, and that any deposited salt can easily be removed form the piping using a soot blower or other means. Subtask 4: The provision of at least one final waste form that meets the waste acceptance criteria of a landfill that will take the waste. This report discusses the progress made in each of these areas

  16. Megavoltage conebeam CT cine as final verification of treatment plan in lung stereotactic body radiotherapy.

    Science.gov (United States)

    Kudithipudi, Vijay; Gayou, Olivier; Colonias, Athanasios

    2016-06-01

    To analyse the clinical impact of megavoltage conebeam computed tomography (MV-CBCT) cine on internal target volume (ITV) coverage in lung stereotactic body radiotherapy (SBRT). One hundred and six patients received lung SBRT. All underwent 4D computed tomography simulation followed by treatment via image guided 3D conformal or intensity modulated radiation. Prior to SBRT, all patients underwent MV-CBCT cine, in which raw projections are displayed as beam's-eye-view fluoroscopic series with the planning target volume (PTV) projected onto each image, enabling verification of tumour motion relative to the PTV and assessment of adequacy of treatment margin. Megavoltage conebeam computed tomography cine was completed 1-2 days prior to SBRT. Four patients (3.8%) had insufficient ITV coverage inferiorly at cine review. All four plans were changed by adding 5 mm on the PTV margin inferiorly. The mean change in PTV volumes was 3.9 cubic centimetres (cc) (range 1.85-6.32 cc). Repeat cine was performed after plan modification to ensure adequate PTV coverage in the modified plans. PTV margin was adequate in the majority of patients with this technique. MV-CBCT cine did show insufficient coverage in a small subset of patients. Insufficient PTV margins may be a function of 4D CT simulation inadequacies or deficiencies in visualizing the ITV inferior border in the full-inhale phase. MV-CBCT cine is a valuable tool for final verification of PTV margins. © 2016 The Royal Australian and New Zealand College of Radiologists.

  17. Hot functional test chemistry - long term experience

    International Nuclear Information System (INIS)

    Vonkova, K.; Kysela, J.; Marcinsky, M.; Martykan, M.

    2010-01-01

    Primary circuit materials undergo general corrosion in high temperature, deoxygenated, neutral or mildly alkaline solutions to form thin oxide films. These oxide layers (films) serve as protective film and mitigate the further corrosion of primary materials. Inner chromium-rich oxide layer has low cation diffusion coefficients and thus control iron and nickel transport from the metal surface to the outer layer and their dissolution into the coolant. Much less corrosion products are generated by the compact, integral and stable oxide (passivation) layer. For the latest Czech and Slovak stations commissioned (Temelin and Mochovce) a modified Hot Functional Test (HFT) chemistry was developed in the NRI Rez. Chromium rich surface layer formatted due to modified HTF chemistry ensures lower corrosion rates and radiation field formation and thus also mitigates crud formation during operation. This procedure was also designed to prepare the commissioned unit for the further proper water chemistry practise. Mochovce 1 (SK) was the first station commissioned using these recommendations in 1998. Mochovce 2 (1999) and Temelin 1 and 2 (CZ - 2000 and 2002) were subsequently commissioned using these guidelines too. The main principles of the controlled primary water chemistry applied during the hot functional tests are reviewed and importance of the water chemistry, technological and other relevant parameters is stressed regarding to the quality of the passive layer formed on the primary system surfaces. Samples from Mochovce indicated that duplex oxide layers up to 20 μm thick were produced, which were mainly magnetite substituted with nickel and chromium (e.g. 60-65% Fe, 18-28% Cr, 9-12% Ni, <1% Mn and 1-2% Si on a stainless steel primary circuit sample). Long term operation experience from both nuclear power plants are discussed in this paper. Radiation field, occupational radiation exposure and corrosion layers evolution during the first c. ten years of operation are

  18. Proof-of-Principle of Onchocerciasis Elimination with Ivermectin Treatment in Endemic Foci in Africa: Final Results of a Study in Mali and Senegal

    Science.gov (United States)

    Traore, Mamadou O.; Sarr, Moussa D.; Badji, Alioune; Bissan, Yiriba; Diawara, Lamine; Doumbia, Konimba; Goita, Soula F.; Konate, Lassana; Mounkoro, Kalifa; Seck, Amadou F.; Toe, Laurent; Toure, Seyni; Remme, Jan H. F.

    2012-01-01

    Background Mass treatment with ivermectin controls onchocerciasis as a public health problem, but it was not known if it could also interrupt transmission and eliminate the parasite in endemic foci in Africa where vectors are highly efficient. A longitudinal study was undertaken in three hyperendemic foci in Mali and Senegal with 15 to 17 years of annual or six-monthly ivermectin treatment in order to assess residual levels of infection and transmission, and test whether treatment could be safely stopped. This article reports the results of the final evaluations up to 5 years after the last treatment. Methodology/Principal Findings Skin snip surveys were undertaken in 131 villages where 29,753 people were examined and 492,600 blackflies were analyzed for the presence of Onchocerca volvulus larva using a specific DNA probe. There was a declining trend in infection and transmission levels after the last treatment. In two sites the prevalence of microfilaria and vector infectivity rate were zero 3 to 4 years after the last treatment. In the third site, where infection levels were comparatively high before stopping treatment, there was also a consistent decline in infection and transmission to very low levels 3 to 5 years after stopping treatment. All infection and transmission indicators were below postulated thresholds for elimination. Conclusion/Significance The study has established the proof of principle that onchocerciasis elimination with ivermectin treatment is feasible in at least some endemic foci in Africa. The study results have been instrumental for the current evolution from onchocerciasis control to elimination in Africa. PMID:23029586

  19. Treatment and final conditioning of solid radioactive wastes

    International Nuclear Information System (INIS)

    Cerre, J.

    1960-01-01

    The storage of solid radioactive wastes on a site is so cumbersome and dangerous that we have developed a method of treatment and conditioning by means of which the volume of waste is considerably reduced and very long-lasting shielding can be provided. This paper describes the techniques adopted at Saclay, where the wastes are sheared, compressed and enveloped in concrete of variable thickness. The main part of the report is devoted to a description of the corresponding remote handling installation. (author) [fr

  20. Nuclear safety. Improvement programme

    International Nuclear Information System (INIS)

    2000-01-01

    In this brochure the improvement programme of nuclear safety of the Mochovce NPP is presented in detail. In 1996, a 'Mochovce NPP Nuclear Safety Improvement Programme' was developed in the frame of unit 1 and 2 completion project. The programme has been compiled as a continuous one, with the aim to reach the highest possible safety level at the time of commissioning and to establish good preconditions for permanent safety improvement in future. Such an approach is in compliance with the world's trends of safety improvement, life-time extension, modernisation and nuclear station power increase. The basic document for development of the 'Programme' is the one titled 'Safety Issues and their Ranking for WWER 440/213 NPP' developed by a group of IAEA experts. The following organisations were selected for solution of the safety measures: EUCOM (Consortium of FRAMATOME, France, and SIEMENS, Germany); SKODA Prague, a.s.; ENERGOPROJEKT Prague, a.s. (EGP); Russian organisations associated in ATOMENERGOEXPORT; VUJE Trnava, a.s

  1. Can Slovakia secure reliable electricity supply without nuclear?

    International Nuclear Information System (INIS)

    Pnacek, I.

    2004-01-01

    In this presentation author deals with structure of electricity production in the Slovak republic in 2006 and perspectives of electricity supply up to 2020 year. Decommissioning of Unit 1 and Unit 2 of the Bohunice NPP and completion of Unit 3 and 4 of the Mochovce NPP are discussed

  2. Efficacy of chlorhexidine as a final irrigant in one-visit root canal treatment: a prospective comparative study.

    Science.gov (United States)

    Miçooğullar Kurt, S; Çalışkan, M K

    2018-03-30

    To evaluate postoperative pain and radiographic evidence of periapical healing in teeth with apical periodontitis treated in one visit with an additional final irrigation using 2% chlorhexidine (CHX) and to compare the results with conventional two-visit root canal treatment (RCT) with an intracanal calcium hydroxide (CH) dressing as a control group. Ninety asymptomatic maxillary anterior teeth with periapical lesions were treated by a single operator. Root canals were prepared using the step-back technique with manual instrumentation with 2.5% NaOCl and 5% EDTA as irrigants. Half of the teeth were randomly assigned to the one-visit (OV) group and received an additional final rinse with 2% CHX before canal filling. The other teeth were treated in two visits (TV) with a CH paste made by mixing CH powder and distilled water as an interappointment dressing. All patients were recalled and investigated clinically and radiographically for 24 months. Postoperative pain at 24-48 h and changes in apical bone density indicating radiographic healing were evaluated statistically using the Mann-Whitney U-test followed by the Friedman and the Wilcoxon tests (α = 0.05). There were no significant differences between two groups regarding the incidence of postoperative pain at 24 h (OV group 50% no pain, 47.6% mild, 2.4% moderate pain/TV group 55% no pain, 42.5% mild, 2.5% moderate pain) and at 48 h (OV group 95% no pain, 5% mild pain/TV group 98% no pain, 2% mild pain). None of the patients reported severe postoperative pain, swelling and/or flare-ups during the follow-up period. There was no significant difference in the radiographic healing rates (OV group 97.6% PAI 1 and/or PAI 2 and 2.4% PAI 3/TV group 95% PAI 1 and/or PAI 2 and 5% PAI 3; P > 0.05). Both groups provided favourable and similar postoperative pain and periapical healing rates at 24 months. Thus, one-visit RCT with a final rinse with 2% CHX is an acceptable alternative to two-visit RCT with CH as

  3. COSTECH - HURIA JOURNAL VOL. 24 (2) COSTECH FINAL_NEW

    African Journals Online (AJOL)

    Prof Kigadye

    consecutive days; finally 6 animals were randomly picked from each treatment and slaughtered ... Organoleptic test was conducted and samples of the mutton, goat meat and ..... Asian-Australasian Journal of Animal Sciences 27(1): 55 –. 60.

  4. Irradiation Embrittlement Monitoring Programs of RPV's in the Slovak Republic NPP's

    International Nuclear Information System (INIS)

    Kupca, Ludovik

    2006-01-01

    Four types of surveillance programs were (are) realized in Slovak NPP's: 'Standard Surveillance Specimen Program' (SSSP) was finished in Jaslovske Bohunice V-2 Nuclear Power Plant (NPP) Units 3 and 4, 'Extended Surveillance Specimen Program' (ESSP), was prepared for Jaslovske Bohunice NPP V-2 with aim to validate the SSSP results, For the Mochovce NPP Unit 1 and 2 was prepared completely new surveillance program 'Modern Surveillance Specimen Program' (MSSP), based on the philosophy that the results of MSSP must be available during all NPP service life, For the Bohunice V-1 NPP was finished 'New Surveillance Specimen Program' (NSSP) coordinated by IAEA, which gave arguments for prolongation of service life these units for minimum 20 years, New Advanced Surveillance Specimen Program (ASSP) for Bohunice V-2 NPP (units 3 and 4) and Mochovce NPP (units 1, 2) is approved now. ASSP is dealing with the irradiation embrittlement of heat affected zone (HAZ) and RPV's austenitic cladding, which were not evaluated till this time in surveillance programs. SSSP started in 1979 and was finished in 1990. ESSP program started in 1995 and will be finished in 2007, was prepared with aim of: increasing of neutron fluence measurement accuracy, substantial improvement the irradiation temperature measurement, fixed orientation of samples to the centre of the reactor core, minimum differences of neutron dose for all the Charpy-V notch and COD specimens, the dose rate effect evaluation. In the year 1996 was started the new surveillance specimen program for the Mochovce RPV's unit-1 and 2, based on the fundamental postulate - to provide the irradiation embrittlement monitoring till the end of units operation. The 'New Surveillance Specimen Program' (NSSP) prepared in the year 1999 for the Bohunice V-1 NPP was finished in the year 2004. Main goal of this program was to evaluate the weld material properties degradation due to the irradiation and recovery efficiency by annealing too. The

  5. Prevalence of Multiple Antibiotics Resistant (MAR) Pseudomonas Species in the Final Effluents of Three Municipal Wastewater Treatment Facilities in South Africa

    Science.gov (United States)

    Odjadjare, Emmanuel E.; Igbinosa, Etinosa O.; Mordi, Raphael; Igere, Bright; Igeleke, Clara L.; Okoh, Anthony I.

    2012-01-01

    The final effluents of three (Alice, Dimbaza, and East London) wastewater treatment plants (WWTPs) were evaluated to determine their physicochemical quality and prevalence of multiple antibiotics resistant (MAR) Pseudomonas species, between August 2007 and July 2008. The annual mean total Pseudomonas count (TPC) was 1.20 × 104 (cfu/100 mL), 1.08 × 104 (cfu/100 mL), and 2.66 × 104 (cfu/100 mL), for the Alice, Dimbaza, and East London WWTPs respectively. The effluents were generally compliant with recommended limits for pH, temperature, TDS, DO, nitrite and nitrate; but fell short of target standards for turbidity, COD, and phosphate. The tested isolates were highly sensitive to gentamicin (100%), ofloxacin (100%), clindamycin (90%), erythromycin (90%) and nitrofurantoin (80%); whereas high resistance was observed against the penicillins (90–100%), rifampin (90%), sulphamethoxazole (90%) and the cephems (70%). MAR index ranged between 0.26 and 0.58. The study demonstrated that MAR Pseudomonas species were quite prevalent in the final effluents of WWTPs in South Africa; and this can lead to serious health risk for communities that depend on the effluent-receiving waters for sundry purposes. PMID:22829792

  6. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume I of V

    International Nuclear Information System (INIS)

    1997-05-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type. This information includes the cumulative impacts of combining future siting configurations for the five waste types and the collective impacts of other past, present, and reasonably foreseeable future activities. The selected waste management facilities being considered for these different waste types are treatment and disposal facilities for low-level mixed waste; treatment and disposal facilities for low-level waste; treatment and storage facilities for transuranic waste in the event that treatment is required before disposal; storage facilities for treated (vitrified) high-level waste canisters; and treatment of nonwastewater hazardous waste by DOE and commercial vendors. In addition to the no action alternative, which includes only existing or approved waste management facilities, the alternatives for each of the waste type configurations include decentralized, regionalized, and centralized alternatives for using existing and operating new waste management facilities. However, the siting, construction and operations of any new facility at a selected site will not be decided until completion of a sitewide or project-specific environmental impact review

  7. Review of the integrated thermal and nonthermal treatment system studies. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    This report contains a review and evaluation of three systems analysis studies performed by LITCO on integrated thermal treatment systems and integrated nonthermal treatment systems for the remediation of mixed low-level waste stored throughout the US Department of Energy weapons complex. The review was performed by an independent team of nine researchers from the Energy and Environmental Research Center, Science Applications International Corporation, the Waste Policy Institute, and Virginia Tech. The three studies reviewed were as follows: Integrated Thermal Treatment System Study, Phase 1 -- issued July 1994; Integrated Thermal Treatment System Study, Phase 2 -- issued February 1996; and Integrated Nonthermal Treatment System Study -- drafted March 1996. The purpose of this review was to (1) determine whether the assumptions of the studies were adequate to produce an unbiased review of both thermal and nonthermal systems, (2) to identify the critical areas of the studies that would benefit from further investigation, and (3) to develop a standard template that could be used in future studies to assure a sound application of systems engineering.

  8. Review of the integrated thermal and nonthermal treatment system studies. Final report

    International Nuclear Information System (INIS)

    1996-10-01

    This report contains a review and evaluation of three systems analysis studies performed by LITCO on integrated thermal treatment systems and integrated nonthermal treatment systems for the remediation of mixed low-level waste stored throughout the US Department of Energy weapons complex. The review was performed by an independent team of nine researchers from the Energy and Environmental Research Center, Science Applications International Corporation, the Waste Policy Institute, and Virginia Tech. The three studies reviewed were as follows: Integrated Thermal Treatment System Study, Phase 1 -- issued July 1994; Integrated Thermal Treatment System Study, Phase 2 -- issued February 1996; and Integrated Nonthermal Treatment System Study -- drafted March 1996. The purpose of this review was to (1) determine whether the assumptions of the studies were adequate to produce an unbiased review of both thermal and nonthermal systems, (2) to identify the critical areas of the studies that would benefit from further investigation, and (3) to develop a standard template that could be used in future studies to assure a sound application of systems engineering

  9. Irradiation as a quarantine treatment of arthropod pests. Proceedings of a final research co-ordination meeting

    International Nuclear Information System (INIS)

    1999-05-01

    Fresh horticultural produce from tropical and sub-tropical areas often harbours insects and mites and are quarantined by importing countries. Such commodities cannot gain access to countries which have strict quarantine regulations such as Australia, Japan, New Zealand and the United States of America unless treated by an approved method/procedure to eliminate such pests. Current approved methods include fumigation by methyl bromide, hot water dip, vapour heat, dried heat and irradiation. Methyl bromide is being phased out globally under the Montreal Protocol in view of its strong ozone depleting properties. Countries such as the USA and those of the European Union are required to phase out the production of this chemical by the year 2005. Among other phytosanitary treatments, irradiation appears to have an edge as it is more versatile in controlling various pests and causes insignificant changes in quality of the treated products. The CRP on Irradiation as a Quarantine Treatment of Mites, Nematodes and Insects other than Fruit Flies, in operation between 1992 and 1997, attempted to fill the gap of information on the effectiveness of irradiation against other quarantine pests. Significant data were generated by this CRP to demonstrate that a minimum dose of between 200 and 400 Gy would render a number of non-fruit fly insects and mites sterile, thus meeting quarantine requirements. However, only a limited species of insects and mites were studied. Additional data are required to provide conclusive evidence that such a dose would render most, if not all, species of non-fruit fly insects and mites sterile. Plant parasitic nematodes appear to be resistant to irradiation as the dose required to render them sterile would cause damage to fresh horticultural commodities. Irradiation would be a useful quarantine treatment against this pest only for durable commodities such as pot soil, wood products, etc. This publication presents the research results of the CRP presented

  10. Irradiation as a quarantine treatment of arthropod pests. Proceedings of a final research co-ordination meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    Fresh horticultural produce from tropical and sub-tropical areas often harbours insects and mites and are quarantined by importing countries. Such commodities cannot gain access to countries which have strict quarantine regulations such as Australia, Japan, New Zealand and the United States of America unless treated by an approved method/procedure to eliminate such pests. Current approved methods include fumigation by methyl bromide, hot water dip, vapour heat, dried heat and irradiation. Methyl bromide is being phased out globally under the Montreal Protocol in view of its strong ozone depleting properties. Countries such as the USA and those of the European Union are required to phase out the production of this chemical by the year 2005. Among other phytosanitary treatments, irradiation appears to have an edge as it is more versatile in controlling various pests and causes insignificant changes in quality of the treated products. The CRP on Irradiation as a Quarantine Treatment of Mites, Nematodes and Insects other than Fruit Flies, in operation between 1992 and 1997, attempted to fill the gap of information on the effectiveness of irradiation against other quarantine pests. Significant data were generated by this CRP to demonstrate that a minimum dose of between 200 and 400 Gy would render a number of non-fruit fly insects and mites sterile, thus meeting quarantine requirements. However, only a limited species of insects and mites were studied. Additional data are required to provide conclusive evidence that such a dose would render most, if not all, species of non-fruit fly insects and mites sterile. Plant parasitic nematodes appear to be resistant to irradiation as the dose required to render them sterile would cause damage to fresh horticultural commodities. Irradiation would be a useful quarantine treatment against this pest only for durable commodities such as pot soil, wood products, etc. This publication presents the research results of the CRP presented

  11. DE-FG02-04ER63746 FinalTechnicalReport

    Energy Technology Data Exchange (ETDEWEB)

    Lidstrom, M.E.

    2009-09-05

    This is the final technical report for a project involving the study of stress response systems in the radiation-resistant bacterium, Deinococcus radiodurans. Three stresses of importance for a mixed waste treatment strain were studied, heat shock, solvent shock, and phosphate starvation. In each case, specific genes involved in the ability to survive the stress were identified using a systems biology approach, and analysis of mutants was used to understand mechanisms. This study has led to increased understanding of the ways in which a potential treatment strain could be manipulated to survive multiple stresses for treatment of mixed wastes.

  12. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume V of V

    International Nuclear Information System (INIS)

    1997-01-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear energy research and the development, production, and testing of nuclear weapons at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives, which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type. This information includes the cumulative impacts of combining future siting configurations for the five waste types and the collective impacts of other past, present, and reasonably foreseeable future activities. The selected waste management facilities being considered for these different waste types are treatment and disposal facilities for low-level mixed waste; treatment and disposal facilities for low-level waste; treatment and storage facilities for transuranic waste in the event that treatment is required before disposal; storage facilities for created (vitrified) high-level waste canisters; and treatment of nonwastewater hazardous waste by DOE and commercial vendors. In addition to the No Action Alternative, which includes only existing of approved waste management facilities, the alternatives for each of the waste-type configurations include Decentralized, Regionalized, and Centralized Alternatives for using existing and operating new waste management facilities. However, the siting, construction, and operations of any new facility at a selected site will not be decided until completion of a sitewide or project-specific environmental impact review

  13. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume III of V

    International Nuclear Information System (INIS)

    1997-01-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type

  14. Treatment and final disposal of nuclear waste. Siting of a deep repository

    International Nuclear Information System (INIS)

    1992-09-01

    Systems and facilities in the program for demonstration deposition of nuclear waste are presented. The siting process is described, from the general studies to the ultimate goal, where a permit to start demonstration deposition has been obtained. National and foreign experiences of siting issues are accounted for. Finally, the structure and plan for work for 1993-98 are outlined. 46 refs, 15 figs, 5 tabs

  15. Intermediate treatments

    Science.gov (United States)

    John R. Jones; Wayne D. Shepperd

    1985-01-01

    Intermediate treatments are those applied after a new stand is successfully established and before the final harvest. These include not only intermediate cuttings - primarily thinning - but also fertilization, irrigation, and protection of the stand from damaging agents.

  16. Case Law

    International Nuclear Information System (INIS)

    2014-01-01

    This section treats of the following case laws sorted by country: 1 - Germany: Federal Administrative Court confirms the judgments of the Higher Administrative Court of the Land Hesse: The shutdown of nuclear power plant Biblis blocks A and B based on a 'moratorium' imposed by the Government was unlawful; List of lawsuits in the nuclear field. 2 - Slovak Republic: Further developments in cases related to the challenge by Greenpeace Slovakia to the Mochovce nuclear power plant; Developments in relation to the disclosure of information concerning the Mochovce nuclear power plant. 3 - United States: Judgment of the Nuclear Regulatory Commission resuming the licensing process for the Department of Energy's construction authorisation application for the Yucca Mountain high-level radioactive waste repository; Judgment of the Licensing Board in favour of Shaw AREVA MOX Services regarding the material control and accounting system at the proposed MOX Facility; Dismissal by US District Court Judge of lawsuit brought by US military personnel against Tokyo Electric Power Company (TEPCO) in connection with the Fukushima Daiichi nuclear power plant accident

  17. Clinical outcomes after final kissing balloon inflation compared with no final kissing balloon inflation in bifurcation lesions treated with a dedicated coronary bifurcation stent

    NARCIS (Netherlands)

    M.J. Grundeken (Maik); M. Lesiak (MacIej); S. Asgedom (Solomon); E. Garcia (Eulogio); A. Bethencourt (Armando); M.S. Norell (Michael); K. Damman (Kevin); E. Woudstra (Evert); K. Koch (Karel); M.M. Vis (Marije); J.P.S. Henriques (Jose); J.G.P. Tijssen (Jan); Y. Onuma (Yoshinobu); D.P. Foley (David); A. Bartorelli (Antonio); P.R. Stella (Pieter); R.J. de Winter (Robbert); J.J. Wykrzykowska (Joanna)

    2014-01-01

    textabstractObjective We evaluated differences in clinical outcomes between patients who underwent final kissing balloon inflation (FKBI) and patients who did not undergo FKBI in bifurcation treatment using the Tryton Side Branch Stent (Tryton Medical, Durham, North Carolina, USA). Methods Clinical

  18. Expectations and final evaluation of complete dentures by patients, dentist and dental technician.

    Science.gov (United States)

    Marachlioglou, C R M Z; Dos Santos, J F F; Cunha, V P P; Marchini, Leonardo

    2010-07-01

    There is a poor association between the dentist's evaluation of denture quality and patients' satisfaction with their dentures. Possible differences between dental professionals and patients' expectations might help explain differences in outcome evaluations. This study compared scores given by a dentist, a dental technician and patients for their expectations before and their final evaluation after complete dentures treatment. Twenty completely edentulous patients, a prosthodontist and a dental technician provided scores for the expected aesthetic and functional results of their dentures based on a visual analogue scale at baseline. Post-treatment completion ratings were given after adjustments, by dentist and patients. The dental technician provided post-treatment completion ratings after completing the dentures. The patients had higher expectations than the dental technician and the dentist perceived for both aesthetic and function (P < 0.001). The patients also presented higher post-treatment completion ratings than the dental professionals perceived for final aesthetics (P = 0.016, Kendall's W = 0.207) and function (P = 0.002, Kendall's W = 0.303). Only the dentist presented a statistically significant difference between expectations (lower) and final (higher) outcomes for aesthetics (P = 0.017) and function (P = 0.003). There was no correlation between expectations and post-treatment completion ratings according to the patients' age. There was also no correlation between the patients' gender and expectation scores. Patients presented higher expectations regarding their dentures than dental professionals. The dentist believed that dentures would bring fewer benefits than patients did, but his perception of denture benefits post-treatment was significantly higher than his expectations.

  19. Ex situ bioremediation of mineral oil in soils: Aerated pile treatment. Final report

    International Nuclear Information System (INIS)

    Graves, D.

    1998-04-01

    Under a contract with Southern Company Services, a pilot-scale evaluation of mineral oil biodegradation was conducted at Plant Mitchell. The evaluation consisted of two demonstrations to examine land treatment and aerated pile treatment of soil contaminated with the mineral insulating oil used in electrical transformers. Treatment of mineral oil contaminated soil is problematic in the State of Georgia and throughout the US because current practice is to excavate and landfill the contaminated soil. In many cases, the cost associated with these activities far exceeds the environmental risk of mineral oil in soil. This project was designed to evaluate the performance of bioremediation for the treatment of mineral oil in soil. Testing was carried out in a demonstration facility prepared by Georgia Power Company. The facility consisted of 12 independent treatment cells constructed on a concrete pad and covered with a roof

  20. Regulatory impact analysis of the part 503 sewage sludge regulation. Final report

    International Nuclear Information System (INIS)

    Burris, S.

    1992-01-01

    The report evaluates the costs, benefits, and economic impacts of the final 40 CFR Part 503 regulation governing the use of disposal of sewage sludge generated during the treatment of domestic sewage in a treatment works and domestic septage. The report begins by describing some relevant characteristics of treatment works and domestic septage haulers. The report focuses on the costs, risks, and benefits of the Part 503 regulation

  1. RTR spent fuel treatment and final waste storage

    International Nuclear Information System (INIS)

    Thomasson, J.

    2000-01-01

    A number of RTR operators have chosen in the past to send their spent fuel to the US in the framework of the US take back program. However, this possibility ends as of May 12th, 2006. 3 different strategies are left for managing RTR spent fuel: extended storage, direct disposal and treatment-conditioning through reprocessing. Whilst former strategies raise a number of uncertainties, the latter already offers a management solution. It features two advantages. It benefits from the long experience of existing flexible industrial facilities from countries like France. Secondly, it offers a dramatic volume reduction of the ultimate waste to be stored under well-characterized, stable and durable forms. RTR spent fuel management through reprocessing-conditioning offers a durable management solution that can be fully integrated in whatever global radioactive waste management policy, including ultimate disposal

  2. Clinical outcomes after final kissing balloon inflation compared with no final kissing balloon inflation in bifurcation lesions treated with a dedicated coronary bifurcation stent

    NARCIS (Netherlands)

    Grundeken, Maik J.; Lesiak, Maciej; Asgedom, Solomon; Garcia, Eulogio; Bethencourt, Armando; Norell, Michael S.; Damman, Peter; Woudstra, Pier; Koch, Karel T.; Vis, M. Marije; Henriques, Jose P.; Tijssen, Jan G.; Onuma, Yoshinobu; Foley, David P.; Bartorelli, Antonio L.; Stella, Pieter R.; de Winter, Robbert J.; Wykrzykowska, Joanna J.

    2014-01-01

    We evaluated differences in clinical outcomes between patients who underwent final kissing balloon inflation (FKBI) and patients who did not undergo FKBI in bifurcation treatment using the Tryton Side Branch Stent (Tryton Medical, Durham, North Carolina, USA). Clinical outcomes were defined as

  3. Part II. Chapter I. Nobody will build the nuclear power cheaper than we finish it under construction

    International Nuclear Information System (INIS)

    Bucha, T.

    2008-01-01

    This is an interview with Mr. Sergej Kozlik (vice-prime minister of the Slovak Government from October 11, 1993 up to March 15, 1994 and from December 12, 1994 up to October 30, 1998 and finance minister from December 13, 1994 up to January 14, 1998) who is remembering about financing of construction of the Mochovce NPP.

  4. Life cycle assessment comparing the treatment of surplus activated sludge in a sludge treatment reed bed system with mechanical treatment on centrifuge

    DEFF Research Database (Denmark)

    Larsen, Julie Dam; Hoeve, Marieke ten; Nielsen, Steen

    2018-01-01

    or the centrifuge and terminated by land application of the final sludge product. The environmental impacts caused by the sludge treatment reed bed system strategy were comparable to or lower than those caused by the mechanical sludge treatment method. The impacts on climate change were the same for all...

  5. GH treatment to final height produces similar height gains in patients with SHOX deficiency and Turner syndrome: results of a multicenter trial.

    Science.gov (United States)

    Blum, Werner F; Ross, Judith L; Zimmermann, Alan G; Quigley, Charmian A; Child, Christopher J; Kalifa, Gabriel; Deal, Cheri; Drop, Stenvert L S; Rappold, Gudrun; Cutler, Gordon B

    2013-08-01

    Growth impairment in short stature homeobox-containing gene (SHOX) deficiency and Turner syndrome share a similar etiology. Because of the established effect of GH treatment on height in patients with Turner syndrome, we hypothesized that GH therapy would also stimulate growth in patients with SHOX deficiency. Our objectives were to evaluate long-term efficacy of GH treatment in short patients with SHOX deficiency and to compare the effect on final (adult) height (FH) in patients with SHOX deficiency and Turner syndrome. A prospective, multinational, open-label, randomized 3-arm study consisting of a 2-year control period and a subsequent extension period to FH. The treatment groups were 1) SHOX-D-C/GH (untreated during the control period, GH-treated during the extension), 2) SHOX-D-GH/GH, and 3) Turner-GH/GH (GH-treated during both study periods). Short-statured prepubertal patients with genetically confirmed SHOX deficiency (n = 49) or Turner syndrome (n = 24) who participated in the extension. Depending on the study arm, patients received a daily sc injection of 0.05 mg/kg recombinant human GH from start of the study or start of the extension until attainment of FH or study closure. Height SD score gain from start of GH treatment to FH was similar between the combined SHOX-deficient groups (n = 28, 1.34 ± 0.18 [least-squares mean ± SE]) and the Turner group (n = 19, 1.32 ± 0.22). In this FH population, 57% of the patients with SHOX deficiency and 32% of the patients with Turner syndrome achieved a FH greater than -2 SD score. GH treatment in short children with SHOX deficiency showed similar long-term efficacy as seen in girls with Turner syndrome.

  6. Medicare and Medicaid programs; advance directives--HCFA. Final rule.

    Science.gov (United States)

    1995-06-27

    This final rule responds to public comments on the March 6, 1992 interim final rule with comment period that amended the Medicare and Medicaid regulations governing provider agreements and contracts to establish requirements for States, hospitals, nursing facilities, skilled nursing facilities, providers of home health care or personal care services, hospice programs and managed care plans concerning advance directives. An advance directive is a written instruction, such as a living will or durable power of attorney for health care, recognized under State law, relating to the provision of health care when an individual's condition makes him or her unable to express his or her wishes. The intent of the advance directives provisions is to enhance an adult individual's control over medical treatment decisions. This rule confirms the interim final rule with several minor changes based on our review and consideration of public comments.

  7. Presence of Stenotrophomonas maltophilia exhibiting high genetic similarity to clinical isolates in final effluents of pig farm wastewater treatment plants.

    Science.gov (United States)

    Kim, Young-Ji; Park, Jin-Hyeong; Seo, Kun-Ho

    2018-03-01

    Although the prevalence of community-acquired Stenotrophomonas maltophilia infections is sharply increasing, the sources and likely transmission routes of this bacterium are poorly understood. We studied the significance of the presence of S. maltophilia in final effluents and receiving rivers of pig farm wastewater treatment plants (WWTPs). The loads and antibiotic resistance profiles of S. maltophilia in final effluents were assessed. Antibiotic resistance determinants and biofilm formation genes were detected by PCR, and genetic similarity to clinical isolates was investigated using multilocus sequence typing (MLST). S. maltophilia was recovered from final effluents at two of three farms and one corresponding receiving river. Tests of resistance to antibiotics recommended for S. maltophilia infection revealed that for each agent, at least one isolate was classified as resistant or intermediate, with the exception of minocycline. Furthermore, multidrug resistant S. maltophilia susceptible to antibiotics of only two categories was isolated and found to carry the sul2 gene, conferring trimethoprim/sulfamethoxazole resistance. All isolates carried spgM, encoding a major factor in biofilm formation. MLST revealed that isolates of the same sequence type (ST; ST189) were present in both effluent and receiving river samples, and phylogenetic analysis showed that all of the STs identified in this study clustered with clinical isolates. Moreover, one isolate (ST192) recovered in this investigation demonstrated 99.61% sequence identity with a clinical isolate (ST98) associated with a fatal infection in South Korea. Thus, the pathogenicity of the isolates reported here is likely similar to that of those from clinical environments, and WWTPs may play a role as a source of S. maltophilia from which this bacterium spreads to human communities. To the best of our knowledge, this represents the first report of S. maltophilia in pig farm WWTPs. Our results indicate that

  8. Fire protection measures

    International Nuclear Information System (INIS)

    Bittner

    1997-01-01

    The presentation could only show a very brief overview of the analysis results of a wide study of the existing fire protection situation at Mochovce. As far not already done the next steps will be the selection of the final suppliers of the different measures, the detailed design and the implementation of the measures. As part of the further assistance in fire protection EUCOM will perform compliance checks of the DD and implementation and assist EMO for raising problems. Especially during the implementation of the measures the belonging quality checks have a high priority. Assuming that the implementation of measures will be in accordance with with the study results and the relevant basic design requirements it can be stated that safety level concerning fire protection will be in accordance with international requirement like IAEA 50 SG D2. The next step of our work will be the delta analysis for 2 unit and the relevant basic design as far as there are differences to unit 1. (author)

  9. Behaviour of Aluminosilicate Inorganic Matrix Sial During and After Solidification of Radioactive Sludge And Radioactive Spent Resins and Their Mixtures

    International Nuclear Information System (INIS)

    Lichvar, P.; Rozloznik, M.; Sekely, S.

    2013-01-01

    SIAL matrix is the product of inorganic compounds by polycondensation. The inorganic SIAL matrix was subject of study from the atomic level to the level of technological application. Infrared spectroscopy measurement and X-ray analysis confirmed that SIAL matrix is mostly formed by amorphous phase. This satisfies the required criteria for disposal of immobilized radioactive waste of appropriate properties into surface repository (Slovak and Czech Republic). First of all, leaching of radioactive nuclide Cs-137 and compressive strength of the final product were found. Various remotely operated devices have been designed, manufactured and successfully used for the radioactive sludge and sludge/resins mixture solidification at the Nuclear power plant (NPP) A-1, V-2 in Jaslovske Bohunice, at Mochovce NPP (Slovak Republic), at Dukovany NPP and at Temelin NPP (Czech Republic). The SIAL matrix was approved for waste package for sludge/resins mixture by the Slovak and Czech Nuclear Regulatory Authorities. (author)

  10. Behaviour of Aluminosilicate Inorganic Matrix Sial During and After Solidification of Radioactive Sludge And Radioactive Spent Resins and Their Mixtures

    Energy Technology Data Exchange (ETDEWEB)

    Lichvar, P.; Rozloznik, M.; Sekely, S. [Amec Nuclear Slovakia, 919 31 Jaslovske Bohunice (Slovakia)

    2013-09-15

    SIAL matrix is the product of inorganic compounds by polycondensation. The inorganic SIAL matrix was subject of study from the atomic level to the level of technological application. Infrared spectroscopy measurement and X-ray analysis confirmed that SIAL matrix is mostly formed by amorphous phase. This satisfies the required criteria for disposal of immobilized radioactive waste of appropriate properties into surface repository (Slovak and Czech Republic). First of all, leaching of radioactive nuclide Cs-137 and compressive strength of the final product were found. Various remotely operated devices have been designed, manufactured and successfully used for the radioactive sludge and sludge/resins mixture solidification at the Nuclear power plant (NPP) A-1, V-2 in Jaslovske Bohunice, at Mochovce NPP (Slovak Republic), at Dukovany NPP and at Temelin NPP (Czech Republic). The SIAL matrix was approved for waste package for sludge/resins mixture by the Slovak and Czech Nuclear Regulatory Authorities. (author)

  11. L/ILW management and final disposal. Proceedings

    International Nuclear Information System (INIS)

    1993-01-01

    This is a proceedings of the Sino-French Seminar on Low- and Intermediate-Level waste Management and Final Disposal. The seminar was held on 26-28 April 1993 in Beijing of China. 33 papers are included in the proceedings. The great efforts in the treatment and disposal of different level radwastes and achievements in the research and development in China are introduced. The rich experience on the radwaste management in France are also introduced

  12. Ethical aspects of final disposal. Final report

    International Nuclear Information System (INIS)

    Baltes, B.; Leder, W.; Achenbach, G.B.; Spaemann, R.; Gerhardt, V.

    2003-01-01

    In fulfilment of this task the Federal Environmental Ministry has commissioned GRS to summarise the current national and international status of ethical aspects of the final disposal of radioactive wastes as part of the project titled ''Final disposal of radioactive wastes as seen from the viewpoint of ethical objectives''. The questions arising from the opinions, positions and publications presented in the report by GRS were to serve as a basis for an expert discussion or an interdisciplinary discussion forum for all concerned with the ethical aspects of an answerable approach to the final disposal of radioactive wastes. In April 2001 GRS held a one-day seminar at which leading ethicists and philosophers offered statements on the questions referred to above and joined in a discussion with experts on issues of final disposal. This report documents the questions that arose ahead of the workshop, the specialist lectures held there and a summary of the discussion results [de

  13. Reducing the chlorine dioxide demand in final disinfection of drinking water treatment plants using activated carbon.

    Science.gov (United States)

    Sorlini, Sabrina; Biasibetti, Michela; Collivignarelli, Maria Cristina; Crotti, Barbara Marianna

    2015-01-01

    Chlorine dioxide is one of the most widely employed chemicals in the disinfection process of a drinking water treatment plant (DWTP). The aim of this work was to evaluate the influence of the adsorption process with granular activated carbon (GAC) on the chlorine dioxide consumption in final oxidation/disinfection. A first series of tests was performed at the laboratory scale employing water samples collected at the outlet of the DWTP sand filter of Cremona (Italy). The adsorption process in batch conditions with seven different types of GAC was studied. A second series of tests was performed on water samples collected at the outlet of four GAC columns installed at the outlet of the DWTP sand filter. The results showed that the best chlorine dioxide demand (ClO2-D) reduction yields are equal to 60-80% and are achieved in the first 30 min after ClO2 addition, during the first 16 days of the column operation using a mineral, coal-based, mesoporous GAC. Therefore, this carbon removes organic compounds that are more rapidly reactive with ClO2. Moreover, a good correlation was found between the ClO2-D and UV absorbance at wavelength 254 nm using mineral carbons; therefore, the use of a mineral mesoporous GAC is an effective solution to control the high ClO2-D in the disinfection stage of a DWTP.

  14. Nevada Test Site site treatment plan. Final annual update. Revision 1

    International Nuclear Information System (INIS)

    1998-04-01

    A Site Treatment Plan (STP) is required for facilities at which the US Department of Energy Nevada Operations Office (DOE/NV) generates or stores mixed waste (MW), defined by the Federal Facility Compliance Act (FFCAct) as waste containing both a hazardous waste subject to the Resource Conservation and Recovery Act (RCRA) and a radioactive material subject to the Atomic Energy Act. This STP was written to identify specific treatment facilities for treating DOE/NV generated MW and provides proposed implementation schedules. This STP was approved by the Nevada Division of Environmental Protection (NDEP) and provided the basis for the negotiation and issuance of the FFCAct Consent Order (CO) dated March 6, 1996. The FFCAct CO sets forth stringent regulatory requirements to comply with the implementation of the STP

  15. Final height in survivors of childhood cancer compared with Height Standard Deviation Scores at diagnosis.

    Science.gov (United States)

    Knijnenburg, S L; Raemaekers, S; van den Berg, H; van Dijk, I W E M; Lieverst, J A; van der Pal, H J; Jaspers, M W M; Caron, H N; Kremer, L C; van Santen, H M

    2013-04-01

    Our study aimed to evaluate final height in a cohort of Dutch childhood cancer survivors (CCS) and assess possible determinants of final height, including height at diagnosis. We calculated standard deviation scores (SDS) for height at initial cancer diagnosis and height in adulthood in a cohort of 573 CCS. Multivariable regression analyses were carried out to estimate the influence of different determinants on height SDS at follow-up. Overall, survivors had a normal height SDS at cancer diagnosis. However, at follow-up in adulthood, 8.9% had a height ≤-2 SDS. Height SDS at diagnosis was an important determinant for adult height SDS. Children treated with (higher doses of) radiotherapy showed significantly reduced final height SDS. Survivors treated with total body irradiation (TBI) and craniospinal radiation had the greatest loss in height (-1.56 and -1.37 SDS, respectively). Younger age at diagnosis contributed negatively to final height. Height at diagnosis was an important determinant for height SDS at follow-up. Survivors treated with TBI, cranial and craniospinal irradiation should be monitored periodically for adequate linear growth, to enable treatment on time if necessary. For correct interpretation of treatment-related late effects studies in CCS, pre-treatment data should always be included.

  16. NPP Mochovce - a project of extraordinay significance

    International Nuclear Information System (INIS)

    Chwolik, I.; Debru, M.

    2000-01-01

    In this paper and in this presentation the reactor safety upgrading of two blocks of the NPP V-1 Bohunice, some results of participation on safety upgrading by the German-French consortium EUCOM (Framatome and Siemens-KWU) are presented. (author)

  17. Safety measures for NPP Mochovce - Skoda contribution

    International Nuclear Information System (INIS)

    Svec, P.

    1997-01-01

    Brief technical descriptions are given of the following issues involved in safety measures: reactor pressure vessel embrittlement and its monitoring; non-destructive testing; integrity of the steam generator primary collector; integrity of steam generator heat exchanging tubes; distribution of feedwater in the steam generator; the hazard of plugging water collectors located on the steam generator room floor; steam generator level control valves; primary circuit venting under emergency conditions; diagnostic systems installed in the primary circuit; monitoring of reactor pressure vessel head leaks; severity of containment leaks; turbine missiles; seismic design; procedures for normal operation; and operation limits and conditions. (M.D.)

  18. Slovak Electric, plc, Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    1999-01-01

    In this popular scientific brochure a brief description of construction scheme of Bohunice Nuclear Power Plant is presented. Electricity generation in a nuclear power plant is described. Instrumentation and control system as well as nuclear safety principles applied on the NPP are presented

  19. Review of selected contributions of the conference 'Suppliers and requirements for quality provision'

    International Nuclear Information System (INIS)

    2007-03-01

    There were 12 contributions presented at the conference focused on the requirements of the standard ISO 9001:2000 for supplies of services and products, especially from the point of view of supplies for nuclear power plants. Two contributions were focused in the issue of quality assurance of finishing of the building of 3. and 4. block of the Nuclear Power Plant Mochovce

  20. Determination of thermal reactivity coefficients for the first fuel loading of MO34

    International Nuclear Information System (INIS)

    Lueley, J.; Vrban, B.; Farkas, G.; Hascik, J.; Hinca, R.; Petriska, M.; Slugen, V.

    2012-01-01

    The article introduces determination of thermal reactivity coefficients, especially summarized (isothermal) and moderator (density) reactivity coefficients between 200 grad C and 260 grad C with 2 grad C step, - in compliance with the assignment - for the first fuel loading into the RC of NP Mochovce units using 2 nd generation fuel during the start-up using calculation code MCNP5 1.60. (authors)

  1. [Diagnostics and treatment of phenylketonuria].

    Science.gov (United States)

    Bayat, Allan; Møller, Libeth Birk; Lund, Allan Meldgaard

    2015-02-16

    Primary phenylalanine hydroxylase deficiency, also known as phenylketonuria, results in accumulation of phenylalanine in the blood. Early identification and treatment prevents the majority of clinical sequelae to the disease, but psychological and neurodevelopmental problems can occur in some patients. This article reviews the symptoms, diagnosis, classification and strategies of treatment and management of phenylketonuria. Finally we review new pharmacological and non-pharmaco-logical means of treatment.

  2. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposl of radioactive and hazardous waste. Volume II

    International Nuclear Information System (INIS)

    1997-01-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type.Volume II is an integral part of the Office of Environmental Management''s (EM''s) Waste Management Programmatic Environmental Impact Statement (WM PEIS), which portrays the impacts of EM''s waste management activities at each of the 17 major DOE sites evaluated in the WM PEIS

  3. Slovak Electric, plc, Environment report 1998

    International Nuclear Information System (INIS)

    1999-01-01

    A brief account of activities in environment protection carried out by the Slovenske Elektrarne, a.s. in 1998 is presented. These activities are reported under the headings: (1) The address of general director; (2) Conception of environmental protection in joint stock company SE, a.s.; (3) Air protection; (4) Water management; (5) Waste management; (6) Environmental management system in joint stock company Slovenske Elektrarne, a.s.; (7) Finances spent to protection and setting of environment; (8) Vojany power plant(SE-EVO); (9) Novaky power plant (SE-ENO); (10) Kosice power plant (SE-TEKO); (11) Trencin water power stations (SE-VET); (12) Dobsina water power stations (SE-VED); (13) Bohunice nuclear power plant (SE-EBO); (14) Mochovce nuclear power plant (SE-EMO); (15) Bratislava transmission system plant (SE-PS); (16) Bohunice radioactive waste treatment and conditioning centre

  4. Hanford 100-N Area Tracer Study Final Report

    International Nuclear Information System (INIS)

    Kretzschmar, S.P.; Bedi, G.S.; Martinez, P.; Ervin, K.

    1996-09-01

    This document provides an engineering tracer study final report for the determination of contact time for the disinfection process at Group A Nontransient Noncommunity water treatment plant for the 100- N Water Plant (located on the Hanford Site in Richland, Washington). The purpose of this study is to determine the actual detention time within the plant clearwell, and the disinfection contact time at several clearwell effluent flow rates

  5. Treatment Planning for Ion Beam Therapy

    Science.gov (United States)

    Jäkel, Oliver

    The special aspects of treatment planning for ion beams are outlined in this chapter, starting with positioning and immobilization of the patient, describing imaging and segmentation, definition of treatment parameters, dose calculation and optimization, and, finally, plan assessment, verification, and quality assurance.

  6. Occurrence of Vibrio Pathotypes in the Final Effluents of Five Wastewater Treatment Plants in Amathole and Chris Hani District Municipalities in South Africa

    Directory of Open Access Journals (Sweden)

    Vuyokazi Nongogo

    2014-08-01

    Full Text Available We assessed the occurrence of Vibrio pathogens in the final effluents of five wastewater treatment plants (WWTPs located in Amathole and Chris Hani District Municipalities in South Africa over a 12 months period between September 2012 and August 2013 using standard membrane filtration technique followed by cultivation on thiosulphate citrate-bile salts-sucrose (TCBS agar. The identities of the presumptive Vibrio isolates were confirmed using polymerase chain reaction (PCR including delineation into V. parahaemolyticus, V. vulnificus and V. fluvialis pathotypes. The counts of Vibrio spp. varied with months in all the study sites and ranged in the order of 101 and 104 CFU/100mL. Vibrio distribution also showed seasonality with high counts being obtained in autumn and spring (p < 0.05. Prevalence of Vibrio spp. among the five WWTPs also differed significantly (p < 0.05. Of the 300 isolates that were confirmed as belonging to the Vibrio genus, 29% (86 were V. fluvialis, 28% (84 were V. vulnificus and 12% (35 were V. parahaemolyticus. The isolation of Vibrio pathogens from the final effluent suggests that this pathogen is in circulation in some pockets of the population and that the WWTPs under study do not efficiently remove bacterial pathogens from the wastewater and consequently are threats to public health.

  7. Final 5-Year Study Results of DASISION: The Dasatinib Versus Imatinib Study in Treatment-Naïve Chronic Myeloid Leukemia Patients Trial.

    Science.gov (United States)

    Cortes, Jorge E; Saglio, Giuseppe; Kantarjian, Hagop M; Baccarani, Michele; Mayer, Jiří; Boqué, Concepción; Shah, Neil P; Chuah, Charles; Casanova, Luis; Bradley-Garelik, Brigid; Manos, George; Hochhaus, Andreas

    2016-07-10

    We report the 5-year analysis from the phase III Dasatinib Versus Imatinib Study in Treatment-Naïve Chronic Myeloid Leukemia Patients (DASISION) trial, evaluating long-term efficacy and safety outcomes of patients with chronic myeloid leukemia (CML) in chronic phase (CP) treated with dasatinib or imatinib. Patients with newly diagnosed CML-CP were randomly assigned to receive dasatinib 100 mg once daily (n = 259) or imatinib 400 mg once daily (n = 260). At the time of study closure, 61% and 63% of dasatinib- and imatinib-treated patients remained on initial therapy, respectively. Cumulative rates of major molecular response and molecular responses with a 4.0- or 4.5-log reduction in BCR-ABL1 transcripts from baseline by 5 years remained statistically significantly higher for dasatinib compared with imatinib. Rates for progression-free and overall survival at 5 years remained high and similar across treatment arms. In patients who achieved BCR-ABL1 ≤ 10% at 3 months (dasatinib, 84%; imatinib, 64%), improvements in progression-free and overall survival and lower rates of transformation to accelerated/blast phase were reported compared with patients with BCR-ABL1 greater than 10% at 3 months. Transformation to accelerated/blast phase occurred in 5% and 7% of patients in the dasatinib and imatinib arms, respectively. Fifteen dasatinib-treated and 19 imatinib-treated patients had BCR-ABL1 mutations identified at discontinuation. There were no new or unexpected adverse events identified in either treatment arm, and pleural effusion was the only drug-related, nonhematologic adverse event reported more frequently with dasatinib (28% v 0.8% with imatinib). First occurrences of pleural effusion were reported with dasatinib, with the highest incidence in year 1. Arterial ischemic events were uncommon in both treatment arms. These final results from the DASISION trial continue to support dasatinib 100 mg once daily as a safe and effective first-line therapy for the long

  8. Activities of the Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear facilities in the Slovak Republic in 1994

    International Nuclear Information System (INIS)

    1995-01-01

    The report summarizes activities of the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1994 and briefly presents results of the national expert supervision over nuclear safety facilities in the SR in 1994. In 1994, the NRA SR have performed a national supervision of following organizations: SE, a.s. - Jaslovske Bohunice Nuclear Power Plant (V-1 Nuclear Power Plant (V-1 NPP), V-2 Nuclear Power Plant (V-2 NPP), A-1 Nuclear Power Plant (A-1 NPP)); Mochovce Nuclear Power Plant; Radioactive waste repository, Mochovce); Organizations providing a specialized training of NPP personnel; Organizations providing specific deliveries and activities for the nuclear power industry; Organizations having an owner of nuclear materials; Organizations providing activities related to import of radioactive sources; Organizations using radioactive sources. Organization structure of the NRA SR is explained. In the presented Chapter 1 - Safety of nuclear power plants in the Slovak Republic - safety aspects of the Slovak NPPs are reported. The next activities are reported: nuclear materials and safeguards; radioactive waste; emergency planning and NRA SR's control and crisis centre; international activities to improve the national surveillance quality; other activities

  9. Treatment of thyroid associated ophthalmopathy with periocular injections of triamcinolone

    Science.gov (United States)

    Ebner, R; Devoto, M H; Weil, D; Bordaberry, M; Mir, C; Martinez, H; Bonelli, L; Niepomniszcze, H

    2004-01-01

    Aim: To evaluate the efficacy of periocular triamcinolone acetonide for the treatment of thyroid associated ophthalmopathy (TAO), and the presence of ocular or systemic adverse effects. Methods: A multicentre prospective pilot study was performed on patients diagnosed with Graves’ ophthalmopathy less than 6 months before entry to the study. Patients were admitted to the study and were randomised into two groups: treatment and control. The treatment group received four doses of 20 mg of triamcinolone acetate 40 mg/ml in a peribulbar injection to the inferolateral orbital quadrant. Both groups were evaluated by measuring the area of binocular vision without diplopia on a Goldmann perimeter and the size of the extraocular muscles on computed tomography (CT) scans. Ophthalmological and systemic examinations were done to rule out ocular and systemic adverse effects. Follow up was 6 months for both groups. Results: 50 patients were eligible for the study. 41 patients completed the study. There was an increase in the area of binocular vision without diplopia in the treatment group (Σ initial: mean 231.1 (SD 99.9) and final absolute change, mean 107.1 (SD 129.0)) compared to the control group (Σ initial: mean 350.7 (SD 86.5) and final absolute change, mean −4.5 (SD 67.6)). The sizes of the extraocular muscles were reduced in the treatment group (mean (inferior rectus initial values): 1.3 (0.7), final percentage change: −13.2 (25.7), medial rectus initial values: 1.2 (0.6), final percentage change: −8.2 (20.7), superior rectus-levator palpebrae initial values: 1.2 (0.6), final percentage change: −9.5 (29.1), lateral rectus initial values: 1.0 (0.4), final percentage change: −11.5 (20.6)) compared to the control group (inferior rectus initial values: 0.9 (0.3), final percentage change: −4.0 (21.5), medial rectus initial values: 0.9 (0.3), final percentage change: 0.6 (22.4), superior rectus-levator palpebrae initial values: 0.9 (0.3), final percentage change

  10. BNL Building 650 lead decontamination and treatment feasibility study. Final report

    International Nuclear Information System (INIS)

    Kalb, P.D.; Cowgill, M.G.; Milian, L.W.

    1995-10-01

    Lead has been used extensively at Brookhaven National Laboratory (BNL) for radiation shielding in numerous reactor, accelerator and other research programs. A large inventory of excess lead (estimated at 410,000 kg) in many shapes and sizes is currently being stored. Due to it's toxicity, lead and soluble lead compounds are considered hazardous waste by the Environmental Protection Agency. Through use at BNL, some of the lead has become radioactive, either by contamination of the surface or through activation by neutrons or deuterons. This study was conducted at BNL's Environmental and Waste Technology Center for the BNL Safety and Environmental Protection Division to evaluate feasibility of various treatment options for excess lead currently being stored. The objectives of this effort included investigating potential treatment methods by conducting a review of the literature, developing a means of screening lead waste to determine the radioactive characteristics, examining the feasibility of chemical and physical decontamination technologies, and demonstrating BNL polyethylene macro-encapsulation as a means of treating hazardous or mixed waste lead for disposal. A review and evaluation of the literature indicated that a number of physical and chemical methods are available for decontamination of lead. Many of these techniques have been applied for this purpose with varying degrees of success. Methods that apply mechanical techniques are more appropriate for lead bricks and sheet which contain large smooth surfaces amenable to physical abrasion. Lead wool, turnings, and small irregularly shaped pieces would be treated more effectively by chemical decontamination techniques. Either dry abrasion or wet chemical methods result in production of a secondary mixed waste stream that requires treatment prior to disposal

  11. FINAL REPORT: Transformational electrode drying process

    Energy Technology Data Exchange (ETDEWEB)

    Claus Daniel, C.; Wixom, M.(A123 Systems, Inc.)

    2013-12-19

    This report includes major findings and outlook from the transformational electrode drying project performance period from January 6, 2012 to August 1, 2012. Electrode drying before cell assembly is an operational bottleneck in battery manufacturing due to long drying times and batch processing. Water taken up during shipment and other manufacturing steps needs to be removed before final battery assembly. Conventional vacuum ovens are limited in drying speed due to a temperature threshold needed to avoid damaging polymer components in the composite electrode. Roll to roll operation and alternative treatments can increase the water desorption and removal rate without overheating and damaging other components in the composite electrode, thus considerably reducing drying time and energy use. The objective of this project was the development of an electrode drying procedure, and the demonstration of processes with no decrease in battery performance. The benchmark for all drying data was an 80°C vacuum furnace treatment with a residence time of 18 – 22 hours. This report demonstrates an alternative roll to roll drying process with a 500-fold improvement in drying time down to 2 minutes and consumption of only 30% of the energy compared to vacuum furnace treatment.

  12. Competence for Contract and Competence to Consent to Treatment

    OpenAIRE

    前田, 泰

    2008-01-01

    This paper analyzes assessing competence to consent to treatment. It focuses on problems of competence for contract and competence to consent to treatment. Finally, it discusses the degree of assessing competence to consent to treatment.

  13. International Youth Nuclear Congress 2000. Film

    International Nuclear Information System (INIS)

    OST Film Production Studio; YDRNS Information Technology Services, Ltd.

    2001-01-01

    This CD-ROM contains 28 minutes 30 seconds of video-film about programme of International Youth Nuclear Congress 2000 (IYNC 2000). There is documentary video-film about IYNC 2000, also presented are: the Opening panel of the IYNC 2000, every day work of IYNC 2000, Congress people; the fun run; Entertainment excursion in Bratislava, about excursion in Mochovce NPP as well as in IAEA

  14. Hyper-attenuating brain lesions on CT after ischemic stroke and thrombectomy are associated with final brain infarction.

    Science.gov (United States)

    Cabral, F B; Castro-Afonso, L H; Nakiri, G S; Monsignore, L M; Fábio, Src; Dos Santos, A C; Pontes-Neto, O M; Abud, D G

    2017-12-01

    Purpose Hyper-attenuating lesions, or contrast staining, on a non-contrast brain computed tomography (NCCT) scan have been investigated as a predictor for hemorrhagic transformation after endovascular treatment of acute ischemic stroke (AIS). However, the association of hyper-attenuating lesions and final ischemic areas are poorly investigated in this setting. The aim of the present study was to assess correlations between hyper-attenuating lesions and final brain infarcted areas after thrombectomy for AIS. Methods Data from patients with AIS of the anterior circulation who underwent endovascular treatment were retrospectively assessed. Images of the brain NCCT scans were analyzed in the first hours and late after treatment. The hyper-attenuating areas were compared to the final ischemic areas using the Alberta Stroke Program Early CT Score (ASPECTS). Results Seventy-one of the 123 patients (65.13%) treated were included. The association between the hyper-attenuating region in the post-thrombectomy CT scan and final brain ischemic area were sensitivity (58.3% to 96.9%), specificity (42.9% to 95.6%), positive predictive values (71.4% to 97.7%), negative predictive values (53.8% to 79.5%), and accuracy values (68% to 91%). The highest sensitivity values were found for the lentiform (96.9%) and caudate nuclei (80.4%) and for the internal capsule (87.5%), and the lowest values were found for the M1 (58.3%) and M6 (66.7%) cortices. Conclusions Hyper-attenuating lesions on head NCCT scans performed after endovascular treatment of AIS may predict final brain infarcted areas. The prediction appears to be higher in the deep brain regions compared with the cortical regions.

  15. Solid waste containing persistent organic pollutants in Serbia: From precautionary measures to the final treatment (case study).

    Science.gov (United States)

    Stevanovic-Carapina, Hristina; Milic, Jelena; Curcic, Marijana; Randjelovic, Jasminka; Krinulovic, Katarina; Jovovic, Aleksandar; Brnjas, Zvonko

    2016-07-01

    Sustainable solid waste management needs more dedicated attention in respect of environmental and human health protection. Solid waste containing persistent organic pollutants is of special concern, since persistent organic pollutants are persistent, toxic and of high risk to human health and the environment. The objective of this investigation was to identify critical points in the Serbian system of solid waste and persistent organic pollutants management, to assure the life cycle management of persistent organic pollutants and products containing these chemicals, including prevention and final destruction. Data were collected from the Serbian competent authorities, and led us to identify preventive actions for solid waste management that should reduce or minimise release of persistent organic pollutants into the environment, and to propose actions necessary for persistent organic pollutants solid waste. The adverse impact of persistent organic pollutants is multidimensional. Owing to the lack of treatment or disposal plants for hazardous waste in Serbia, the only option at the moment to manage persistent organic pollutants waste is to keep it in temporary storage and when conditions are created (primarily financial), such waste should be exported for destruction in hazardous waste incinerators. Meanwhile, it needs to be assured that any persistent organic pollutants management activity does not negatively impact recycling flows or disturb progress towards a more circular economy in Serbia. © The Author(s) 2016.

  16. Final Environmental Impact Statement (FEIS)/Final Environmental Impact Report (FEIR). Otis Air National Guard Base, Wastewater Treatment Facility

    Science.gov (United States)

    1990-06-01

    and G.E. Ness, 1982, Survival of Vibrio cholerae and Escherichia coli in Estuarine Water and Sediments, Applied and Environmental Microbiology, 43...and publications in areas of water and wastewater treatment. David Tomasko, Ph.D., 1985. University of New Mexico . Staff Hydrogeologist. Research...Reserve in California. We are working on EIS’s for the U.S. Air Force Base Closings in realignment in California, New Mexico and Washington, and a very

  17. 42 CFR 8.34 - Court review of final administrative action; exhaustion of administrative remedies.

    Science.gov (United States)

    2010-10-01

    ... HEALTH AND HUMAN SERVICES GENERAL PROVISIONS CERTIFICATION OF OPIOID TREATMENT PROGRAMS Procedures for... Withdrawal of Approval of an Accreditation Body § 8.34 Court review of final administrative action...

  18. Narrative Finality

    Directory of Open Access Journals (Sweden)

    Armine Kotin Mortimer

    1981-01-01

    Full Text Available The cloturai device of narration as salvation represents the lack of finality in three novels. In De Beauvoir's Tous les hommes sont mortels an immortal character turns his story to account, but the novel makes a mockery of the historical sense by which men define themselves. In the closing pages of Butor's La Modification , the hero plans to write a book to save himself. Through the thrice-considered portrayal of the Paris-Rome relationship, the ending shows the reader how to bring about closure, but this collective critique written by readers will always be a future book. Simon's La Bataille de Pharsale , the most radical attempt to destroy finality, is an infinite text. No new text can be written. This extreme of perversion guarantees bliss (jouissance . If the ending of De Beauvoir's novel transfers the burden of non-final world onto a new victim, Butor's non-finality lies in the deferral to a future writing, while Simon's writer is stuck in a writing loop, in which writing has become its own end and hence can have no end. The deconstructive and tragic form of contemporary novels proclaims the loss of belief in a finality inherent in the written text, to the profit of writing itself.

  19. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Gurney, Kevin R. [Arizona Univ., Mesa, AZ (United States)

    2015-01-12

    This document constitutes the final report under DOE grant DE-FG-08ER64649. The organization of this document is as follows: first, I will review the original scope of the proposed research. Second, I will present the current draft of a paper nearing submission to Nature Climate Change on the initial results of this funded effort. Finally, I will present the last phase of the research under this grant which has supported a Ph.D. student. To that end, I will present the graduate student’s proposed research, a portion of which is completed and reflected in the paper nearing submission. This final work phase will be completed in the next 12 months. This final workphase will likely result in 1-2 additional publications and we consider the results (as exemplified by the current paper) high quality. The continuing results will acknowledge the funding provided by DOE grant DE-FG-08ER64649.

  20. Ozone/UV treatment to enhance biodegradation of surfactants in industrial wastewater. CRADA final report

    Energy Technology Data Exchange (ETDEWEB)

    Cline, J.E. [Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States); Sullivan, P.F. [Specialty Industrial Products, Inc., Spartanburg, SC (United States); Lovejoy, M.A.; Collier, J. [Sun River Innovations, Ltd., Lexington, KY (United States); Adams, C.D. [Univ. of Missouri, Rolla, MO (United States)

    1996-10-01

    The new owners of a surfactant manufacturing plant wanted to triple production but were limited by the plant`s wastewater treatment capacity. Mass balance calculations indicated that little aerobic biodegradation was occurring in the plant`s wastewater treatment system. Literature reviews and laboratory tests confirmed that as much as 60% of the plant`s products might resist aerobic biodegradation. Overall chemical losses, both solid and aqueous, were estimated at 3.8% of theoretical. Organic loadings to the wastewater treatment system were 170 kg/d of which 50 kg/d reached the biological treatment system. Pollution prevention measures have allowed a > 20% increase in production levels with a > 30% decrease in effluent volume and no increase in discharge of chemical oxygen demand (COD). A new dissolved air flotation (DAF) system removes 70% of the organic loading. Sludge volumes are lower by an order of magnitude than with the clarifier/drum-filter process it replaced.

  1. Dimensional Behavior of Matrix Graphite Compacts during Heat Treatments for HTGR Fuel Element Fabrication

    International Nuclear Information System (INIS)

    Lee, Young-Woo; Yeo, Seunghwan; Cho, Moon Sung

    2015-01-01

    The carbonization is a process step where the binder that is incorporated during the matrix graphite powder preparation step is evaporated and the residue of the binder is carbonized during the heat treatment at about 1073 K. This carbonization step is followed by the final high temperature heat treatment where the carbonized compacts are heat treated at 2073-2173 K in vacuum for a relatively short time (about 2 hrs). In order to develop a fuel compact fabrication technology, and for fuel matrix graphite to meet the required material properties, it is essential to investigate the relationship among the process parameters of the matrix graphite powder preparation, the fabrication parameters of fuel element green compact and the heat treatments conditions, which has a strong influence on the further steps and the material properties of fuel element. In this work, the dimensional changes of green compacts during the carbonization and final heat treatment are evaluated when compacts have different densities from different pressing conditions and different final heat treatment temperatures are employed, keeping other process parameters constant, such as the binder content, carbonization time, temperature and atmosphere (two hours ant 1073K and N2 atmosphere). In this work, the dimensional variations of green compacts during the carbonization and final heat treatment are evaluated when compacts have different densities from different pressing conditions and different final heat treatment temperatures are employed

  2. Final Scientific Report: DE-SC0002194

    Energy Technology Data Exchange (ETDEWEB)

    Seidler, Gerald [Univ. of Washington, Seattle, WA (United States)

    2017-04-07

    We provide the final scientific report for DE-SC0002194. During the term of this grant, 28 publications spanning a variety of topics were addressed under the rubric of advanced x-ray methods and their application to extreme conditions of time-resolution or x-ray intensities. Notable accomplishments include a new observation of XANES features associated with f-shell reconfiguration in lanthanides, size-dependent x-ray heating effects under XFEL illumination conditions, theoretical development of improved treatments of inelastic x-ray scattering for 'warm dense matter' conditions, and several new instrument develop efforts for atomic, molecular, and condensed phase studies in the lab and at major facility lightsources.

  3. Historical performance evaluation of Iowa pavement treatments using data analytics : final report.

    Science.gov (United States)

    2016-11-01

    The pavement network in Iowa has reached a mature state making maintenance and rehabilitation activities more important than new construction. As such, a need exists to evaluate the performance of the pavement treatments and estimate their performanc...

  4. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Schuur, Edward [Northern Arizona Univ., Flagstaff, AZ (United States); Luo, Yiqi [Univ. of Oklahoma, Norman, OK (United States)

    2016-12-01

    This final grant report is a continuation of the final grant report submitted for DE-SC0006982 as the Principle Investigator (Schuur) relocated from the University of Florida to Northern Arizona University. This report summarizes the original project goals, as well as includes new project activities that were completed in the final period of the project.

  5. Curve identification for high friction surface treatment (HFST) installation recommendation : final report.

    Science.gov (United States)

    2016-09-01

    The objectives of this study are to develop and deploy a means for cost-effectively extracting curve information using the widely available GPS and GIS data to support high friction surface treatment (HFST) installation recommendations (i.e., start a...

  6. PRIMAVERA - the experience of the utilization at the completion MO34

    International Nuclear Information System (INIS)

    Porubsky, S.

    2009-01-01

    Today, it is not possible to provide the required quality of neither the process nor the project's outputs without suitable software management support. It is necessary to remember, that the software management support of the big projects is necessary, not just sufficient condition for successful implementation of the project. The following contribution describes the experience with the software support setting for completion project of units 3. and 4. of NPP Mochovce

  7. Transport of radioactive wastes

    International Nuclear Information System (INIS)

    Stuller, C.

    2003-01-01

    In this article author describes the system of transport and processing of radioactive wastes from nuclear power of Slovenske elektrarne, plc. It is realized the assurance of transport of liquid and solid radioactive wastes to processing links from places of their formation, or of preliminary storage and consistent transports of treated radioactive wastes fixed in cement matrix of fibre-concrete container into Rebublic storage of radioactive wastes in Mochovce

  8. Part I. Remembering No. 2 (Ladislav Loerinc). EMO joint venture, joint-stock company - really completely useless organ?

    International Nuclear Information System (INIS)

    Blaha, M.

    2008-01-01

    In this chapter author reviewed the story of the EMO joint venture, joint-stock company, between Slovenske elektrarne, a. s. and EdF. EMO joint venture, joint-stock company, was established to complete the Mochovce nuclear power plant. EMO joint venture, joint-stock company was closed after one year of work. History of EMO joint venture, joint-stock company, was described by its former general manager Mr. Ladislav Loerinc.

  9. Final treatment of spent batteries by thermal plasma.

    Science.gov (United States)

    Cubas, Anelise Leal Vieira; Machado, Marina de Medeiros; Machado, Marília de Medeiros; Dutra, Ana Regina de Aguiar; Moecke, Elisa Helena Siegel; Fiedler, Haidi D; Bueno, Priscila

    2015-08-15

    The growth in the use of wireless devices, notebooks and other electronic products has led to an ever increasing demand for batteries, leading to these products being commonly found in inappropriate locations, with adverse effects on the environment and human health. Due to political pressure and according to the environmental legislation which regulates the destination of spent batteries, in several countries the application of reverse logistics to hazardous waste is required. Thus, some processes have been developed with the aim of providing an appropriate destination for these products. In this context, a method for the treatment of spent batteries using thermal plasma technology is proposed herein. The efficiency of the method was tested through the determination of parameters, such as total organic carbon, moisture content and density, as well as analysis by atomic absorption spectrometry, scanning electron microscopy and X-ray fluorescence using samples before and after inertization. The value obtained for the density was 19.15%. The TOC results indicated 8.05% of C in the batteries prior to pyrolisis and according to the XRF analysis Fe, S, Mn and Zn were the most stable elements in the samples (highest peaks). The efficiency of the paste inertization was 97% for zinc and 99.74% for manganese. The results also showed that the most efficient reactor was that with the DC transferred arc plasma torch and quartzite sand positively influenced by the vitrification during the pyrolysis of the electrolyte paste obtain from batteries. Copyright © 2015. Published by Elsevier Ltd.

  10. Treatment selection in a randomized clinical trial via covariate-specific treatment effect curves.

    Science.gov (United States)

    Ma, Yunbei; Zhou, Xiao-Hua

    2017-02-01

    For time-to-event data in a randomized clinical trial, we proposed two new methods for selecting an optimal treatment for a patient based on the covariate-specific treatment effect curve, which is used to represent the clinical utility of a predictive biomarker. To select an optimal treatment for a patient with a specific biomarker value, we proposed pointwise confidence intervals for each covariate-specific treatment effect curve and the difference between covariate-specific treatment effect curves of two treatments. Furthermore, to select an optimal treatment for a future biomarker-defined subpopulation of patients, we proposed confidence bands for each covariate-specific treatment effect curve and the difference between each pair of covariate-specific treatment effect curve over a fixed interval of biomarker values. We constructed the confidence bands based on a resampling technique. We also conducted simulation studies to evaluate finite-sample properties of the proposed estimation methods. Finally, we illustrated the application of the proposed method in a real-world data set.

  11. An Approach for Practical Multiobjective IMRT Treatment Planning

    International Nuclear Information System (INIS)

    Craft, David; Halabi, Tarek; Shih, Helen A.; Bortfeld, Thomas

    2007-01-01

    Purpose: To introduce and demonstrate a practical multiobjective treatment planning procedure for intensity-modulated radiation therapy (IMRT) planning. Methods and Materials: The creation of a database of Pareto optimal treatment plans proceeds in two steps. The first step solves an optimization problem that finds a single treatment plan which is close to a set of clinical aspirations. This plan provides an example of what is feasible, and is then used to determine mutually satisfiable hard constraints for the subsequent generation of the plan database. All optimizations are done using linear programming. Results: The two-step procedure is applied to a brain, a prostate, and a lung case. The plan databases created allow for the selection of a final treatment plan based on the observed tradeoffs between the various organs involved. Conclusions: The proposed method reduces the human iteration time common in IMRT treatment planning. Additionally, the database of plans, when properly viewed, allows the decision maker to make an informed final plan selection

  12. 40 CFR 61.134 - Standard: Naphthalene processing, final coolers, and final-cooler cooling towers.

    Science.gov (United States)

    2010-07-01

    ... coolers, and final-cooler cooling towers. 61.134 Section 61.134 Protection of Environment ENVIRONMENTAL... Standard: Naphthalene processing, final coolers, and final-cooler cooling towers. (a) No (“zero”) emissions are allowed from naphthalene processing, final coolers and final-cooler cooling towers at coke by...

  13. Confidence level in performing endodontic treatment among final year undergraduate dental students from the University of Medical Science and Technology, Sudan (2014

    Directory of Open Access Journals (Sweden)

    Elhadi Mohieldin Awooda

    2016-01-01

    Full Text Available Aim: This study is aimed to evaluate the confidence level of undergraduate final year dental students in performing root canal treatment (RCT and how it may affect their performance and perception regarding endodontics. Materials and Methods: A self-administered questionnaire was distributed to the final year dental students, at the University of Medical Sciences and Technology, Khartoum, Sudan (2013–2014. A total of 21 students were requested to participate voluntary and were asked to score their level of confidence using a 5-point Likert's scale. Results: Response rate was 100%, all the students (100% stated that the requirements set were enough, and 66.7% rated endodontic as average in terms of difficulty. When rating the mean of self-confidence for performing RCT in the dentition, maxillary teeth (2.43 ± 0.51 followed by mandibular teeth (2.71 ± 0.64 were higher, whereas the molars were the least. Higher scores of self-confidence were in administrating local anesthesia (4.24 ± 0.70, followed by root canal shaping by hand instrument (3.76 ± 0.54. No association was found between overall confidence level and the number of performed RCT (P = 0.721. No association was found between overall confidence level of students who were subjected to instrument fracture and their frequency of fracture (P = 0.507, supervisor' reaction (P = 0.587, and willingness to specialize in endodontics (P = 0.530. Conclusion: Students displayed high confidence in performing basic endodontic and treating single-rooted teeth. More exposure is recommended to enhance the students' self-confidence.

  14. On Darwin's 'metaphysical notebooks'. II: "Metaphysics" and final cause.

    Science.gov (United States)

    Calabi, L

    2001-01-01

    The first part of this paper was published in Rivista di Biologia/Biology Forum 94 (2001). In the second part below an examination is made of the meaning of the term Metaphysics in some passages of the Darwinian Notebooks for the years 1836-1844. Metaphysics no longer defines a field of philosophical enquiries mainly concerning the being and the essence after the manner of Aristotle; it now refers to a kind of philosophy of mind after the manner of J. Locke's criticism of the Hypokeimenon. However Aristotle's Metaphysics also encompasses a treatment of the idea of causes, and of final cause particularly, in the explanation of events, and in the explanation of natural phenomena especially. The criticism of the idea of final cause in the interpretation of the world of life is one of Darwin's foundational acts in his early years. When conceiving his Système du monde, in the last years of the XVIII Century, Laplace could think that God is a hypothesis not really needed by science, as we are told. For the knowledge of organic nature to attain the status of science, it remained to be shown that since--certain of the exemplariness of Newton's Principles as much as cautious before the mystery of life--did not need the hypothesis of final ends in order to understand and explain the productions of the living nature: not only in the form of that final cause (the First Cause, the Vera Causa) in which Natural Theology still rested, but also in the form of nature's inner finality which still moulded Whewell's Kantian philosophy. Such demonstration is a very important subject in Darwin's early enquiries, where he criticises finalism as a projection of self-conceiving Man, likely inherited from a knowing of causality in nuce to be found also in animals.

  15. There's no Nuclear Future without the Young

    International Nuclear Information System (INIS)

    Petrech, R.; Holy, R.

    2002-01-01

    Construction of Mochovce NPP started in 1981 - i.e. more than 20 years ago, however it was halted in early 90's after velvet Revolution in former Czechoslovakia. When the (I and C) system was decided in 1989 to be replaced with a state-of-the-art system of Siemens, and it was implemented in early 1990-1, the utility lacked money for further works and building works had to be halted. We were consequently thrown in difficult public and expert debates about the nuclear future: do we really need it? Nuclear is looking for new ways to persuade the public about the need to keep nuclear as a part of the world energy mix. For experts it is clear. It has already been indicated in the Green Book - a report about the future electricity demand coverage by diverse sources made out for the EC. The role of the young people is indispensable in this process. Information campaigns are focused mostly on youngsters from the very young age whose opinions are being formed. Only a long-lasting systematic work with the youth can bring better public opinion. About 95 % of Mochovce NPP visitors are students (mostly primary and secondary schools) - that is important.(author)

  16. Response to growth hormone treatment and final height after cranial or craniospinal irradiation

    International Nuclear Information System (INIS)

    Sulmont, V.; Brauner, R.; Fontoura, M.; Rappaport, R.

    1990-01-01

    Growth hormone (GH) deficiency (GHD) induced by cranial irradiation has become a frequent indication of hGH substitutive therapy. This study analyses the growth response to hGH therapy and the factors involved in the decrease in growth velocity observed after cranial irradiation. One hundred children given cranial radiation for pathology distant from the hypothalamo-pituitary area were studied. Fifty-six of them received hGH therapy for GHD resulting in decreased growth velocity. The initial annual height gain in the cranial-irradiated group was comparable to that of patients treated for idiopathic GHD; additional spinal irradiation significantly reduced the growth response. Twenty-eight hGH-treated patients reached final heights which were compared to those of 2 untreated irradiated groups, one with GHD (n=27) and the other with normal GH secretion (n=17). The height SD score changes observed in hGH therapy were +0.3 in the cranial (n=10) and -1.2 SD in the craniospinal (n=18) groups. GH deficiency had contributed to a mean height loss of 1 SD and spinal irradiation to a loss of 1.4SD. The small effect of hGH therapy on final height is probably linked to the small bone age retardation at onset of hGH therapy and to the fact that irradiated children entered puberty at a younger age in terms of chronological age and bone age than the idiopathic GHD patients. These data suggest that the results of gGH therapy in irradiated children might be improved with higher and more fractionated hGH doses and, in some patients, by delaying puberty using luteinizing hormone releasing hormone analogs

  17. Response to growth hormone treatment and final height after cranial or craniospinal irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Sulmont, V.; Brauner, R.; Fontoura, M.; Rappaport, R. (Hospital des Enfants Malades, Paris (France). Pediatric Endocrinology Unit and INSERM U30)

    1990-01-01

    Growth hormone (GH) deficiency (GHD) induced by cranial irradiation has become a frequent indication of hGH substitutive therapy. This study analyses the growth response to hGH therapy and the factors involved in the decrease in growth velocity observed after cranial irradiation. One hundred children given cranial radiation for pathology distant from the hypothalamo-pituitary area were studied. Fifty-six of them received hGH therapy for GHD resulting in decreased growth velocity. The initial annual height gain in the cranial-irradiated group was comparable to that of patients treated for idiopathic GHD; additional spinal irradiation significantly reduced the growth response. Twenty-eight hGH-treated patients reached final heights which were compared to those of 2 untreated irradiated groups, one with GHD (n=27) and the other with normal GH secretion (n=17). The height SD score changes observed in hGH therapy were +0.3 in the cranial (n=10) and -1.2 SD in the craniospinal (n=18) groups. GH deficiency had contributed to a mean height loss of 1 SD and spinal irradiation to a loss of 1.4SD. The small effect of hGH therapy on final height is probably linked to the small bone age retardation at onset of hGH therapy and to the fact that irradiated children entered puberty at a younger age in terms of chronological age and bone age than the idiopathic GHD patients. These data suggest that the results of gGH therapy in irradiated children might be improved with higher and more fractionated hGH doses and, in some patients, by delaying puberty using luteinizing hormone releasing hormone analogs.

  18. Mixed-waste treatment -- What about the residuals?

    International Nuclear Information System (INIS)

    Carlson, T.; Carpenter, C.; Cummins, L.; Haas, P.; MacInnis, J.; Maxwell, C.

    1993-01-01

    Incineration currently is the best demonstrated available technology for the large inventory of U.S. Department of Energy (DOE) mixed waste. However, molten salt oxidation (MSO) is an alternative thermal treatment technology with the potential to treat a number of these wastes. Of concern for both technologies is the final waste forms, or residuals, that are generated by the treatment process. An evaluation of the two technologies focuses on 10 existing DOE waste streams and current hazardous-waste regulations, specifically for the delisting of ''derived-from'' residuals. Major findings include that final disposal options are more significantly impacted by the type of waste treated and existing regulations than by the type of treatment technology; typical DOE waste streams are not good candidates for delisting; and mass balance calculations indicate that MSO and incineration generate similar quantities (dry) and types of residuals

  19. Slovenske elektrarne, Mochovce nuclear power plant. Safety strategy

    International Nuclear Information System (INIS)

    1999-01-01

    In this leaflet the Management's declaration is presented. This declaration contains: operation management and quality assurance, plant commissioning, maintenance and repairs, reactor physics, radiation protection, surveillance programmes, events analyses and experience feed-back, accident management procedures and training, emergency planning and preparedness review of safety performance, human resources, and personnel responsibility

  20. Critical modeling parameters identified for 3D CFD modeling of rectangular final settling tanks for New York City wastewater treatment plants.

    Science.gov (United States)

    Ramalingam, K; Xanthos, S; Gong, M; Fillos, J; Beckmann, K; Deur, A; McCorquodale, J A

    2012-01-01

    New York City Environmental Protection is in the process of incorporating biological nitrogen removal (BNR) in its wastewater treatment plants (WWTPs) which entails operating the aeration tanks with higher levels of mixed liquor suspended solids (MLSS) than a conventional activated sludge process. The objective of this paper is to discuss two of the important parameters introduced in the 3D CFD model that has been developed by the City College of New York (CCNY) group: (a) the development of the 'discrete particle' measurement technique to carry out the fractionation of the solids in the final settling tank (FST) which has critical implications in the prediction of the effluent quality; and (b) the modification of the floc aggregation (K(A)) and floc break-up (K(B)) coefficients that are found in Parker's flocculation equation (Parker et al. 1970, 1971) used in the CFD model. The dependence of these parameters on the predictions of the CFD model will be illustrated with simulation results on one of the FSTs at the 26th Ward WWTP in Brooklyn, NY.

  1. Sewage Treatment Plants: Standards of Performance for New Stationary Sources 1977 Final Rule (42 FR 58520)

    Science.gov (United States)

    This document includes a copy of the Federal Register publication of the November 10, 1977 Final Rule for the Standards of Performance of New Stationary Sources for 40 CFR 60 Subparts O. This document is provided curtesy of HeinOnline.

  2. Comprehensive supernate treatment

    International Nuclear Information System (INIS)

    Egan, B.Z.; Collins, J.L.; Davidson, D.J.; Anderson, K.K.; Chase, C.W.

    1996-01-01

    This task involves the recovery of the liquid (supernatant or supernate) portions of Oak Ridge National Laboratory (ORNL) Melton Valley Storage Tank waste in a hot cell and treatment of the supernate to separate and remove the radionuclides. The supernate is utilized in testing various sorbent materials for removing cesium, strontium, and technetium from the highly alkaline, saline solutions. Batch tests are used to evaluate and select the most promising materials for supernate treatment to reduce the amount of waste for final disposal. Once the sorbents have been selected based on the results from the batch tests, small column tests are made to verify the batch data. Additional data from these tests can be used for process design. The sorption tests emphasize evaluation of newly developed sorbents and engineered forms of sorbents. Methods are also evaluated for recovering the radionuclides from the sorbents, including evaluating conditions for eluting ion exchange resins. A final report will summarize the results and compare the results with those of other investigators, along with recommendations for separating and concentrating radionuclides from DOE storage tank supernates at Oak Ridge and other sites. Documentation of the data and the significance of the findings will be compared, and recommendations will be provided to likely users of the data in EM-30. This program also provides input to the supernate treatment process demonstration projects at ORNL

  3. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume IV of V

    International Nuclear Information System (INIS)

    1997-01-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type.Transportation is an integral component of the alternatives being considered for each type of radioactive waste in the U.S. Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The types of radioactive waste considered in Part I are high-level waste (HLW), low-level waste (LLW), transuranic waste (TRUW), and low-level mixed waste (LLMW). For some alternatives, radioactive waste would be shipped among the DOE sites at various stages of the treatment, storage, and disposal (TSD) process. The magnitude of the transportation-related activities varies with each alternative, ranging from minimal transportation for decentralized approaches to significant transportation for some centralized approaches. The human health risks associated with transporting various waste materials were assessed to ensure a complete appraisal of the impacts of each PEIS alternative being considered

  4. Advantages of viscodampers for NPPs upgrading

    International Nuclear Information System (INIS)

    Reinsch, K.H.; Schwahn, K.J.; Podrouzek, J.

    1993-01-01

    Viscodampers GERB are the ideal components for seismic upgrading of flexible pipework systems of the existing operating NPPs, of WWER-440 type, namely in primary reactor part. There are cheap, maintenance-free, simple and their installation minimizes the support forces to the structures. The quoted attests are enclosed in this paper. The references for application on Bohunice NPP upgrading are positive, and they are used in Mochovce and Temelin NPP as well

  5. Investigation and analysis of SSI effects in seismic response of NPPs EMO and EBO

    International Nuclear Information System (INIS)

    Juhasova, E.

    1996-01-01

    This progress report outlines and describes the analysis and investigations of soil-structure interaction effects in seismic response of Bohunice and Mochovce nuclear power plants. The work carries out consists of theoretical-numerical analysis of soil-structure interaction and the description of the experimental results obtained so far. Investigations were performed for different soil conditions and recommendations were elaborated as to prepare and use long-term monitoring of vibration activity at the Bohunice NPP site

  6. Radiochemical speciation of strontium and cesium in soils and influence of the zeolite on its migration

    International Nuclear Information System (INIS)

    Cipakova, A.

    1998-01-01

    The dissertation deals with sorption and desorption characteristics of two significant radionuclides Sr-85 and Cs-137 in selected soil samples as well as from around of NPP Bohunice and NPP Mochovce which were examined. The dissertation consists from next chapters: (1) Introduction; (2) Present state of knowledge; (3) Materials and methods; (4) Results and discussion; (5) Conclusions; (6) Particular conclusions for the realisation in practice and for next development of the science

  7. Enel Graduates in Slovakia

    International Nuclear Information System (INIS)

    Galvani, L

    2009-01-01

    Enel constructs two reactors of second generation in Mochovce. Commissioning is expected at the end of 2013, a few months after Italy returns to nuclear. The power plant relies on the support of the public in the country, free way to adopted safety requirements from Brussels. So did inform assigned redactor Laura Galvagni in the edition of the most read Italian economic daily Il Sole 24 Ore on 24 November 2009. (author)

  8. Schedulability Analysis for Java Finalizers

    DEFF Research Database (Denmark)

    Bøgholm, Thomas; Hansen, Rene Rydhof; Søndergaard, Hans

    2010-01-01

    Java finalizers perform clean-up and finalisation of objects at garbage collection time. In real-time Java profiles the use of finalizers is either discouraged (RTSJ, Ravenscar Java) or even disallowed (JSR-302), mainly because of the unpredictability of finalizers and in particular their impact...... on the schedulability analysis. In this paper we show that a controlled scoped memory model results in a structured and predictable execution of finalizers, more reminiscent of C++ destructors than Java finalizers. Furthermore, we incorporate finalizers into a (conservative) schedulability analysis for Predictable Java...... programs. Finally, we extend the SARTS tool for automated schedulability analysis of Java bytecode programs to handle finalizers in a fully automated way....

  9. Final Environmental Impact Statement for the Treatment and Management of Sodium-Bonded Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    2000-01-01

    DOE is responsible for the safe and efficient management of its sodium-bonded spent nuclear fuel. This fuel contains metallic sodium, a highly reactive material; metallic uranium, which is also reactive; and in some cases, highly enriched uranium. The presence of reactive materials could complicate the process of qualifying and licensing DOE's sodium-bonded spent nuclear fuel inventory for disposal in a geologic repository. Currently, more than 98 percent of this inventory is located at the Idaho National Engineering and Environmental Laboratory (INEEL), near Idaho Falls, Idaho. In addition, in a 1995 agreement with the State of Idaho, DOE committed to remove all spent nuclear fuel from Idaho by 2035. This EIS evaluates the potential environmental impacts associated with the treatment and management of sodium-bonded spent nuclear fuel in one or more facilities located at Argonne National Laboratory-West (ANL-W) at INEEL and either the F-Canyon or Building 105-L at the Savannah River Site (SRS) near Aiken, South Carolina. DOE has identified and assessed six proposed action alternatives in this EIS. These are: (1) electrometallurgical treatment of all fuel at ANL-W, (2) direct disposal of blanket fuel in high-integrity cans with the sodium removed at ANL-W, (3) plutonium-uranium extraction (PUREX) processing of blanket fuel at SRS, (4) melt and dilute processing of blanket fuel at ANL-W, (5) melt and dilute processing of blanket fuel at SRS, and (6) melt and dilute processing of all fuel at ANL-W. In addition, Alternatives 2 through 5 include the electrometallurgical treatment of driver fuel at ANL-W. Under the No Action Alternative, the EIS evaluates both the continued storage of sodium-bonded spent nuclear fuel until the development of a new treatment technology or direct disposal without treatment. Under all of the alternatives, the affected environment is primarily within 80 kilometers (50 miles) of spent nuclear fuel treatment facilities. Analyses indicate

  10. DIMEC - Final Report

    DEFF Research Database (Denmark)

    Conrad, Finn

    1997-01-01

    Final report of the research project DIMEC - Danish InfoMechatronic Control supported by the Danish Technical Research Council, STVF.......Final report of the research project DIMEC - Danish InfoMechatronic Control supported by the Danish Technical Research Council, STVF....

  11. Impact of neutron resonance treatments on reactor calculation

    International Nuclear Information System (INIS)

    Leszczynski, F.

    1988-01-01

    The neutron resonance treatment on reactor calculation is one of the not completely resolved problems of reactor theory. The calculation required on design, fuel management and accident analysis of nuclear reactors contains adjust coefficients and semi-empirical values introduced on the computer codes; these values are obtained comparing calculation results with experimental values and more exact calculation results. This is made when the characteristics of the analyzed system are such that this type of comparisons are possible. The impact that one fixed resonance treatment method have on the final evaluation of physics reactor parameters, reactivity, power distribution, etc., is useful to know. In this work, the differences between calculated parameters with two different methods of resonance treatment in cell calculations are shown. It is concluded that improvements on resonance treatment are necessary for growing the reliability on core calculations results. Finally, possible improvements, easy to implement in current computer codes, are presented. (Author) [es

  12. UMTRA project: Canonsburg final design

    International Nuclear Information System (INIS)

    Thiers, G.R.; Guros, F.B.; Smith, E.S.

    1984-01-01

    Final design for on-site stabilization of over 300,000 cubic yards of abandoned mill tailings in Canonsburg, Pennsylvania, is being completed this Fall. This paper describes design criteria, design procedures, and difficulties encountered for the following required elements: 1. Encapsulation cell; 2. Durability of erosion protection material; 3. Flood control berm; 4. Sedimentation pond; 5. Wastewater treatment plant. The 70,000 cubic yards of the tailings for which radiation levels exceed 100 picocuries per gram will be placed on a 2-ft-thick compacted clay liner and encased by a 3-ft-thick compacted clay cover. The remaining tailings will be covered with at least two feet of clay to prevent radon escape and to reduce rainfall infiltration. Erosion protection will be provided for the encapsulation cell, the drainage swales, and from potential meandering of nearby Chartiers Creek

  13. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Glasser, Alan H. [Fusion Theory and Computation Inc., Kingston, WA (United States)

    2018-02-02

    Final technical report on DE-SC0016106. This is the final technical report for a portion of the multi-institutional CEMM project. This report is centered around 3 publications and a seminar presentation, which have been submitted to E-Link.

  14. Mixed debris treatment at the Idaho National Engineering Laboratory (INEL)

    International Nuclear Information System (INIS)

    Garcia, E.C.; Porter, C.L.; Wallace, M.T.

    1993-01-01

    August 18, 1992 the EPA published the final revised treatment standards for hazardous debris, including mixed debris. Whereas previous standards had been concentration based, the revised standards are performance based. Debris must be treated prior to land disposal, using specific technologies from one or more of the following families of debris treatment technologies: Extraction, destruction, or immobilization. Seventeen specific technologies with generic application are discussed in the final rule. The existing capabilities and types of debris at the INEL were evaluated against the debris rule to determine an overall treatment strategy for the INEL. Seven types of debris were identified: Combustible, porous, non-porous, inherently hazardous, HEPA filters, asbestos contaminated, and reactive metals contaminated debris. With the exception of debris contaminated with reactive metals treatment can be achieved utilizing existing facilities coupled with minor modifications

  15. Chapter 8: Quality assurance

    International Nuclear Information System (INIS)

    2001-01-01

    The main efforts of Nuclear Regulatory Authority of the Slovak Republic (UJD) have been focused on inspection of quality assurance programmes of Slovak Power Stations, plc. and its daughter companies at Bohunice and Mochovce. Two quality assurance inspections in the area of periodical in service inspections (V-2 units) and tests of selected equipment (NPP V-2 units) and operation control (V-1 units) has been performed at NPPs Bohunice. One violation of decree on quality assurance of selected equipment has been found in the area of documentation archiving. The inspection concerning the implementation of quality assurance programme for operation of NPP Mochovce in the area of operation control has been performed focused on safety aspects of operation, operational procedures, control of operational events and feedback from operational experience. The results of this inspection were positive. Inspection of implementation of quality assurance programme for operation of radioactive waste repository (RU RAW) at the Mochovce location has been performed focused on receiving of containers, with radioactive wastes, containers handling, radiation monitoring, activities of documentation control and radiation protection at the repository site. No serious deficiencies have been found out. Also one inspection of experimental nuclear installations of VUJE Trnava at Jaslovske Bohunice site has been performed focused on procurement control, quality audits, documentation and quality records control when performing activities at experimental nuclear installations. The activity on development of internal quality assurance system continued. The implementation of this system will assure quality and effective fulfilment enlarged tasks of UJD with limited resources for its activity. The analyses of possible use of existing internal administrative control documentation as a basis for future quality system procedures was performed in co-operation with an external specialised organisation. The

  16. Effect of growth hormone treatment on the adult height of children with chronic renal failure. German Study Group for Growth Hormone Treatment in Chronic Renal Failure.

    Science.gov (United States)

    Haffner, D; Schaefer, F; Nissel, R; Wühl, E; Tönshoff, B; Mehls, O

    2000-09-28

    Growth hormone treatment stimulates growth in short children with chronic renal failure. However, the extent to which this therapy increases final adult height is not known. We followed 38 initially prepubertal children with chronic renal failure treated with growth hormone for a mean of 5.3 years until they reached their final adult height. The mean (+/-SD) age at the start of treatment was 10.4+/-2.2 years, the mean bone age was 7.1+/-2.3 years, and the mean height was 3.1+/-1.2 SD below normal. Fifty matched children with chronic renal failure who were not treated with growth hormone served as controls. The children treated with growth hormone had sustained catch-up growth, whereas the control children had progressive growth failure. The mean final height of the growth hormone-treated children was 165 cm for boys and 156 cm for girls. The mean final adult height of the growth hormone-treated children was 1.6+/-1.2 SD below normal, which was 1.4 SD above their standardized height at base line (Pgrowth hormone-treated children, treatment was not associated with a shortening of the pubertal growth spurt. The total height gain was positively associated with the initial target-height deficit and the duration of growth hormone therapy and was negatively associated with the percentage of the observation period spent receiving dialysis treatment. Long-term growth hormone treatment of children with chronic renal failure induces persistent catch-up growth, and the majority of patients achieve normal adult height.

  17. Surveillance of WWER-440 fuel performance

    International Nuclear Information System (INIS)

    Simko, J.; Urban, P.

    1999-01-01

    In this lecture next problems of surveillance of WWER-440 fuel performance are presented: surveillance of WWER-440 fuel performance at Mochovce NPP; basic data of WWER-440 reactor; in-core reactor measuring system 'SVRK'; basic level of SVRK; information output of basic level of SVRK; surveillance of fuel performance; table of permissible operation conditions of the reactor; limitation of the unit 1 power at the beginning of the operation; cyclic changes of power; future perspectives

  18. Solutions to microplastic pollution - Removal of microplastics from wastewater effluent with advanced wastewater treatment technologies.

    Science.gov (United States)

    Talvitie, Julia; Mikola, Anna; Koistinen, Arto; Setälä, Outi

    2017-10-15

    Conventional wastewater treatment with primary and secondary treatment processes efficiently remove microplastics (MPs) from the wastewater. Despite the efficient removal, final effluents can act as entrance route of MPs, given the large volumes constantly discharged into the aquatic environments. This study investigated the removal of MPs from effluent in four different municipal wastewater treatment plants utilizing different advanced final-stage treatment technologies. The study included membrane bioreactor treating primary effluent and different tertiary treatment technologies (discfilter, rapid sand filtration and dissolved air flotation) treating secondary effluent. The MBR removed 99.9% of MPs during the treatment (from 6.9 to 0.005 MP L -1 ), rapid sand filter 97% (from 0.7 to 0.02 MP L -1 ), dissolved air flotation 95% (from 2.0 to 0.1 MP L -1 ) and discfilter 40-98.5% (from 0.5 - 2.0 to 0.03-0.3 MP L -1 ) of the MPs during the treatment. Our study shows that with advanced final-stage wastewater treatment technologies WWTPs can substantially reduce the MP pollution discharged from wastewater treatment plants into the aquatic environments. Copyright © 2017 Elsevier Ltd. All rights reserved.

  19. Method of treating final products from flue gas desulfurization

    International Nuclear Information System (INIS)

    Bloss, W.; Mohn, U.

    1984-01-01

    A method of treating final products from a flue gas desulfurization. The flue gas desulfurization is carried out by the absorption of sulfur oxide in a spray dryer with a suspension which contains lime, or in a reactor with a dry, fine-grained, absorbent which contains lime. Prior to desulfurization, the fly ash carried along by the flue gas which is to be desulfurized is separated entirely, partially, or not at all from the flue gas, and the final products from the flue gas desulfurization, prior to any further treatment thereof, amount to 1-99% by weight, preferably 1-70% by weight, of fly ash, and 1-99% by weight, preferably 30-99% by weight, of the sum of the desulfurization products, preferably calcium sulfite hemihydrate, and/or calcium sulfite, and/or calcium sulfate dyhydrate, and/or calcium sulfate hemihydrate, and/or calcium sulfate, as well as residue of the absorbent. The reduction of the amount of calcium sulfite is implemented by a dry oxidation with air

  20. Liquid effluent retention facility final-status groundwater monitoring plan

    International Nuclear Information System (INIS)

    Sweeney, M.D.; Chou, C.J.; Bjornstad, B.N.

    1997-09-01

    The following sections describe the groundwater-monitoring program for the Liquid Effluent Retention Facility (LERF). The LERF is regulated under the Resource Conservation and Recovery Act of 1976 (RCRA). The LERF is included in the open-quotes Dangerous Waste Portion of the Resource Conservation and Recovery Act Permit for the Treatment, Storage, and Disposal of Dangerous Waste, Permit WA890008967close quotes, (referred to herein as the Permit) (Ecology 1994) and is subject to final-status requirements for groundwater monitoring (WAC 173-303-645). This document describes a RCRA/WAC groundwater detection-monitoring program for groundwater in the uppermost aquifer system at the LERF. This plan describes the LERF monitoring network, constituent list, sampling schedule, statistical methods, and sampling and analysis protocols that will be employed for the LERF. This plan will be used to meet the groundwater monitoring requirements from the time the LERF becomes part of the Permit and through the post-closure care period, until certification of final closure

  1. Poor final visual outcome after traumatic hyphema: A retrospective study of associated factors

    Directory of Open Access Journals (Sweden)

    Ayda Khalfan Al Ali

    2012-09-01

    Full Text Available OBJECTIVES: To determine the factors associated with a poor final visual outcome following a non-perforating traumatic hyphema. METHODS: The in-patient records of all traumatic hyphema patients admitted to the Department of Ophthalmology of the Hamad Medical Centre (HMC in Doha, Qatar, were retrospectively reviewed for a four-year period from January 2004 to March 2008. One hundred and seventeen patients who did not meet the exclusion criteria were divided into two groups based on their final visual outcome post-treatment. Group 1 (good outcome consisted of 100 patients with a visual acuity (VA of 6/18 or better and group 2 (worse outcome consisted of 17 patients with a VA of less than 6/18. The two groups were compared to determine the factors associated with a poor final visual outcome. RESULTS: Group 2 patients had an 82.3% incidence of complications after a traumatic hyphema compared with a 21% incidence in group 1. Of these complications, secondary glaucoma and rebleeding were significantly associated with a worse final visual outcome. Trauma from projectiles or blows did not differ significantly in their effect on the final visual outcome, although blow injuries had a greater impact on the final visual outcome. Posterior segment injuries were associated with a worse visual outcome. CONCLUSION: It was concluded that secondary glaucoma, rebleeding, and posterior segment injuries are factors associated with a poor final visual outcome.

  2. Sodium-Bearing Waste Treatment, Applied Technology Plan

    International Nuclear Information System (INIS)

    Lance Lauerhass; Vince C. Maio; S. Kenneth Merrill; Arlin L. Olson; Keith J. Perry

    2003-01-01

    Settlement Agreement between the Department of Energy and the State of Idaho mandates treatment of sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center within the Idaho National Engineering and Environmental Laboratory. One of the requirements of the Settlement Agreement is to complete treatment of sodium-bearing waste by December 31, 2012. Applied technology activities are required to provide the data necessary to complete conceptual design of four identified alternative processes and to select the preferred alternative. To provide a technically defensible path forward for the selection of a treatment process and for the collection of needed data, an applied technology plan is required. This document presents that plan, identifying key elements of the decision process and the steps necessary to obtain the required data in support of both the decision and the conceptual design. The Sodium-Bearing Waste Treatment Applied Technology Plan has been prepared to provide a description/roadmap of the treatment alternative selection process. The plan details the results of risk analyzes and the resulting prioritized uncertainties. It presents a high-level flow diagram governing the technology decision process, as well as detailed roadmaps for each technology. The roadmaps describe the technical steps necessary in obtaining data to quantify and reduce the technical uncertainties associated with each alternative treatment process. This plan also describes the final products that will be delivered to the Department of Energy Idaho Operations Office in support of the office's selection of the final treatment technology

  3. Sodium-Bearing Waste Treatment, Applied Technology Plan

    Energy Technology Data Exchange (ETDEWEB)

    Lance Lauerhass; Vince C. Maio; S. Kenneth Merrill; Arlin L. Olson; Keith J. Perry

    2003-06-01

    Settlement Agreement between the Department of Energy and the State of Idaho mandates treatment of sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center within the Idaho National Engineering and Environmental Laboratory. One of the requirements of the Settlement Agreement is to complete treatment of sodium-bearing waste by December 31, 2012. Applied technology activities are required to provide the data necessary to complete conceptual design of four identified alternative processes and to select the preferred alternative. To provide a technically defensible path forward for the selection of a treatment process and for the collection of needed data, an applied technology plan is required. This document presents that plan, identifying key elements of the decision process and the steps necessary to obtain the required data in support of both the decision and the conceptual design. The Sodium-Bearing Waste Treatment Applied Technology Plan has been prepared to provide a description/roadmap of the treatment alternative selection process. The plan details the results of risk analyzes and the resulting prioritized uncertainties. It presents a high-level flow diagram governing the technology decision process, as well as detailed roadmaps for each technology. The roadmaps describe the technical steps necessary in obtaining data to quantify and reduce the technical uncertainties associated with each alternative treatment process. This plan also describes the final products that will be delivered to the Department of Energy Idaho Operations Office in support of the office's selection of the final treatment technology.

  4. Mixed debris treatment at the Idaho National Engineering Laboratory (INEL)

    International Nuclear Information System (INIS)

    Garcia, E.C.; Porter, C.L.; Wallace, M.T.

    1993-01-01

    August 18, 1992 the Environmental Protection Agency (EPA) published the final revised treatment standards for hazardous debris, including mixed debris. (1) Whereas previous standards had been concentration based, the revised standards are performance based. Debris must be treated prior to land disposal, using specific technologies from one or more of the following families of debris treatment technologies: Extraction, destruction, or immobilization. Seventeen specific technologies with generic application are discussed in the final rule. The existing capabilities and types of debris at the INEL were scrubbed against the debris rule to determine an overall treatment strategy. Seven types of debris were identified: combustible, porous, non-porous, inherently hazardous, HEPA filters, asbestos contaminated, and reactive metals contaminated debris. With the exception of debris contaminated with reactive metals treatment can be achieved utilizing existing facilities coupled with minor modifications

  5. Induction of micronuclei in the mouse. Revised timing of the final stage of erythropoiesis

    International Nuclear Information System (INIS)

    Hart, J.W.; Hartley-Asp, B.

    1983-01-01

    the early effects of X-rays, vincristine, cyclophosphamide, quinacrine dihydrochloride, cycloheximide, actinomycin D and hydroxyurea on the induction of micronuclei in mouse bone-marrow erythrocytes were studied. A significant increase in the incidence of micronuclei in polychromatic erythrocytes was seen as early as 5 h after a single treatment with vincristine, 6 h after treatment with X-rays and 10 h after treatment with cyclophosphamide. The cell kinetics of the mouse erythropoietic system described by Cole et al. (1981) can be modified to fit these results. According to this revised model, the final mitosis takes place only 5 h before the expulsion of the nucleus. (orig.)

  6. Induction of micronuclei in the mouse. Revised timing of the final stage of erythropoiesis

    Energy Technology Data Exchange (ETDEWEB)

    Hart, J.W. (Leo Pharmaceutical Products Ltd., Ballerup (Denmark)); Hartley-Asp, B. (AB Leo, Helsingborg (Sweden))

    1983-05-01

    the early effects of X-rays, vincristine, cyclophosphamide, quinacrine dihydrochloride, cycloheximide, actinomycin D and hydroxyurea on the induction of micronuclei in mouse bone-marrow erythrocytes were studied. A significant increase in the incidence of micronuclei in polychromatic erythrocytes was seen as early as 5 h after a single treatment with vincristine, 6 h after treatment with X-rays and 10 h after treatment with cyclophosphamide. The cell kinetics of the mouse erythropoietic system described by Cole et al. (1981) can be modified to fit these results. According to this revised model, the final mitosis takes place only 5 h before the expulsion of the nucleus.

  7. [Endodontically treated teeth. Success--failure. Endorestorative treatment plan].

    Science.gov (United States)

    Zabalegui, B

    1990-01-01

    More and more often the general dentist is finding the presence of endodontically treated teeth during his treatment planning procedure. He has to ask himself if the endo-treated tooth functions and will continue to function function successfully, when deciding which final endo-restorative procedure to apply. For this reason the dentist or the endodontist with whom he works should clinically evaluate these teeth, establish a diagnostic criteria of their success or failure and a treatment plan according to the prognosis. The purpose of this article is to offer an organized clinical view of the steps to follow when evaluating an endodontically treated tooth and how to establish a final endo-restorative plan.

  8. Early glottic cancer: the influence of primary treatment on voice preservation

    International Nuclear Information System (INIS)

    Lesnicar, Hotimir; Smid, Lojze; Zakotnik, Branko

    1996-01-01

    Purpose: Retrospective analysis was performed to assess the influence of primary surgical or irradiation treatment on local control, survival, and final preservation of larynx in comparable groups of patients with T1N0 and T2N0 glottic cancer. Methods and Materials: Two hundred sixty-three previously untreated patients with invasive squamous cell carcinoma of the glottis (187T1 and 76T2) were treated with primary radiotherapy (159T1 and 60T2) or primary surgery (28T1 and 16T2) between January 1976 and December 1990, at the University of Ljubljana, Slovenia. Conventional one daily fraction of 2 Gy to doses of 60-74 Gy (median: 65 Gy) were used in 98% of primarily irradiated patients through out the observed period. To enable better comparison between the two treatment groups, primarily irradiated patients were retrospectively stratified by the criteria of suitability for primary voice-sparing operation. Several host, tumor, and treatment parameters were analyzed. Results: Only the stage of the disease significantly influenced both 10-year recurrence-free and disease-specific survival regardless primary treatment modality (p = 0.0002). In all primary irradiated patients local control was significantly better for those with overall treatment time of less than 48 days (p = 0.007). In patients suitable for voice-sparing operation, local control of primarily operated patients was similar to that of patients primarily irradiated with shorter overall treatment time, which was 93 and 88% for T1 and 67 and 64% for T2 tumors, respectively. Ultimate local control in primary surgery and radiotherapy group was 96 and 96% for T1 and 89 and 88% for T2 tumors, respectively. Equal larynx preservation of 100% in T1 and 90% in T2 patients was achieved in finally cured primarily operated patients and those patients primarily irradiated with a shorter overall treatment time. If treatment time was longer than 48 days, significantly worse final larynx preservation of 84% in T1 and 75% in

  9. The Modernization Program and Power Up-rate at NPP V2 Jaslovske Bohunice, Slovak Republic

    International Nuclear Information System (INIS)

    Reznik, Vladivoj; Krajmer, Imrich

    2010-01-01

    Slovenske Elektrarne, a.s. is a second largest utility company in the Central and Eastern Europe that owns an optimal production portfolio comprised of nuclear, thermal and hydroelectric power plants. There are two nuclear power plants Bohunice and Mochovce both operate with two units and another two units Mochovce 3 and 4 are currently under construction. Electricity at Nuclear power plant Bohunice V2 is generated by two 440 MW units that had gradually been connected to the power network over the period between 1984 and 1985. In the construction of the nuclear power plant V2 the concept of pressurized water reactors was adopted and the Soviet-era design WWER 440 used. The upgrading of Nuclear Power Plant Bohunice V2 is based on three main points: Modernization, Power up-rate, and Ageing monitoring program. The main targets of the modernization project were: Increasing of the Nuclear Safety and of the Nuclear operational reliability, and Seismic improvement. This modernization program is in full compliance with IAEA requirements and with the decisions from the Nuclear Regulatory Agency of the Slovak Republic (UJD) and achievement of the probabilistic safety criteria in accordance with IAEA recommendations. Except that is ensured a safe, reliable, economical and effective electricity and heat generation. Achieved results are based for further prolongation of the operation life time up to 60 years. (authors)

  10. Thermo-hydrogenating treatments in Ti-6Al-4V

    International Nuclear Information System (INIS)

    Guitar, A; Domizzi, G; Luppo, M.I; Vigna, G

    2006-01-01

    The production of components of Ti alloys, specifically Ti-6Al-4V, involves some difficulties in obtaining the final desired microstructure, producing decrease in the material's mechanical properties. In the specific case of materials to be used for surgical implants an equiaxial fine grain microstructure of α phase a with an homogenously precipitated β phase is needed. The modification of certain microstructural features is not possible based on simple thermal treatments. Thermomechanical treatments are effective for transforming the lamellar α phase into equiaxial α, but these methods include major deformations in the (α + β) two-phase field. In order to avoid this stage, thermo-hydrogenating processes were used (THP). The THP involve a treatment of β solubilization before, during or after the hydrogenation, a possible isothermal treatment below the β hydrogenated transus temperature and the final vacuum dehydrogenation. The development of treatments using hydrogen as a temporary alloying element creates a new class of microstructures, which are finer than equiaxial structures and respond well to resistance to traction and fatigue. Since the THP do not include the working of the material to control the microstructure, they are more appropriate for use with shaped components close to the end, like those obtained by powder metallurgy or smelting. Different thermo-hydrogenating treatments in Ti-6Al-4V to modify the microstructure were studied. Final microstructures of α fine phase and β disperse phase were obtained using THP in samples with initial lamellar α phase separated by thin sheets of β phase. The characterization of the initial material and of the transformed material was carried out using optic and scanning electron microscopy (CW)

  11. Final-state interactions and relativistic effects in the quasielastic (e,e') reaction

    International Nuclear Information System (INIS)

    Chinn, C.R.; Physics Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87545); Picklesimer, A.; Van Orden, J.W.

    1989-01-01

    The longitudinal and transverse response functions for the inclusive quasielastic (e,e') reaction are analyzed in detail. A microscopic theoretical framework for the many-body reaction provides a clear conceptual (nonrelativistic) basis for treating final-state interactions and goes far beyond simple plane-wave or Hermitean potential models. The many-body physics of inelastic final-state channels as described by optical and multiple scattering theories is properly included by incorporating a full complex optical potential. Explicit nonrelativistic and relativistic momentum-space calculations quantitatively demonstrate the importance of such a treatment of final-state interactions for both the transverse and longitudinal response. Nonrelativistic calculations are performed using final-state interactions based on phenomenology, local density models, and microscopic multiple scattering theory. Relativistic calculations span a similar range of models and employ Dirac bound-state wave functions. The theoretical extension to relativistic dynamics is of course not clear, but is done in obvious parallel to elastic proton scattering. Extensive calculations are performed for 40 Ca at momentum transfers of 410, 550, and 700 MeV/c. A number of interesting physical effects are observed, including significant relativistic suppressions (especially for R L ), large off-shell and virtual pair effects, enhancement of the tails of the response by the final-state interactions, and large qualitative and even shape distinctions between the predictions of the various models of the final-state interactions. None of the models is found to be able to simultaneously predict the data for both response functions. This strongly suggests that additional physical mechanisms are of qualitative importance in inclusive quasielastic electron scattering

  12. Electron beam treatment of wastewater

    International Nuclear Information System (INIS)

    Arai, H.; Hosono, M.; Shimizu, K.; Sugiyama, M.

    1991-01-01

    Supernatant comes from dewaterization of sewage sludge, and contains biologically nondegradable organics so that it is hard to be treated by conventional activated sludge. By electron beam (EB) irradiation, any kinds of organics in water can be oxidized to biodegradable organic acids. We studied the treatment of supernatant by application of this effect. The direct irradiation of the original supernatant was found not to be so effective to decrease COD. In order to increase the irradiation effect, supernatant was pretreated biologically to decrease the biodegradable organics in it. The chemical oxygen demand (COD) and biochemical oxygen demand (BOD) were decreased from 800 and 910 mg/L to 78 and 5 mg/L by this pretreatment, respectively. This pretreated supernatant was irradiated by EB of 2 MeV using a batch type reactor. The COD was gradually decreased with dose. In contrast, BOD was increased markedly, indicating increase in biodegradability. The irradiated sample water was treated biologically again. After the final biological treatment, COD was decreased below 30 mg/L in the case of 10 - 12 kGy irradiation. Finally, the initial COD of 800 mg/L was decreased below 30 mg/L by the combination of EB irradiation and biological treatment. The cost of irradiation for this process was evaluated preliminarily. (author)

  13. Mixed Waste Treatment Using the ChemChar Thermolytic Detoxification Technique

    International Nuclear Information System (INIS)

    Kuchynka, D.J.

    1997-01-01

    This R and D program addresses the treatment of mixed waste employing the ChemChar Thermolytic Detoxification process. Surrogate mixed waste streams will be treated in a four inch diameter, continuous feed, adiabatic reactor with the goal of meeting all regulatory treatment levels for the contaminants in the surrogates with the concomitant production of contaminant free by-products. Successful completion of this program will show that organic contaminants in mixed waste surrogates will be converted to a clean, energy rich synthesis gas capable of being used, without further processing, for power or heat generation. The inorganic components in the surrogates will be found to be adsorbed on a macroporous coal char activated carbon substrate which is mixed with the waste prior to treatment. These contaminants include radioactive metal surrogate species, RCRA hazardous metals and any acid gases formed during the treatment process. The program has three main tasks that will be performed to meet the above objectives. The first task is the design and construction of the four inch reactor at Mirage Systems in Sunnyvale, CA. The second task is production and procurement of the activated carbon char employed in the ChemChartest runs and identification of two surrogate mixed wastes. The last task is testing and operation of the reactor on char/surrogate waste mixtures to be performed at the University of Missouri. The deliverables for the project are a Design Review Report, Operational Test Plan, Topical Report and Final Report. This report contains only the results of the design and construction carbon production-surrogate waste identification tasks.Treatment of the surrogate mixed wastes has just begun and will not be reported in this version of the Final Report. The latter will be reported in the final version of the Final Report

  14. Integrated nonthermal treatment system study

    International Nuclear Information System (INIS)

    Biagi, C.; Bahar, D.; Teheranian, B.; Vetromile, J.; Quapp, W.J.; Bechtold, T.; Brown, B.; Schwinkendorf, W.; Swartz, G.

    1997-01-01

    This report presents the results of a study of nonthermal treatment technologies. The study consisted of a systematic assessment of five nonthermal treatment alternatives. The treatment alternatives consist of widely varying technologies for safely destroying the hazardous organic components, reducing the volume, and preparing for final disposal of the contact-handled mixed low-level waste (MLLW) currently stored in the US Department of Energy complex. The alternatives considered were innovative nonthermal treatments for organic liquids and sludges, process residue, soil and debris. Vacuum desorption or various washing approaches are considered for treatment of soil, residue and debris. Organic destruction methods include mediated electrochemical oxidation, catalytic wet oxidation, and acid digestion. Other methods studied included stabilization technologies and mercury separation of treatment residues. This study is a companion to the integrated thermal treatment study which examined 19 alternatives for thermal treatment of MLLW waste. The quantities and physical and chemical compositions of the input waste are based on the inventory database developed by the US Department of Energy. The Integrated Nonthermal Treatment Systems (INTS) systems were evaluated using the same waste input (2,927 pounds per hour) as the Integrated Thermal Treatment Systems (ITTS). 48 refs., 68 figs., 37 tabs

  15. Integrated nonthermal treatment system study

    Energy Technology Data Exchange (ETDEWEB)

    Biagi, C.; Bahar, D.; Teheranian, B.; Vetromile, J. [Morrison Knudsen Corp. (United States); Quapp, W.J. [Nuclear Metals (United States); Bechtold, T.; Brown, B.; Schwinkendorf, W. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States); Swartz, G. [Swartz and Associates (United States)

    1997-01-01

    This report presents the results of a study of nonthermal treatment technologies. The study consisted of a systematic assessment of five nonthermal treatment alternatives. The treatment alternatives consist of widely varying technologies for safely destroying the hazardous organic components, reducing the volume, and preparing for final disposal of the contact-handled mixed low-level waste (MLLW) currently stored in the US Department of Energy complex. The alternatives considered were innovative nonthermal treatments for organic liquids and sludges, process residue, soil and debris. Vacuum desorption or various washing approaches are considered for treatment of soil, residue and debris. Organic destruction methods include mediated electrochemical oxidation, catalytic wet oxidation, and acid digestion. Other methods studied included stabilization technologies and mercury separation of treatment residues. This study is a companion to the integrated thermal treatment study which examined 19 alternatives for thermal treatment of MLLW waste. The quantities and physical and chemical compositions of the input waste are based on the inventory database developed by the US Department of Energy. The Integrated Nonthermal Treatment Systems (INTS) systems were evaluated using the same waste input (2,927 pounds per hour) as the Integrated Thermal Treatment Systems (ITTS). 48 refs., 68 figs., 37 tabs.

  16. Design works organization during the IandC system upgrading on an operating VVER power plant from the general designer's standpoint

    International Nuclear Information System (INIS)

    Krepel, V.

    1997-01-01

    Two replacements of nuclear power plant instrumentation and control systems have already been implemented according to the project design of Energoprojekt: at the Mochovce WWER-440 and the Temelin WWER-1000 plants. In the present contribution the design problems encountered during the replacement are described, the causes of the problems are discussed, and a policy of organizing project design work for an instrumentation and control system replacement at an operating WWER power plant is established such as would avoid these problems. (A.K.)

  17. Final height in central precocious puberty after long term treatment with a slow release GnRH agonist

    NARCIS (Netherlands)

    Oostdijk, W; Rikken, B; Schreuder, S; Otten, Barto; Odink, R; Rouwe, C; Jansen, M; Gerver, WJ; Waelkens, J; Drop, S

    1996-01-01

    Objective-To study the resumption of puberty and the final height achieved in children with central precocious puberty (CPP) treated with the GnRH agonist triptorelin. Patients-31 girls and five boys with CPP who were treated with triptorelin 3.75 mg intramuscularly every four weeks. Girls were

  18. TARGET 2 and Settlement Finality

    Directory of Open Access Journals (Sweden)

    Ivan MANGATCHEV

    2011-03-01

    Full Text Available This article examines how TARGET 2 as system implements the idea of settlement finality regulated by Directive 98/26 EC of the European parliament and of the Council of 19 May 1998 on settlement finality in payment and securities settlement systems (Settlement Finality Directive and Directive 2009/44/EC of the European parliament and of the Council of 6 May 2009 amending Directive 98/26/EC on settlement finality in payment and securities settlement systems and Directive 2002/47/EC on financial collateral arrangements as regards linked systems and credit claims (Directive 2009/44/EC. As the title of the arti and finality of the settlement in this system.

  19. Optimization of multi-stage dynamic treatment regimes utilizing accumulated data.

    Science.gov (United States)

    Huang, Xuelin; Choi, Sangbum; Wang, Lu; Thall, Peter F

    2015-11-20

    In medical therapies involving multiple stages, a physician's choice of a subject's treatment at each stage depends on the subject's history of previous treatments and outcomes. The sequence of decisions is known as a dynamic treatment regime or treatment policy. We consider dynamic treatment regimes in settings where each subject's final outcome can be defined as the sum of longitudinally observed values, each corresponding to a stage of the regime. Q-learning, which is a backward induction method, is used to first optimize the last stage treatment then sequentially optimize each previous stage treatment until the first stage treatment is optimized. During this process, model-based expectations of outcomes of late stages are used in the optimization of earlier stages. When the outcome models are misspecified, bias can accumulate from stage to stage and become severe, especially when the number of treatment stages is large. We demonstrate that a modification of standard Q-learning can help reduce the accumulated bias. We provide a computational algorithm, estimators, and closed-form variance formulas. Simulation studies show that the modified Q-learning method has a higher probability of identifying the optimal treatment regime even in settings with misspecified models for outcomes. It is applied to identify optimal treatment regimes in a study for advanced prostate cancer and to estimate and compare the final mean rewards of all the possible discrete two-stage treatment sequences. Copyright © 2015 John Wiley & Sons, Ltd.

  20. Permeable treatment wall design and cost analysis

    International Nuclear Information System (INIS)

    Manz, C.; Quinn, K.

    1997-01-01

    A permeable treatment wall utilizing the funnel and gate technology has been chosen as the final remedial solution for one industrial site, and is being considered at other contaminated sites, such as a closed municipal landfill. Reactive iron gates will be utilized for treatment of chlorinated VOCs identified in the groundwater. Alternatives for the final remedial solution at each site were evaluated to achieve site closure in the most cost effective manner. This paper presents the remedial alternatives and cost analyses for each site. Several options are available at most sites for the design of a permeable treatment wall. Our analysis demonstrates that the major cost factor's for this technology are the design concept, length, thickness, location and construction methods for the reactive wall. Minimizing the amount of iron by placement in the most effective area and construction by the lowest cost method is critical to achieving a low cost alternative. These costs dictate the design of a permeable treatment wall, including selection of a variety of alternatives (e.g., a continuous wall versus a funnel and gate system, fully penetrating gates versus partially penetrating gates, etc.). Selection of the appropriate construction methods and materials for the site can reduce the overall cost of the wall

  1. Radioiodine treatment for malignant thyroid disease

    Energy Technology Data Exchange (ETDEWEB)

    Berg, Gertrud [Sahlgrenska Univ. Hospital, Goeteborg (Sweden). Dept. of Oncology

    2006-12-15

    Radioiodine treatment for thyroid disease has been given for half a decade in Sweden. The most common indication for treatment is hyperthyroidism, when iodine uptake is high. The situation in which radioiodine treatment is used in thyroid cancer is less favourable and measures therefore have to be taken to optimize the treatment. Treatment should be performed early in the course of the disease to achieve the highest possible differentiation. Before treatment the iodine and goitrogen intake should be kept low. Stimulation of the thyrocytes by thyroid-stimulating hormone (TSH) should be high. It is conventionally achieved by thyroid hormone withdrawal rendering the patient hypothyroid, or by the recently available recombinant human TSH (rhTSH) which can be recommended for ablation of the thyroid remnant after thyroidectomy and for treatment of metastases in fragile patients unable to undergo hypothyroidism. Finally, stunning - the negative effect of a prior test dose from radioactive iodine - should be avoided.

  2. Chemical treatment of uranium ores in France

    International Nuclear Information System (INIS)

    Mouret, P.; Sartorius, R.

    1958-01-01

    The various processes of chemical treatment of uranium ores, from the oldest to the more recent, are exposed, considering the following conditions: economics, geography, techniques and safety. The interest of obtaining a final concentrate as uranyl nitrate is discussed. (author) [fr

  3. Long-Term, Open-Label Safety and Efficacy of Atomoxetine in Adults with ADHD: Final Report of a 4-Year Study

    Science.gov (United States)

    Adler, Lenard A.; Spencer, Thomas J.; Williams, David W.; Moore, Rodney J.; Michelson, David

    2008-01-01

    Objective: Previously, data from 97 weeks of open-label atomoxetine treatment of adults with attention-deficit/hyperactivity disorder (ADHD) were reported. This final report of that study presents results from over 4 years of treatment. Method: Results were derived from the study of 384 patients (125 patients remaining in the open-label trial…

  4. Anxiety disorders: diagnosis and treatment.

    Science.gov (United States)

    Jack, R A; Mathew, R J

    1985-07-01

    Pathologic anxiety, marked by inappropriate apprehension and/or fear, causes patients to seek help. Anxiety is associated with a wide variety of physical illnesses, and these must be initially considered when making a diagnosis. Similarly, anxiety associated with a wide variety of psychiatric syndromes must also be considered. Finally, the possibility of transient situational anxiety is ever present. Once it is determined that a primary anxiety disorder exists, then the presence or absence of phobias, panic attacks, and chronic "free-floating" anxiety will fully characterize the disorder. With an accurate diagnosis in hand, a multifaceted treatment approach can be designed. Effective treatments now exist for phobic and panic disorders, and more effective treatment for chronic generalized anxiety may be forthcoming.

  5. Sixty-five-year old final clarifier performance rivals that of modern designs.

    Science.gov (United States)

    Barnard, James L; Kunetz, Thomas E; Sobanski, Joseph P

    2008-01-01

    The Stickney plant of the Metropolitan Wastewater Reclamation District of Greater Chicago (MWRDGC), one of the largest wastewater treatment plants in the world, treats an average dry weather flow of 22 m3/s and a sustained wet weather flow of 52 m3/s that can peak to 63 m3/s. Most of the inner city of Chicago has combined sewers, and in order to reduce pollution through combined sewer overflows (CSO), the 175 km Tunnel and Reservoir Plan (TARP) tunnels, up to 9.1 m in diameter, were constructed to receive and convey CSO to a reservoir from where it will be pumped to the Stickney treatment plant. Pumping back storm flows will result in sustained wet weather flows over periods of weeks. Much of the success of the plant will depend on the ability of 96 circular final clarifiers to produce an effluent of acceptable quality. The nitrifying activated sludge plant is arranged in a plug-flow configuration, and some denitrification takes place as a result of the high oxygen demand in the first pass of the four-pass aeration basins that have a length to width ratio of 18:1. The SVI of the mixed liquor varies between 60 and 80 ml/g. The final clarifiers, which were designed by the District's design office in 1938, have functioned for more than 65 years without major changes and are still producing very high-quality effluent. This paper will discuss the design and operation of these final clarifiers and compare the design with more modern design practices. (c) IWA Publishing 2008.

  6. 75 FR 62133 - Notice of Availability of Final Environmental Assessment (FINAL EA) and a Finding of No...

    Science.gov (United States)

    2010-10-07

    ... Availability of Final Environmental Assessment (FINAL EA) and a Finding of No Significant Impact (FONSI) for... of No Significant Impact (FONSI) for Land Purchase, Access Road Construction and Access Tunnel... Impact (FONSI) based on the Final Environmental Assessment (FINAL EA) for Land Purchase, Access Road...

  7. 14 CFR 1214.1105 - Final ranking.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false Final ranking. 1214.1105 Section 1214.1105... Recruitment and Selection Program § 1214.1105 Final ranking. Final rankings will be based on a combination of... preference will be included in this final ranking in accordance with applicable regulations. ...

  8. INTERNATIONAL ACCOUNTING TREATMENT REGARDING REVENUE

    Directory of Open Access Journals (Sweden)

    ECOBICI NICOLAE

    2014-08-01

    Full Text Available This paper discusses the news on international accounting treatments of revenue arising from the extensive process of convergence between IASB and FASB that began in 2002. The starting point of this approach is to identify the treatments currently applicable to income. Finally we presented a summary of the main provisions of the new standard IFRS 15 “Revenue from Contracts with Customers”, which replaces IAS 11 and IAS 18 (as well as a number of SIC and IFRIC interpretations required to be applied from January 1, 2017, emphasizing the potential impact on entities.

  9. Combined modality treatment with radiotherapy and chemotherapy

    International Nuclear Information System (INIS)

    Tannock, I.F.; Toronto Univ., ON

    1989-01-01

    The present paper discusses some of the methodological issues which can confound the interpretation of clinical trials of combined modality treatment. It reviews some of the larger randomized trials which have evaluated combined modality treatment in cancers of the head and neck, lung, gastrointestinal tract and bladder. It concludes that adequate trials have yet to be performed in many of thses sites, but that at present, evidence for long-term benefit from adjunctivechemotherapy is meagre. Finally, it suggests some possible mechanisms which might heve limited the benefit of chemotherapy when added to radiation treatment. (Author). 87 refs.; 4 figs.; 4 tabs

  10. 78 FR 43912 - Final Candidate Conservation Agreement with Assurances, Final Environmental Assessment, and...

    Science.gov (United States)

    2013-07-22

    ...-FF02ENEH00] Final Candidate Conservation Agreement with Assurances, Final Environmental Assessment, and Finding of No Significant Impact; Rio Grande Cutthroat Trout, New Mexico and Colorado AGENCY: Fish and... environmental assessment (EA) and the draft Finding of No Significant Impact (FONSI) under the National...

  11. Treatment Readiness as a Determinant of Treatment Participation in a Prison-Based Rehabilitation Program: An Exploratory Study.

    Science.gov (United States)

    Bosma, Anouk Q; Kunst, Maarten J J; Dirkzwager, Anja J E; Nieuwbeerta, Paul

    2017-06-01

    The current study had three aims. First, it measured treatment readiness among offenders who entered the Prevention of Recidivism program. This is a prison-based rehabilitation program in the Netherlands that aims to lower re-offending rates among offenders with a prison sentence of at least for months and that is carried out during the final months of incarceration. Second, the study evaluated whether treatment readiness was associated with treatment participation. Third, the study examined whether treatment readiness measured with a validated instrument predicted treatment participation above and beyond a clinical assessment of treatment readiness, currently used as a criterion to include offenders in rehabilitation programs. To address these aims, data were used from the fourth wave of a research project studying the effects of imprisonment on the life of detainees in the Netherlands. Results indicated that treatment readiness as measured with a validated instrument was a significant predictor of treatment participation. Also, the current study showed that treatment readiness measured with a validated instrument improved the prediction of treatment participation above and beyond a clinical assessment of treatment readiness. Outcomes were discussed in light of study limitations and implications.

  12. Applications of artificial intelligence technology to wastewater treatment fields in China

    Institute of Scientific and Technical Information of China (English)

    QING Xiao-xia; WANG Bo; MENG De-tao

    2005-01-01

    Current applications of artificial intelligence technology to wastewater treatment in China are summarized. Wastewater treatment plants use expert system mainly in the operation decision-making and fault diagnosis of system operation, use artificial neuron network for system modeling, water quality forecast and soft measure, and use fuzzy control technology for the intelligence control of wastewater treatment process. Finally, the main problems in applying artificial intelligence technology to wastewater treatment in China are analyzed.

  13. Accuracy of Invisalign® treatments in the anterior tooth region. First results.

    Science.gov (United States)

    Krieger, Elena; Seiferth, Jörg; Saric, Ivana; Jung, Britta A; Wehrbein, Heinrich

    2011-03-01

    To analyse (a) to what extent the pretreatment model at the beginning of the treatment corresponds to the initial position in the ClinCheck® and (b) to what extent the predicted treatment result corresponds to the actual result of the therapy at the end of the treatment. Pre- and posttreatment models as well as the initial and final position of the ClinCheck with a total of 35 patients aged between 15 and 59 were measured; all of whom were treated by using the Invisalign® technology (Invisalign®, Align Technology, S.C., Calif., USA). The measurement of the initial and final models was conducted by using an electronic digital calliper rule, i.e. that of ClinCheck® using the measurement tool ToothMeasure® of Invisalign® Software. The following parameters in the anterior region were measured: Overjet, Overbite, dental midline shift. Pretreament models and the initial ClinChecks® revealed slight deviations in the parameters overjet 0.08 mm (standard deviation (SD) 0.3), overbite 0.3 mm (SD 0.4) and dental midline deviation 0.1mm (SD 0.4). The final model and the final ClinCheck® revealed larger deviations: the differences for the Overjet were on average 0.4 mm (SD 0.7), Overbite 0.9 mm (SD 0.9) and dental midline shift 0.4 mm (SD 0.5). The IT-based transmission of mal-aligned teeth into the ClinCheck® presentation provides sufficiently good accuracy. Tooth corrections in the vertical plane were more difficult to realize. A vertical overcorrection in the final ClinCheck®, a case refinement at the end of the treatment or additional measures (e.g. horizontal beveled attachments or vertical elastics) seems useful to achieve the individually intended therapeutic goal.

  14. Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

    International Nuclear Information System (INIS)

    1993-08-01

    The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993

  15. Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993.

  16. 75 FR 60723 - Seamless Refined Copper Pipe and Tube From Mexico: Final Determination of Sales at Less Than Fair...

    Science.gov (United States)

    2010-10-01

    ... Comment 4: Model Matching Hierarchy Comment 5: Nacobre's U.S. Date of Sale Comment 6: Treatment of Nacobre... suspension-of- liquidation instructions will remain in effect until further notice. Final Determination The...

  17. Treatment plan in amelogenesis imperfecta: A structured literature review on treatment protocols and dedicating the best possible options

    Directory of Open Access Journals (Sweden)

    Azari A.

    2008-12-01

    Full Text Available "nAmelogenesis imperfecta is an inherited disease that disturbs the formation of the enamel. It occurs as two main categories, hypomineralized and hypoplastic. Both deciduous and permanent teeth are affected, and the disorder may create unaesthetic appearance, dental sensitivity, and severe attrition. In this article through performing a structured literature review, numerous treatment modalities which so far advocated in rehabilitation of amelogenesis imperfecta in adults and children is discussed. The progressive changes on open bite, the problem of bonding during restorative phase of treatment , the rehabilitation difficulties of deciduous as well as permanent teeth is also discussed in detail and finally the interdisciplinary approach for treatment of this disability is demonstrated and some points for decision making in treatment protocols are suggested.

  18. 10 CFR 51.93 - Distribution of final environmental impact statement and supplement to final environmental impact...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Distribution of final environmental impact statement and supplement to final environmental impact statement; news releases. 51.93 Section 51.93 Energy NUCLEAR... Environmental Impact Statements-General Requirements § 51.93 Distribution of final environmental impact...

  19. Cetuximab in treatment of metastatic colorectal cancer

    DEFF Research Database (Denmark)

    Guren, Tormod Kyrre; Thomsen, Maria Morandi; Kure, Elin H

    2017-01-01

    BACKGROUND: The NORDIC-VII study is a randomised phase III trial of cetuximab plus continuous or intermittent fluorouracil, folinic acid, and oxaliplatin (Nordic FLOX) vs FLOX alone in first-line treatment of metastatic colorectal cancer. The present report presents an updated and final survival...

  20. Treatment of spent solutions containing tributylphosphate

    Energy Technology Data Exchange (ETDEWEB)

    Barinova, Ella A.; Diordiy, Mikhail N.; Karlina, Olga K. [Federal State Unitary Enterprise ' RADON' , 2/14, 7 th Rostovsky lane, Moscow (Russian Federation)

    2013-07-01

    The realization of the process of treatment of organic radioactive waste (RW) containing tributylphosphate (TBP) in hydrocarbon solvent under the laboratory conditions is considered in this work. The main parameters of the process have been investigated as well as the characteristics of the final process product - sodium-aluminium-phosphate glass matrix. (authors)

  1. Computerized radiation treatment planning

    International Nuclear Information System (INIS)

    Laarse, R. van der.

    1981-01-01

    Following a general introduction, a chain consisting of three computer programs which has been developed for treatment planning of external beam radiotherapy without manual intervention is described. New score functions used for determination of optimal incidence directions are presented and the calculation of the position of the isocentre for each optimum combination of incidence directions is explained. A description of how a set of applicators, covering fields with dimensions of 4 to 20 cm, for the 6 to 20 MeV electron beams of a MEL SL75-20 linear accelerator was developed, is given. A computer program for three dimensional electron beam treatment planning is presented. A microprocessor based treatment planning system for the Selectron remote controlled afterloading system for intracavitary radiotherapy is described. The main differences in treatment planning procedures for external beam therapy with neutrons instead of photons is discussed. A microprocessor based densitometer for plotting isodensity lines in film dosimetry is described. A computer program for dose planning of brachytherapy is presented. Finally a general discussion about the different aspects of computerized treatment planning as presented in this thesis is given. (Auth.)

  2. Psychodynamic Treatment of the Criminal Offender: Making the Case for Longer-Term Treatment in a Longer-Term Setting.

    Science.gov (United States)

    Mulay, Abby L; Kelly, Elspeth; Cain, Nicole M

    2017-01-01

    In recent years, prisons and jails have become de facto psychiatric hospitals, responsible for the care and treatment of individuals with serious mental illness. Historically, cognitive-behaviorally informed therapeutic approaches have been the treatment of choice among mental health practitioners in correctional settings. However, inmate-clients often present with complex diagnostic issues that are arguably better served by long-term treatment options, such as psychodynamic psychotherapy. We first review the nature of psychotherapy in the correctional setting, as well as treatment barriers and challenges faced by both mental health providers and inmate-clients. We then review treatment studies that examine the efficacy of various therapeutic techniques in correctional/forensic contexts. Finally, we argue that, due to the complex nature of psychopathology, average length of time incarcerated, and treatment issues that arise in this multifaceted and challenging setting, mental health treatment providers should consider providing psychodynamic treatment modalities when working with incarcerated individuals. We also argue that more research is needed to examine the efficacy of these treatment approaches with inmate-clients.

  3. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    DeTar, Carleton [P.I.

    2012-12-10

    This document constitutes the Final Report for award DE-FC02-06ER41446 as required by the Office of Science. It summarizes accomplishments and provides copies of scientific publications with significant contribution from this award.

  4. Pavement Edge Treatment Final Report

    Science.gov (United States)

    2018-01-01

    The New York City Connected Vehicle Pilot aims to improve the safety of travelers and pedestrians in the city through the deployment of connected vehicle technologies. This objective directly aligns with the city's Vision Zero initiative, which began...

  5. Electrokinetic treatment of contaminated soils, sludges, and lagoons. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Wittle, J.K. [Electro-Petroleum, Inc., Wayne, PA (United States); Pamukcu, S. [Lehigh Univ., Bethlehem, PA (United States). Dept. of Civil Engineering

    1993-04-01

    The electrokinetic process is an emerging technology for in-situ soil decontamination, in which chemical species, both ionic and nonionic are transported to an electrode site in soil. These products are subsequently removed from the ground via collection systems engineered for each specific application. Electrokinetics refer to movement of water, ions and charged particles relative to one another under the action of an applied direct current electric field. In a porous compact matrix of surface charged particles such as soil, the ion containing pore fluid may be made to flow to collection sites under the applied field. This report describes the effort undertaken to investigate electrokinetically enhanced transport of soil contaminants in synthetic systems. These systems consisted of clay or clay-sand mixtures containing known concentration of a selected heavy metal salt solution or an organic compound. Metals, surrogate radio nuclides and organic compounds evaluated in the program were representatives of those found at a majority of DOE sites. Degree of removal of these metals from soil by the electrokinetic treatment process was assessed through the metal concentration profiles generated across the soil between the electrodes. The best removals, from about 85 to 95% were achieved at the anode side of the soil specimens. Transient pH change had an effect on the metal movement via transient creation of different metal species with different ionic mobilities, as well as changing of the surface characteristics of the soil medium.

  6. Automatic initial and final segmentation in cleft palate speech of Mandarin speakers.

    Directory of Open Access Journals (Sweden)

    Ling He

    Full Text Available The speech unit segmentation is an important pre-processing step in the analysis of cleft palate speech. In Mandarin, one syllable is composed of two parts: initial and final. In cleft palate speech, the resonance disorders occur at the finals and the voiced initials, while the articulation disorders occur at the unvoiced initials. Thus, the initials and finals are the minimum speech units, which could reflect the characteristics of cleft palate speech disorders. In this work, an automatic initial/final segmentation method is proposed. It is an important preprocessing step in cleft palate speech signal processing. The tested cleft palate speech utterances are collected from the Cleft Palate Speech Treatment Center in the Hospital of Stomatology, Sichuan University, which has the largest cleft palate patients in China. The cleft palate speech data includes 824 speech segments, and the control samples contain 228 speech segments. The syllables are extracted from the speech utterances firstly. The proposed syllable extraction method avoids the training stage, and achieves a good performance for both voiced and unvoiced speech. Then, the syllables are classified into with "quasi-unvoiced" or with "quasi-voiced" initials. Respective initial/final segmentation methods are proposed to these two types of syllables. Moreover, a two-step segmentation method is proposed. The rough locations of syllable and initial/final boundaries are refined in the second segmentation step, in order to improve the robustness of segmentation accuracy. The experiments show that the initial/final segmentation accuracies for syllables with quasi-unvoiced initials are higher than quasi-voiced initials. For the cleft palate speech, the mean time error is 4.4ms for syllables with quasi-unvoiced initials, and 25.7ms for syllables with quasi-voiced initials, and the correct segmentation accuracy P30 for all the syllables is 91.69%. For the control samples, P30 for all the

  7. Evaluating the technical aspects of mixed waste treatment technologies

    International Nuclear Information System (INIS)

    Bagaasen, L.M.; Scott, P.A.

    1992-10-01

    This report discusses treatment of mixed wastes which is thought to be more complicated than treatment of either hazardous or radioactive wastes. In fact, the treatment itself is no more complicated: however, the regulations that define acceptability of the final waste disposal system are significantly more entangled, and sometimes in apparent conflict. This session explores the factors that influence the choice of waste treatment technologies, and expands on some of the limitations to their application. The objective of the presentation is to describe the technical factors that influence potential treatment processes and the ramifications associated with particular selections (for example, the generation of secondary waste streams). These collectively provide a framework for making informed treatment process selections

  8. Final Environmental Assessment for Rapid Attack Identification, Detection, and Reporting System - Block 10

    Science.gov (United States)

    2007-05-03

    Navassa Island, and Kingman Reef . 3 Through an agreement with the Republic of the Marshall Islands Government, US actions at USAKA are subject to...tripod (similar to the RE used at the Hosted Sites) 15 RAIDRS Block 10 Final Environmental Assessment Banana R ive r A t l an t i c...operations, wastewater treatment plants , fuel storage tanks, aircraft and ground vehicle refueling and maintenance operations, soil

  9. Engineered ecosystem for on-site wastewater treatment in tropical areas.

    Science.gov (United States)

    de Sá Salomão, André Luis; Marques, Marcia; Severo, Raul Gonçalves; da Cruz Roque, Odir Clécio

    2012-01-01

    There is a worldwide demand for decentralized wastewater treatment options. An on-site engineered ecosystem (EE) treatment plant was designed with a multistage approach for small wastewater generators in tropical areas. The array of treatment units included a septic tank, a submersed aerated filter, and a secondary decanter followed by three vegetated tanks containing aquatic macrophytes intercalated with one tank of algae. During 11 months of operation with a flow rate of 52 L h(-1), the system removed on average 93.2% and 92.9% of the chemical oxygen demand (COD) and volatile suspended solids (VSS) reaching final concentrations of 36.3 ± 12.7 and 13.7 ± 4.2 mg L(-1), respectively. Regarding ammonia-N (NH(4)-N) and total phosphorus (TP), the system removed on average 69.8% and 54.5% with final concentrations of 18.8 ± 9.3 and 14.0 ± 2.5 mg L(-1), respectively. The tanks with algae and macrophytes together contributed to the overall nutrient removal with 33.6% for NH(4)-N and 26.4% for TP. The final concentrations for all parameters except TP met the discharge threshold limits established by Brazilian and EU legislation. The EE was considered appropriate for the purpose for which it was created.

  10. Development of High-Performance Cast Crankshafts. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, Mark E [General Motors, Detroit, MI (United States)

    2017-03-31

    The objective of this project was to develop technologies that would enable the production of cast crankshafts that can replace high performance forged steel crankshafts. To achieve this, the Ultimate Tensile Strength (UTS) of the new material needs to be 850 MPa with a desired minimum Yield Strength (YS; 0.2% offset) of 615 MPa and at least 10% elongation. Perhaps more challenging, the cast material needs to be able to achieve sufficient local fatigue properties to satisfy the durability requirements in today’s high performance gasoline and diesel engine applications. The project team focused on the development of cast steel alloys for application in crankshafts to take advantage of the higher stiffness over other potential material choices. The material and process developed should be able to produce high-performance crankshafts at no more than 110% of the cost of current production cast units, perhaps the most difficult objective to achieve. To minimize costs, the primary alloy design strategy was to design compositions that can achieve the required properties with minimal alloying and post-casting heat treatments. An Integrated Computational Materials Engineering (ICME) based approach was utilized, rather than relying only on traditional trial-and-error methods, which has been proven to accelerate alloy development time. Prototype melt chemistries designed using ICME were cast as test specimens and characterized iteratively to develop an alloy design within a stage-gate process. Standard characterization and material testing was done to validate the alloy performance against design targets and provide feedback to material design and manufacturing process models. Finally, the project called for Caterpillar and General Motors (GM) to develop optimized crankshaft designs using the final material and manufacturing processing path developed. A multi-disciplinary effort was to integrate finite element analyses by engine designers and geometry-specific casting

  11. Extracorporeal Treatment for Metformin Poisoning

    DEFF Research Database (Denmark)

    Calello, Diane P; Liu, Kathleen D; Wiegand, Timothy J

    2015-01-01

    diverse professions, presents its systematic review and clinical recommendations for extracorporeal treatment in metformin poisoning. METHODS: A systematic literature search was performed, data extracted, findings summarized, and structured voting statements developed. A two-round modified Delphi method...... was used to achieve consensus on voting statements and RAND/UCLA Appropriateness Method to quantify disagreement. Anonymized votes and opinions were compiled and discussed. A second vote determined the final recommendations. RESULTS: One hundred seventy-five articles were identified, including 63 deaths...... appears to be amenable to extracorporeal treatments. Despite clinical evidence comprised mostly of case reports and suboptimal toxicokinetic data, the workgroup recommended extracorporeal removal in the case of severe metformin poisoning....

  12. MHD seed recovery and regeneration, Phase II. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1994-10-01

    This final report summarizes the work performed by the Space and Technology Division of the TRW Space and Electronics Group for the U.S. Department of Energy, Pittsburgh Energy Technology Center for the Econoseed process. This process involves the economical recovery and regeneration of potassium seed used in the MHD channel. The contract period of performance extended from 1987 through 1994 and was divided into two phases. The Phase II test results are the subject of this Final Report. However, the Phase I test results are presented in summary form in Section 2.3 of this Final Report. The Econoseed process involves the treatment of the potassium sulfate in spent MHD seed with an aqueous calcium formate solution in a continuously stirred reactor system to solubilize, as potassium formate, the potassium content of the seed and to precipitate and recover the sulfate as calcium sulfate. The slurry product from this reaction is centrifuged to separate the calcium sulfate and insoluble seed constituents from the potassium formate solution. The dilute solids-free potassium formate solution is then concentrated in an evaporator. The concentrated potassium formate product is a liquid which can be recycled as a spray into the MHD channel. Calcium formate is the seed regenerant used in the Econoseed process. Since calcium formate is produced in the United States in relatively small quantities, a new route to the continuous production of large quantities of calcium formate needed to support an MHD power industry was investigated. This route involves the reaction of carbon monoxide gas with lime solids in an aqueous medium.

  13. The final checkpoint. Cancer as an adaptive evolutionary mechanism

    Directory of Open Access Journals (Sweden)

    Rumena Petkova

    2016-05-01

    Full Text Available The mechanisms for identification of DNA damage and repair usually manage DNA damage very efficiently. If damaged cells manage to bypass the checkpoints where the integrity of the genome is assessed and the decisions whether to proceed with the cell cycle are made, they may evade the imperative to stop dividing and to die. As a result, cancer may develop. Warding off the potential sequence-altering effects of DNA damage during the life of the individual or the existence span of the species is controlled by a set of larger checkpoints acting on a progressively increasing scale, from systematic removal of damaged cells from the proliferative pool by means of repair of DNA damage/programmed cell death through ageing to, finally, cancer. They serve different purposes and act at different levels of the life cycle, safeguarding the integrity of the genetic backup of the individual, the genetic diversity of the population, and, finally, the survival of the species and of life on Earth. In the light of the theory that cancer is the final checkpoint or the nature's manner to prevent complex organisms from living forever at the expense of genetic stagnation, the eventual failure of modern anti-cancer treatments is only to be expected. Nevertheless, the medicine of today and the near future has enough potential to slow down the progression to terminal cancer so that the life expectancy and the quality of life of cancer-affected individuals may be comparable to those of healthy aged individuals.

  14. 76 FR 26178 - Modifications to Treatment of Aircraft and Vessel Leasing Income

    Science.gov (United States)

    2011-05-06

    ... Modifications to Treatment of Aircraft and Vessel Leasing Income AGENCY: Internal Revenue Service (IRS... final regulations addressing the treatment of certain income and assets related to the leasing of... controlled foreign corporations that derive income from the leasing of aircraft or vessels in foreign...

  15. Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Summary

    International Nuclear Information System (INIS)

    1997-09-01

    The purpose of the Waste Isolation Pilot Plant Disposal Final Supplemental Environmental Impact Statement (SEIS-II) is to provide information on environmental impacts regarding the Department of Energy''s (DOE) proposed disposal operations at WIPP. The Proposed Action describes the treatment and disposal of the Basic inventory of TRU waste over a 35-year period. The Action Alternatives proposed the treatment of the Basic Inventory and an Additional Inventory as well as the transportation of the treated waste to WIPP for disposal over a 150- to 190-year period. The three Action Alternatives include the treatment of TRU waste at consolidation sites to meet WIPP planning-basic Waste Acceptance Criteria, the thermal treatment of TRU waste to meet Land Disposal Restrictions, and the treatment of TRU waste by a shred and grout process. SEIS-II evaluates environmental impacts resulting from the various treatment options; the transportation of TRU waste to WIPP using truck, a combination of truck and regular rail service, and a combination of truck and dedicated rail service; and the disposal of this waste in the repository. Evaluated impacts include those to the general environment and to human health. Additional issues associated with the implementation of the alternatives are discussed to provide further understanding of the decisions to be reached and to provide the opportunity for public input on improving DOE''s Environmental Management Program

  16. The Slovaks support completion of MO34

    International Nuclear Information System (INIS)

    Holy, R.

    2007-01-01

    This year (2007) in March a reputable international agency GfK conducted a poll, which was focused primarily on the questions relating to the presence and future of nuclear energy sector in Slovakia as well as brand awareness of Slovenske elektrarne. It results from the poll that 2/3 of Slovak population is not against the completion of Units 3 and 4 of Mochovce NPP (EMO34), and this relates to as much as 87 % of the asked in the region within a 10 km distance from EMO! (author)

  17. Excerpts from the introductory statement by IAEA Director General. IAEA Board of Governors, Vienna, 25 November 1998

    International Nuclear Information System (INIS)

    ElBaradei, M.

    1998-01-01

    The document contains excerpts from the Introductory Statement made by the Director General of the IAEA at the IAEA Board of Governors on 25 November 1998. The following aspects from the Agency's activity are presented: inspections in Iraq in relation to its clandestine nuclear programme, conclusion of Additional Protocols to safeguards agreements, the strengthened safeguards system, Agency's involvement in safeguards verification in the Democratic People's Republic of Korea (DPRK), safety review at the Mochovce nuclear power plant in Slovakia, and the year 2000 (Y2K) computer system problems in the Agency's Member States

  18. Technical area status report for chemical/physical treatment

    International Nuclear Information System (INIS)

    Brown, C.H. Jr.; Schwinkendorf, W.E.

    1993-08-01

    The Office of Environmental Restoration and Waste Management (EM) was established by the Department of Energy (DOE) to direct and coordinate waste management and site remediation programs and activities throughout the DOE Complex. The Mixed Waste Integrated Program (MWIP) was created by the DOE Office of Technology Development (OTD) to develop, deploy, and complete appropriate technologies for the treatment of an DOE low-level mixed waste (LLMW). The MWIP mission includes development of strategies related to enhanced waste form production, improvements to and testing of the EM-30 baseline flowsheet for mixed waste treatment, programmatic oversight for ongoing technical projects, and specific technical tasks related to the site specific Federal Facilities Compliance Agreement (FFCA). The MWIP has established five Technical Support Groups (TSGs) based on primary functional areas of the Mixed Waste Treatment Plant) identified by EM-30. These TSGs are: (1) Front-End Waste Handling, (2) Chemical/Physical Treatment, (3) Waste Destruction and Stabilization, (4) Second-stage Destruction and Offgas Treatment, and (5) Final Waste Forms. The focus of this document is the Chemical/Physical Treatment System (CPTS). The CPTS performs the required pretreatment and/or separations on the waste streams passing through the system for discharge to the environment or efficient downstream processing. Downstream processing can include all system components except Front-End Waste Handling. The primary separations to be considered by the CPTS are: (1) removal of suspended and dissolved solids from aqueous and liquid organic streams, (2) separation of water from organic liquids, (3) treatment of wet and dry solids, including separation into constituents as required, for subsequent thermal treatment and final form processing, (4) mercury removal and control, and (5) decontamination of equipment and waste classified as debris

  19. Final Hazard Categorization for the Remediation of the 116-C-3 Chemical Waste Tanks

    Energy Technology Data Exchange (ETDEWEB)

    T. M. Blakley; W. D. Schofield

    2007-09-10

    This final hazard categorization (FHC) document examines the hazards, identifies appropriate controls to manage the hazards, and documents the commitments for the 116-C-3 Chemical Waste Tanks Remediation Project. The remediation activities analyzed in this FHC are based on recommended treatment and disposal alternatives described in the Engineering Evaluation for the Remediation to the 116-C-3 Chemical Waste Tanks (BHI 2005e).

  20. 5 CFR 1216.206 - Final determination.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 3 2010-01-01 2010-01-01 false Final determination. 1216.206 Section... PROCEEDINGS Demands or Requests for Testimony and Production of Documents § 1216.206 Final determination. The General Counsel makes the final determination on demands to requests to employees for production of...

  1. 45 CFR 150.219 - Final determination.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 1 2010-10-01 2010-10-01 false Final determination. 150.219 Section 150.219... Are Failing To Substantially Enforce HIPAA Requirements § 150.219 Final determination. If, after... the State a written notice of its final determination. The notice includes the following: (a...

  2. Supercritical water oxidation test bed effluent treatment study

    International Nuclear Information System (INIS)

    Barnes, C.M.

    1994-04-01

    This report presents effluent treatment options for a 50 h Supercritical Water Test Unit. Effluent compositions are calculated for eight simulated waste streams, using different assumed cases. Variations in effluent composition with different reactor designs and operating schemes are discussed. Requirements for final effluent compositions are briefly reviewed. A comparison is made of two general schemes. The first is one in which the effluent is cooled and effluent treatment is primarily done in the liquid phase. In the second scheme, most treatment is performed with the effluent in the gas phase. Several unit operations are also discussed, including neutralization, mercury removal, and evaporation

  3. Wet oxidative degradation of cellulosic wastes 5- chemical and thermal properties of the final waste forms

    International Nuclear Information System (INIS)

    Eskander, S.B.; Saleh, H.M.

    2002-01-01

    In this study, the residual solution arising from the wet oxidative degradation of solid organic cellulosic materials, as one of the component of radioactive solid wastes, using hydrogen peroxide as oxidant. Were incorporated into ordinary Portland cement matrix. Leaching as well as thermal characterizations of the final solidified waste forms were evaluated to meet the final disposal requirements. Factors, such as the amount of the residual solution incorporated, types of leachant. Release of different radionuclides and freezing-thaw treatment, that may affect the leaching characterization. Were studied systematically from the data obtained, it was found that the final solid waste from containing 35% residual solution in tap water is higher than that in ground water or sea water. Based on the data obtained from thermal analysis, it could be concluded that incorporating the residual solution form the wet oxidative degradation of cellulosic materials has no negative effect on the hydration of cement materials and consequently on the thermal stability of the final solid waste from during the disposal process

  4. Enhanced integrated nonthermal treatment system study

    International Nuclear Information System (INIS)

    Biagi, C.; Schwinkendorf, B.; Teheranian, B.

    1997-02-01

    The purpose of the Enhanced Nonthermal Treatment Systems (ENTS) study is to evaluate alternative configurations of one of the five systems evaluated in the Integrated Nonthermal Treatment Systems (INTS) study. Five alternative configurations are evaluated. Each is designed to enhance the final waste form performance by replacing grout with improved stabilization technologies, or to improve system performance by improving the destruction efficiency for organic contaminants. AU enhanced systems are alternative configurations of System NT-5, which has the following characteristics: Nonthermal System NT-5: (1) catalytic wet oxidation (CWO) to treat organic material including organic liquids, sludges, and soft (or combustible) debris, (2) thermal desorption of inorganic sludge and process residue, (3) washing of soil and inorganic debris with treatment by CWO of removed organic material, (4) metal decontamination by abrasive blasting, (5) stabilization of treated sludge, soil, debris, and untreated debris with entrained contamination in grout, and (6) stabilization of inorganic sludge, salts and secondary waste in polymer. System NT-5 was chosen because it was designed to treat combustible debris thereby minimizing the final waste form volume, and because it uses grout for primary stabilization. The enhanced nonthermal systems were studied to determine the cost and performance impact of replacing grout (a commonly used stabilization agent in the DOE complex) with improved waste stabilization methods such as vitrification and polymer

  5. 75 FR 60632 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Direct Final Rule

    Science.gov (United States)

    2010-10-01

    ... Waste Management System; Identification and Listing of Hazardous Waste; Direct Final Rule AGENCY... management and treatment of several F- and K-waste codes. These waste codes are F037, F038, K048, K049, K051... released from the waste, plausible and specific types of management of the petitioned waste, the quantities...

  6. Deployment Evaluation Methodology for the Electrometallurgical Treatment of DOE-EM Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Ramer, Ronald James; Adams, James Paul; Rynearson, Michael Ardel; Dahl, Christian Adam

    1999-01-01

    The Department of Energy - Environmental Management (DOE-EM) National Spent Nuclear Fuel Program (NSNFP) is charged with the disposition of legacy Spent Nuclear Fuel (SNF). The NSNFP, conducted by Lockheed Martin Idaho Technology Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL), is evaluating final disposition of SNF in the DOE complex. While direct repository disposal of the SNF is the preferred disposition option, some DOE SNF may need treatment to meet acceptance criteria at various disposition sites. Evaluations of treatment needs and options have been previously prepared, and further evaluations are ongoing activities in the DOE-EM NSNFP. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. As a planning basis, a need is assumed for a treatment process, either as a primary or backup technology, that is compatible with, and cost-effective for, this portion of the DOE-EM inventory. The current planning option for treating this SNF, pending completion of development work and National Environmental Policy Act (NEPA) analysis, is the EMT process under development by Argonne National Laboratory - West (ANL-W). A decision on the deployment of the EMT is pending completion of an engineering scale demonstration currently in progress at ANL-W. Treatment options and treatment locations will depend on fuel type and location of the fuel. One of the first steps associated with selecting one or more sites for treating SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. One of the major issues associated with SNF treatment is final disposition of treatment products and associated waste streams. During conventional SNF treatment, various chemicals are added that may increase the product

  7. Postsurgical Orthodontic Treatment Planning: a Case Report with 20 Years Follow-up.

    Science.gov (United States)

    Farronato, Giampietro; Garagiola, Umberto; Carletti, Vera; Cressoni, Paolo; Mortellaro, Carmen

    2011-01-01

    Traditionally, maxillofacial deformities are corrected surgically after an initial orthodontic treatment phase. However in, this article, the authors emphasize the postsurgical therapeutic protocol which is extremely important for determining the final and permanent retention of the corrected occlusion. A 55 year old female with severe skeletal Class II malocclusion is presented. Combined surgical and orthodontic correction of the malocclusion was used. : The step-by-step procedure the authors followed for the postsurgical therapy is described. The goals of the postoperative therapy were to restore and rehabilitate neuromuscular function, obtain occlusal stabilization, grind teeth selectively, and final occlusion retention. The importance of a surgical occlusal splint for rehabilitating stomatognathic neuromuscular function postoperatively was demonstrated. Furthermore, the orthodontic-prosthodontic treatment ensured occlusion stability after the surgical correction. The long-term results confirmed the efficacy of the treatment protocol presented here from both functional and aesthetical perspectives. Postsurgical orthodontic treatment is an important step in the surgical and orthodontic therapy of maxillofacial deformities.

  8. Postsurgical Orthodontic Treatment Planning: a Case Report with 20 Years Follow-up

    Directory of Open Access Journals (Sweden)

    Giampietro Farronato

    2011-04-01

    Full Text Available Background: Traditionally, maxillofacial deformities are corrected surgically after an initial orthodontic treatment phase. However in, this article, the authors emphasize the postsurgical therapeutic protocol which is extremely important for determining the final and permanent retention of the corrected occlusion.Methods: A 55 year old female with severe skeletal Class II malocclusion is presented. Combined surgical and orthodontic correction of the malocclusion was used.Results: The step-by-step procedure the authors followed for the postsurgical therapy is described. The goals of the postoperative therapy were to restore and rehabilitate neuromuscular function, obtain occlusal stabilization, grind teeth selectively, and final occlusion retention. The importance of a surgical occlusal splint for rehabilitating stomatognathic neuromuscular function postoperatively was demonstrated. Furthermore, the orthodontic-prosthodontic treatment ensured occlusion stability after the surgical correction. The long-term results confirmed the efficacy of the treatment protocol presented here from both functional and aesthetical perspectives.Conclusions: Postsurgical orthodontic treatment is an important step in the surgical and orthodontic therapy of maxillofacial deformities.

  9. 78 FR 69817 - Polyethylene Retail Carrier Bags From Thailand: Final Court Decision and Amended Final Results of...

    Science.gov (United States)

    2013-11-21

    ... Bags From Thailand: Final Court Decision and Amended Final Results of Administrative Review of the..., which recalculated the weighted-average duty margin for polyethylene retail carrier bags (PRCBs) from... Packaging at the CIT. \\2\\ See Polyethylene Retail Carrier Bags from Thailand: Final Results and Partial...

  10. Final Report

    DEFF Research Database (Denmark)

    Heiselberg, Per; Brohus, Henrik; Nielsen, Peter V.

    This final report for the Hybrid Ventilation Centre at Aalborg University describes the activities and research achievement in the project period from August 2001 to August 2006. The report summarises the work performed and the results achieved with reference to articles and reports published...

  11. Treatment of cyanide-contained Waste Water

    International Nuclear Information System (INIS)

    Scheglov, M.Y.

    1999-01-01

    This work contains results of theoretical and experimental investigations of possibility to apply industrial ionites of different kinds for recovering complex cyanide of some d-elements (Cu, Zn, an dso on) and free CN-ions with purpose to develop technology and unit for plating plant waste water treatment. Finally, on basis of experimental data about equilibrium kinetic and dynamic characteristic of the sorption in model solutions, strong base anionite in CN- and OH-forms was chosen. This anionite has the best values of operational sorption uptake. Recommendations of using the anionite have been developed for real cyanide-contained wastewater treatment

  12. Principles of mastitis treatment in sheep and goats.

    Science.gov (United States)

    Mavrogianni, Vasia S; Menzies, Paula I; Fragkou, Ilektra A; Fthenakis, George C

    2011-03-01

    This article indicates the principles for treatment of mastitis in ewes/does and explains the reasons why treatment may occasionally fail. It presents the principles for administration of antimicrobial agents at drying off of the animals. Finally, it addresses the risk of antimicrobials present in milk when improper withdrawal periods are used and the issues around testing for inhibitors before putting the milk into in a farm's tank. Copyright © 2011 Elsevier Inc. All rights reserved.

  13. 11 CFR 9409.9 - Final determination.

    Science.gov (United States)

    2010-01-01

    ... 11 Federal Elections 1 2010-01-01 2010-01-01 false Final determination. 9409.9 Section 9409.9... INFORMATION AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS § 9409.9 Final determination. The General Counsel will make the final determination on demands and requests to employees for production of official...

  14. 48 CFR 32.605 - Final decisions.

    Science.gov (United States)

    2010-10-01

    ... REQUIREMENTS CONTRACT FINANCING Contract Debts 32.605 Final decisions. (a) The contracting officer shall issue a final decision as required by 33.211 if— (1) The contracting officer and the contractor are unable... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Final decisions. 32.605...

  15. 75 FR 50930 - Final Determination To Approve Alternative Final Cover Request for the Lake County, Montana Landfill

    Science.gov (United States)

    2010-08-18

    ... Determination To Approve Alternative Final Cover Request for the Lake County, Montana Landfill AGENCY... VIII is making a final determination to approve an alternative final cover for the Lake County landfill, a municipal solid waste landfill (MSWLF) owned and operated by Lake County, Montana on the...

  16. 32 CFR 536.64 - Final offers.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 3 2010-07-01 2010-07-01 true Final offers. 536.64 Section 536.64 National... UNITED STATES Investigation and Processing of Claims § 536.64 Final offers. (a) When claims personnel... less than the amount claimed, a settlement authority will make a written final offer within his or her...

  17. In-Patient Treatment of Severe Acute Malnutrition

    DEFF Research Database (Denmark)

    Rytter, Maren Johanne Heilskov

    Severe acute malnutrition is a serious health problem among children in low-income countries. Particularly malnourished children requiring in-hospital treatment are at high risk of dying. This dissertation investigates possible reasons for this high mortality, by following a group of 120 children...... during their in-hospital treatment of severe acute malnutrition at Mwanamugimu Nutrition Unit in Kampala, Uganda. We assessed how malnutrition affected the children’s immune system, by measuring the size of their thymus gland with ultrasound. We examined characteristics of children with the serious form...... of malnutrition, Kwashiorkor, where the children develop oedema. Finally, we explored symptoms, findings or treatments given that were associated with a higher risk of death in the children. Hopefully, these findings may contribute to improving the treatment offered to children with severe acute malnutrition....

  18. MO-G-BRE-04: Automatic Verification of Daily Treatment Deliveries and Generation of Daily Treatment Reports for a MR Image-Guided Treatment Machine

    International Nuclear Information System (INIS)

    Yang, D; Li, X; Li, H; Wooten, H; Green, O; Rodriguez, V; Mutic, S

    2014-01-01

    Purpose: Two aims of this work were to develop a method to automatically verify treatment delivery accuracy immediately after patient treatment and to develop a comprehensive daily treatment report to provide all required information for daily MR-IGRT review. Methods: After systematically analyzing the requirements for treatment delivery verification and understanding the available information from a novel MR-IGRT treatment machine, we designed a method to use 1) treatment plan files, 2) delivery log files, and 3) dosimetric calibration information to verify the accuracy and completeness of daily treatment deliveries. The method verifies the correctness of delivered treatment plans and beams, beam segments, and for each segment, the beam-on time and MLC leaf positions. Composite primary fluence maps are calculated from the MLC leaf positions and the beam-on time. Error statistics are calculated on the fluence difference maps between the plan and the delivery. We also designed the daily treatment delivery report by including all required information for MR-IGRT and physics weekly review - the plan and treatment fraction information, dose verification information, daily patient setup screen captures, and the treatment delivery verification results. Results: The parameters in the log files (e.g. MLC positions) were independently verified and deemed accurate and trustable. A computer program was developed to implement the automatic delivery verification and daily report generation. The program was tested and clinically commissioned with sufficient IMRT and 3D treatment delivery data. The final version has been integrated into a commercial MR-IGRT treatment delivery system. Conclusion: A method was developed to automatically verify MR-IGRT treatment deliveries and generate daily treatment reports. Already in clinical use since December 2013, the system is able to facilitate delivery error detection, and expedite physician daily IGRT review and physicist weekly chart

  19. Deep inelastic final states

    International Nuclear Information System (INIS)

    Girardi, G.

    1980-11-01

    In these lectures we attempt to describe the final states of deep inelastic scattering as given by QCD. In the first section we shall briefly comment on the parton model and give the main properties of decay functions which are of interest for the study of semi-inclusive leptoproduction. The second section is devoted to the QCD approach to single hadron leptoproduction. First we recall basic facts on QCD log's and derive after that the evolution equations for the fragmentation functions. For this purpose we make a short detour in e + e - annihilation. The rest of the section is a study of the factorization of long distance effects associated with the initial and final states. We then show how when one includes next to leading QCD corrections one induces factorization breaking and describe the double moments useful for testing such effects. The next section contains a review on the QCD jets in the hadronic final state. We begin by introducing the notion of infrared safe variable and defining a few useful examples. Distributions in these variables are studied to first order in QCD, with some comments on the resummation of logs encountered in higher orders. Finally the last section is a 'gaullimaufry' of jet studies

  20. 36 CFR 908.33 - Final determination.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false Final determination. 908.33... DEVELOPMENT AREA Review Procedure § 908.33 Final determination. (a) The Chairman or designee(s) shall make a final determination on the claim within 45 days of receipt of the file from the Director of Real Estate...

  1. Uninterrupted heat-treatment of starch raw materials

    Energy Technology Data Exchange (ETDEWEB)

    Bronshtein, D Z

    1958-01-01

    A setup is presented, with a Rekord grinder, a Khronos scale, and other equipment of Soviet manufacture, in which oats, rye, wheat, and other grains are treated at 42 to 45 degrees prior to their use as raw materials in the ethanol industry. These materials are analyzed with respect to H/sub 2/O, starch, bulk, weight, screen analysis, and the final ethanol yields/ton of such raw materials. In a three year run in plant, this heat-treatment was advantageous, as compared to the former treatment of the starch materials.

  2. Uninterrupted heat-treatment of starch raw materials

    Energy Technology Data Exchange (ETDEWEB)

    Bronshtein, D Z

    1958-01-01

    A setup is presented, with a Rekord grinder, a Khronos scale, and other equipment of Soviet manufacture, in which oats, rye, wheat, and other grains are treated at 42 to 45/sup 0/ prior to their use as raw materials in the ethanol industry. These materials are analyzed with respect to H/sub 2/O, starch, bulk weight, screen analysis, and the final ethanol yields/ton of such raw materials. In a three year run in a plant, this heat-treatment was advantageous, as compared to the former treatment of the starch materials.

  3. Data breaches. Final rule.

    Science.gov (United States)

    2008-04-11

    This document adopts, without change, the interim final rule that was published in the Federal Register on June 22, 2007, addressing data breaches of sensitive personal information that is processed or maintained by the Department of Veterans Affairs (VA). This final rule implements certain provisions of the Veterans Benefits, Health Care, and Information Technology Act of 2006. The regulations prescribe the mechanisms for taking action in response to a data breach of sensitive personal information.

  4. Final focus system for TLC

    International Nuclear Information System (INIS)

    Oide, K.

    1988-11-01

    A limit of the chromaticity correction for the final focus system of a TeV Linear Collider (TLC) is investigated. As the result, it becomes possible to increase the aperture of the final doublet with a small increase of the horizontal β function. The new optics design uses a final doublet of 0.5 mm half-aperture and 1.4 T pole-tip field. The length of the system is reduced from 400 m to 200 m by several optics changes. Tolerances for various machine errors with this optics are also studied. 5 refs., 7 figs., 2 tabs

  5. Cassini's Grand Finale Overview

    Science.gov (United States)

    Spilker, L. J.

    2017-12-01

    After 13 years in orbit, the Cassini-Huygens Mission to Saturn ended in a science-rich blaze of glory. Cassini sent back its final bits of unique science data on September 15, 2017, as it plunged into Saturn's atmosphere, vaporizing and satisfying planetary protection requirements. Cassini's final phase covered roughly ten months and ended with the first time exploration of the region between the rings and planet. In late 2016 Cassini transitioned to a series of 20 Ring Grazing orbits with peripases just outside Saturn's F ring, providing close flybys of tiny ring moons, including Pan, Daphnis and Atlas, and high-resolution views of Saturn's A and F rings. A final Titan flyby in late April 2017 propelled Cassini across Saturn's main rings and into its Grand Finale orbits. Comprised of 22 orbits, Cassini repeatedly dove between Saturn's innermost rings and upper atmosphere to answer fundamental questions unattainable earlier in the mission. The last orbit turned the spacecraft into the first Saturn atmosphere probe. The Grand Finale orbits provided highest resolution observations of both the rings and Saturn, and in-situ sampling of the ring particle composition, Saturn's atmosphere, plasma, and innermost radiation belts. The gravitational field was measured to unprecedented accuracy, providing information on the interior structure of the planet, winds in the deeper atmosphere, and mass of the rings. The magnetic field provided insight into the physical nature of the magnetic dynamo and structure of the internal magnetic field. The ion and neutral mass spectrometer sampled the upper atmosphere for molecules that escape the atmosphere in addition to molecules originating from the rings. The cosmic dust analyzer directly sampled the composition from different parts of the main rings for the first time. Fields and particles instruments directly measured the plasma environment between the rings and planet. Science highlights and new mysteries collected in the Grand

  6. Effluent treatment plant for pharmaceutical unit at Bahipheru - case study

    International Nuclear Information System (INIS)

    Hayat, A.

    1997-01-01

    This project has been awarded to environ (Pvt) Ltd., on turnkey basis, and is an integrated waste treatment facility for pharmaceuticals companies, manufacturing paracetamole, aspirin and various pharmaceuticals intermediates, from phenol as basic raw material. A highly toxic waste water, containing high concentrations of phenolics and sulfate ions is generated at this plant and has to be treatment before final disposal into an irrigation channel. (author)

  7. Effects of hot water treatments on dormant grapevine propagation materials used for grafted vine production

    Directory of Open Access Journals (Sweden)

    Soltekin Oguzhan

    2017-01-01

    Full Text Available Agrobacterium vitis is responsible for the crown gall disease of grapevine which breaks the grapevine trunk vascular system. Nutrient flow is prevented by crown gall and it leads to weak growth and death of the plants. It can be destructive disease often encountered in vineyards and it can be spread in cuttings for propagation. Thermotherapy treatment is an alternative method for eradicating A. vitis from grapevine cuttings but effects of thermotherapy treatments on dormant vine tissue, bud vitality, rooting and shooting of the propagation materials are not yet fully understood. In this research, it is aimed to determine the effects of thermotherapy treatment (Hot water treatment on callus formation (at the basal part and grafting point, grafted vine quality (shoot length, shoot width, root number, shooting and rooting development, fresh and dry weight of shoots and roots and final take in the grafted vine production. Experiment was conducted in the nursery of Manisa Viticultural Research Institute. Rootstocks (Kober 5BB, Couderc 1613 and 41B and scions (Sultan 7 and Manisa sultanı were hot-water treated at 50°C for 30 minutes which is the most common technique against Agrobacterium vitis. After thermotherapy treatment, all rootstocks were grafted with Sultan 7 and Manisa sultanıvarieties. They were kept for 22 days in callusing room for callus development and then they were planted in polyethlyene bags for rooting. At the end of the study, significant treatment x rootstock interaction were observed for the final take of Sultan 7 variety. Thermotherapy treated of 1613C/Sultan 7 combinations had more final take than the control (untreated group. For instance, hot water treated cuttings of 1613C/Sultan 7 combinations had 75% final take while the control group had the 70%. Also there were not observed any adverse effects of HWT on bud and tissue vitality.

  8. Nail Psoriasis: A Review of Treatment Options.

    Science.gov (United States)

    Pasch, Marcel C

    2016-04-01

    Nail involvement affects 80-90 % of patients with plaque psoriasis, and is even more prevalent in patients with psoriatic arthritis. This review is the result of a systemic approach to the literature and covers topical, intralesional, conventional systemic, and biologic systemic treatments, as well as non-pharmacological treatment options for nail psoriasis. The available evidence suggests that all anti-tumor necrosis factor-α, anti-interleukin (IL)-17, and anti-IL-12/23 antibodies which are available for plaque psoriasis and psoriatic arthritis are highly effective treatments for nail psoriasis. Conventional systemic treatments, including methotrexate, cyclosporine, acitretin, and apremilast, as well as intralesional corticosteroids, can also be effective treatments for nail psoriasis. Topical treatments, including corticosteroids, calcipotriol, tacrolimus, and tazarotene, have also been shown to have a position in the treatment of nail psoriasis, particularly in mild cases. Finally, non-pharmacological treatment options, including phototherapy, photodynamic therapy, laser therapy, and several radiotherapeutic options, are also reviewed but cannot be advised as first-line treatment options. Another conclusion of this review is that the lack of a reliable core set of outcomes measures for trials in nail psoriasis hinders the interpretation of results, and is urgently needed.

  9. Thermomechanical Treatments on High Strength Al-Zn-Mg(-Cu) Alloys

    National Research Council Canada - National Science Library

    Di Russo, E; Conserva, M; Gatto, F

    1974-01-01

    An investigation was carried out to determine the metallurgical properties of Al-Zn-Mg and Al-Zn-Mg-Cu alloy products processed according to newly developed Final Thermomechanical Treatments (FTMT) of T-AHA type...

  10. Thermochemical treatment of biogas digestate solids to produce organic fertilisers

    DEFF Research Database (Denmark)

    Pantelopoulos, Athanasios

    digestate, are acknowledged for their potential to serve as organic amendments and fertilizers however, their characteristics constitutes them prone to N losses, and their management (handling, storage, transportation) costly. Thermal drying of manures is known to facilitate transportation by volume...... reduction, nutrient concentration and hygienization of the final product. However, thermal treatment of ammonium rich organic wastes such as digestate solids has been linked with relative high volatilization of NH3 and therefore decrease in N fertilizing value of the final product. Temperature and air...... solids had low N fertilizing value due to the excessive loses of inorganic N during the drying process. On the contrary, acidification minimized ammonia volatilization from solids during the thermal treatment with direct impact on the N fertilizing value of acid treated solids. In addition, acidification...

  11. N-containing carbons from styrene-divinylbenzene copolymer by urea treatment

    Energy Technology Data Exchange (ETDEWEB)

    Zhuravsky, Sergey V.; Kartel, Mykola T.; Tarasenko, Yuriy O. [Chuiko Institute of Surface Chemistry, National Academy of Sciences of Ukraine, 17 General Naumov Street, Kiev, 03164 (Ukraine); Villar-Rodil, Silvia [Instituto Nacional del Carbon, INCAR-CSIC, Apartado 73, 33080 Oviedo (Spain); Dobos, Gabor [Department of Atomic Physics, Budapest University of Technology and Economics, H-1521 Budapest (Hungary); Toth, Ajna [Department of Physical Chemistry and Materials Science, Budapest University of Technology and Economics, H-1521 Budapest, PO Box 92 (Hungary); Tascon, Juan M.D. [Instituto Nacional del Carbon, INCAR-CSIC, Apartado 73, 33080 Oviedo (Spain); Laszlo, Krisztina, E-mail: klaszlo@mail.bme.hu [Department of Physical Chemistry and Materials Science, Budapest University of Technology and Economics, H-1521 Budapest, PO Box 92 (Hungary)

    2012-01-15

    N-containing synthetic carbons with narrow porosity were prepared from a chlorinated styrene and divinylbenzene copolymer by a multistep method with a yield of 34 wt%. Surface chemical treatment and thermal carbonization of the starting copolymer was monitored by urea impregnation. Steam activation, oxidation and an additional heat treatment gave the final product. The synthesis route was designed in a cost-effective way. The porosity and the concentration of the introduced nitrogen atoms were determined at each step. The final product has a surface area of 1135 m{sup 2}/g. More than 70% of the pore volume comes from micropores with an average width of 0.7 nm. The 2.3 at.% surface nitrogen atoms are distributed among five detectable species, of which about 44% is quaternary nitrogen.

  12. 77 FR 14416 - Notice of Availability of a Final Environmental Impact Statement and Final Environmental Impact...

    Science.gov (United States)

    2012-03-09

    ...In accordance with the National Environmental Policy Act of 1969, as amended (NEPA), and the Federal Land Policy and Management Act of 1976, as amended (FLPMA), the Bureau of Land Management (BLM) has prepared a Proposed California Desert Conservation Area (CDCA) Plan Amendment (PA)/Final Environmental Impact Statement (EIS) and Final Environmental Impact Report (EIR) for the Ocotillo Express Wind Energy Facility (OWEF) and by this notice is announcing the availability of the Proposed PA and Final EIS/EIR.

  13. Mixed Waste Salt Encapsulation Using Polysiloxane - Final Report

    International Nuclear Information System (INIS)

    Miller, C.M.; Loomis, G.G.; Prewett, S.W.

    1997-01-01

    A proof-of-concept experimental study was performed to investigate the use of Orbit Technologies polysiloxane grouting material for encapsulation of U.S. Department of Energy mixed waste salts leading to a final waste form for disposal. Evaporator pond salt residues and other salt-like material contaminated with both radioactive isotopes and hazardous components are ubiquitous in the DOE complex and may exceed 250,000,000 kg of material. Current treatment involves mixing low waste percentages (less than 10% by mass salt) with cement or costly thermal treatment followed by cementation to the ash residue. The proposed technology involves simple mixing of the granular salt material (with relatively high waste loadings-greater than 50%) in a polysiloxane-based system that polymerizes to form a silicon-based polymer material. This study involved a mixing study to determine optimum waste loadings and compressive strengths of the resultant monoliths. Following the mixing study, durability testing was performed on promising waste forms. Leaching studies including the accelerated leach test and the toxicity characteristic leaching procedure were also performed on a high nitrate salt waste form. In addition to this testing, the waste form was examined by scanning electron microscope. Preliminary cost estimates for applying this technology to the DOE complex mixed waste salt problem is also given

  14. [Surgical treatment of anal fistula].

    Science.gov (United States)

    Zeng, Xiandong; Zhang, Yong

    2014-12-01

    Anal fistula is a common disease. It is also quite difficult to be solved without recurrence or damage to the anal sphincter. Several techniques have been described for the management of anal fistula, but there is no final conclusion of their application in the treatment. This article summarizes the history of anal fistula management, the current techniques available, and describes new technologies. Internet online searches were performed from the CNKI and Wanfang databases to identify articles about anal fistula management including seton, fistulotomy, fistulectomy, LIFT operation, biomaterial treatment and new technology application. Every fistula surgery technique has its own place, so it is reasonable to give comprehensive individualized treatment to different patients, which may lead to reduced recurrence and avoidance of damage to the anal sphincter. New technologies provide promising alternatives to traditional methods of management. Surgeons still need to focus on the invention and improvement of the minimally invasive techniques. Besides, a new therapeutic idea is worth to explore that the focus of surgical treatment should be transferred to prevention of the formation of anal fistula after perianal abscess.

  15. Definition of treatment geometry in radiation therapy

    International Nuclear Information System (INIS)

    Aaltonen, P.

    1996-01-01

    When accurate systems for quality assurance and treatment optimization are employed, a precise system for fixation and dosimetric and portal verification are as important as a continued and standardized code of practice for dosimetry and patient follow-up, including registration of tumour responses and acute and late normal tissue reactions. To improve the accuracy of existing dose response relations in order to improve future therapy the treatment geometry and dose delivery concepts have to be accurately defined and uniformly employed. A Nordic working group was set up in 1991 (by Nordic Association of Clinica Physics) to standardize the concepts and quantities used during the whole radiotherapy process in the Nordic countries. Now the group is finalizing its report ''Specification of Dose Delivery in Radiation Therapy''. The report emphasizes that the treatment geometry shall be consistent with the geometry used during the diagnostic work up. The patient fixation is of importance early in the diagnostic phase to ensure that the same reference points and patients position will be used both during the diagnostic work up, simulation and treatment execution. Reference Coordinate System of the patient is a concept based on defined anatomic reference points. This Patient Reference System is a local system which has validity for the tissues, organs and volumes defined during radiotherapy. The reference points of the Patient Reference System should in turn be used for beam set-up. The treatment geometry is then defined by using different concepts describing tissues which are mobile in the Patient Reference System, and finally, volumes which are fixed in this coordinate system. A Set-up Margin has to be considered for movements of the volumes defined in the Reference Coordinate System of the Patient in relation to the radiation beam. The Set-up Margin is dependent on the treatment technique and it is needed in the treatment planning procedure to ensure that the prescribed

  16. Definition of treatment geometry in radiation therapy

    Energy Technology Data Exchange (ETDEWEB)

    Aaltonen, P [Finnish Centre for Radiation and Nuclear Safety (STUK), Helsinki (Finland)

    1996-08-01

    When accurate systems for quality assurance and treatment optimization are employed, a precise system for fixation and dosimetric and portal verification are as important as a continued and standardized code of practice for dosimetry and patient follow-up, including registration of tumour responses and acute and late normal tissue reactions. To improve the accuracy of existing dose response relations in order to improve future therapy the treatment geometry and dose delivery concepts have to be accurately defined and uniformly employed. A Nordic working group was set up in 1991 to standardize the concepts and quantities used during the whole radiotherapy process in the Nordic countries. Now the group is finalizing its report ``Specification of Dose Delivery in Radiation Therapy``. The report emphasizes that the treatment geometry shall be consistent with the geometry used during the diagnostic work up. The patient fixation is of importance early in the diagnostic phase to ensure that the same reference points and patients position will be used both during the diagnostic work up, simulation and treatment execution. Reference Coordinate System of the patient is a concept based on defined anatomic reference points. This Patient Reference System is a local system which has validity for the tissues, organs and volumes defined during radiotherapy. The reference points of the Patient Reference System should in turn be used for beam set-up. The treatment geometry is then defined by using different concepts describing tissues which are mobile in the Patient Reference System, and finally, volumes which are fixed in this coordinate system. A Set-up Margin has to be considered for movements of the volumes defined in the Reference Coordinate System of the Patient in relation to the radiation beam. The Set-up Margin is dependent on the treatment technique and it is needed in the treatment planning procedure to ensure that the prescribed dose to the Target Volume is delivered.

  17. Effects of corona discharge treatment on some properties of wool ...

    African Journals Online (AJOL)

    Yomi

    2011-12-21

    Dec 21, 2011 ... Corona discharge after operation worsted water absorption property increased and the ... finally conditioned with atmospheric air (20°C, relative humidity ... For corona treatment, a glow discharge generator was used with a.

  18. Immobilization in ceramic waste forms of the residues from treatment of mixed wastes

    International Nuclear Information System (INIS)

    Oversby, V.M.; van Konynenburg, R.A.; Glassley, W.E.; Curtis, P.G.

    1993-11-01

    The Environmental Restoration and Waste Management Applied Technology Program at LLNL is developing a Mixed Waste Management Facility to demonstrate treatment technologies that provide an alternative to incineration. As part of that program, we are developing final waste forms using ceramic processing methods for the immobilization of the treatment process residues. The ceramic phase assemblages are based on using Synroc D as a starting point and varying the phase assemblage to accommodate the differences in chemistry between the treatment process residues and the defense waste for which Synroc D was developed. Two basic formulations are used, one for low ash residues resulting from treatment of organic materials contaminated with RCRA metals, and one for high ash residues generated from the treatment of plastics and paper products. Treatment process residues are mixed with ceramic precursor materials, dried, calcined, formed into pellets at room temperature, and sintered at 1150 to 1200 degrees C to produce the final waste form. This paper discusses the chemical composition of the waste streams and waste forms, the phase assemblages that serve as hosts for inorganic waste elements, and the changes in waste form characteristics as a function of variation in process parameters

  19. Clinical observation of two treatments for vitreous hemorrhage

    Directory of Open Access Journals (Sweden)

    He-Yi Li

    2014-08-01

    Full Text Available AIM: To investigate the indications and therapeutic effect of the conservative treatment and surgical treatment for vitreous hemorrhage.METHODS: Hemorrhage reasons, degree of illness, and treatment and final results of vitreous hemorrhage were recorded from 2008 to 2013, and curative effect of different treatments was analyzed.RESULTS: Selected 22 cases(24 eyesof conservative treatment, vision degree of 6 eyes(25%had raised, 5 eyes(21%occurred secondary retinal detachment without treatment, 3 eyes(12.5%suffered neovascular glaucoma were underwent operation, but the vision had lost completely. In 26 cases(31 eyesof control(operationgroup, vision of 17 eyes(55%had improved, 2 eyes(6.5%suffered the second operation, 2 eyes(6.5%suffered the third surgery, 3 eyes(10%suffered eyeball atrophy. The number of ultimate vision improved with conservative treatment were significantly lower than the number of cases with surgical treatment(PCONCLUSION: The surgical treatment is still visible vitreous hemorrhage treatment means of positive, but there will be eyeball atrophy and other serious complications, so we should choose a different methods in according to the different treatment objects and treatment time.

  20. Cost effective water treatment program in Heavy Water Plant (Manuguru)

    International Nuclear Information System (INIS)

    Mohapatra, C.; Prasada Rao, G.

    2002-01-01

    Water treatment technology is in a state of continuous evolution. The increasing urgency to conserve water and reduce pollution has in recent years produced an enormous demand for new chemical treatment programs and technologies. Heavy water plant (Manuguru) uses water as raw material (about 3000 m 3 /hr) and its treatment and management has benefited the plant in a significant way. It is a fact that if the water treatment is not proper, it can result in deposit formation and corrosion of metals, which can finally leads to production losses. Therefore, before selecting treatment program, complying w.r.t. quality requirements, safety and pollution aspects cost effectiveness shall be examined. The areas where significant benefits are derived, are raw water treatment using polyelectrolyte instead of inorganic coagulant (alum), change over of regenerant of cation exchangers from hydrochloric acid to sulfuric acid and in-house development of cooling water treatment formulation. The advantages and cost effectiveness of these treatments are discussed in detail. Further these treatments has helped the plant in achieving zero discharge and indirectly increased cost reduction of final product (heavy water); the dosage of 3 ppm of polyelectrolyte can replace 90 ppm alum at turbidity level of 300 NTU of raw water which has resulted in cost saving of Rs. 15-20 lakhs in a year beside other advantages; the change over of regenerant from HCl to H 2 SO 4 will result in cost saving of at least Rs.1.4 crore a year besides other advantages; the change over to proprietary formulation to in-house formulation in cooling water treatment has resulted in a saving about Rs.11 lakhs a year. To achieve the above objectives in a sustainable way the performance results are being monitored. (author)

  1. Gemstone enhancement. Heat, irradiation, impregnation, dyeing, and other treatments which alter the appearance of gemstones, and the detection of such treatments

    Energy Technology Data Exchange (ETDEWEB)

    Nassau, K.

    1984-01-01

    One of the important tasks of the gemologist is to identify treatments which may have been used to modify the colour or appearance of the gemstones being examined. The book is written for gemologists, to explain the details of possible treatment techniques. An historical account of treatments is given in chapter 2, general accounts of heat treatments in chapter 3, irradiations in chapter 4 and miscellaneous techniques (including impregnation and dyeing) in chapter 5. Chapter 6 is a brief discussion of the identification techniques used to reveal treatments. In chapter 7 the various gemstone materials are considered alphabetically, by groups. The irradiation treatments considered in chapter 4 start by summarising and explaining the rays and particles used for the irradiation of gemstones. The major colour changes that occur on irradiation are tabulated. Colour centres are explained. Colour-centre-like colour changes are mentioned. Finally, radioactive gemstones are considered.

  2. Radiation treatment of sewage effluent, (2)

    International Nuclear Information System (INIS)

    Sawai, Teruko; Sekiguchi, Masayuki; Sawai, Takeshi; Shimokawa, Toshinari; Tanabe, Hiroko

    1991-01-01

    The water demand of the past several years has increased rapidly. Recycling of municipal waste water is an effective mean of coping with the water shortage in Tokyo. We studied the radiation treatment method of further purification of the effluent from sewage treatment plants. By gamma irradiation the refractory organic substances in the effluent were decomposed and the COD values decreased with increasing dose. The high molecular weight components in the effluent were degraded to lower molecular weight substances and were decomposed finally to carbon dioxide. In this paper we studied on the fading color and the reducing of order of sewage effluent. (author)

  3. Development of treatment technologies for the processing of US Department of Energy mixed waste

    International Nuclear Information System (INIS)

    Backus, P.M.; Berry, J.B.; Coyle, G.J.; Lurk, P.W.; Wolf, S.M.

    1993-01-01

    Waste contaminated with chemically hazardous and radioactive species is defined as mixed waste. Significant technology development has been conducted for separate treatment of hazardous and radioactive waste, but technology development addressing mixed-waste treatment has been limited. Management of mixed waste requires treatment which must meet the standards established by the US Environmental Protection Agency for the specific hazardous constituents while also providing adequate control of the radionuclides. Technology has not been developed, demonstrated, or tested to produce a low-risk final waste form specifically for mixed waste. Throughout the US Department of Energy (DOE) complex, mixed waste is a problem because definitive treatment standards have not been established and few disposal facilities are available. Treatment capability and capacity are also limited. Site-specific solutions to the management of mixed waste have been initiated; however, site-specific programs result in duplication of technology development between various sites. Significant progress is being made in developing technology for mixed waste under the Mixed Waste Integrated Program. The status of the technical initiatives in chemical/physical treatment, destruction/stabilization technology, off-gas treatment, and final waste form production/assessment is described in this paper

  4. Integrated ecotechnology approach towards treatment of complex wastewater with simultaneous bioenergy production.

    Science.gov (United States)

    Hemalatha, Manupati; Sravan, J Shanthi; Yeruva, Dileep Kumar; Venkata Mohan, S

    2017-10-01

    Sequential integration of three stage diverse biological processes was studied by exploiting the individual process advantage towards enhanced treatment of complex chemical based wastewater. A successful attempt to integrate sequence batch reactor (SBR) with bioelectrochemical treatment (BET) and finally with microalgae treatment was studied. The sequential integration has showed individual substrate degradation (COD) of 55% in SBR, 49% in BET and 56% in microalgae, accounting for a consolidated treatment efficiency of 90%. Nitrates removal efficiency of 25% was observed in SBR, 31% in BET and 44% in microalgae, with a total efficiency of 72%. The SBR treated effluents fed to BET with the electrode intervention showed TDS removal. BET exhibited relatively higher process performance than SBR. The integration approach significantly overcame the individual process limitations along with value addition as biomass (1.75g/L), carbohydrates (640mg/g), lipids (15%) and bioelectricity. The study resulted in providing a strategy of combining SBR as pretreatment step to BET process and finally polishing with microalgae cultivation achieving the benefits of enhanced wastewater treatment along with value addition. Copyright © 2017 Elsevier Ltd. All rights reserved.

  5. Biochemical and physical characterisation of urinary nanovesicles following CHAPS treatment.

    Science.gov (United States)

    Musante, Luca; Saraswat, Mayank; Duriez, Elodie; Byrne, Barry; Ravidà, Alessandra; Domon, Bruno; Holthofer, Harry

    2012-01-01

    Urinary exosomes represent a precious source of potential biomarkers for disease biology. Currently, the methods for vesicle isolation are severely restricted by the tendency of vesicle entrapment, e.g. by the abundant Tamm-Horsfall protein (THP) polymers. Treatment by reducing agents such as dithiothreitol (DTT) releases entrapped vesicles, thus increasing the final yield. However, this harsh treatment can cause remodelling of all those proteins which feature extra-vesicular domains stabilized by internal disulfide bridges and have detrimental effects on their biological activity. In order to optimize exosomal yield, we explore two vesicle treatment protocols - dithiothreitol (DTT) and 3-[(3-cholamidopropyl)dimethylammonio]-1-propanesulfonic (CHAPS) - applied to the differential centrifugation protocol for exosomal vesicle isolation. The results show that CHAPS treatment does not affect vesicle morphology or exosomal marker distribution, thus eliminating most of THP interference. Moreover, the recovery and preservation of catalytic activity of two trans-membrane proteases, dipeptidyl peptidase IV and nephrilysin, was examined and found to be clearly superior after CHAPS treatment compared to DTT. Finally, proteomic profiling by mass spectrometry (MS) revealed that 76.2% of proteins recovered by CHAPS are common to those seen for DTT treatment, which illustrates underlining similarities between the two approaches. In conclusion, we provide a major improvement to currently-utilized urinary vesicle isolation strategies to allow recovery of urinary vesicles without the deleterious interference of abundant urinary proteins, while preserving typical protein folding and, consequently, the precious biological activity of urinary proteins which serve as valuable biomarkers.

  6. Dentoalveolar Segmental Osteotomy Combined with Orthodontic Treatment for an Impacted and Ankylosed Upper Canine

    DEFF Research Database (Denmark)

    Aludden, Hanna Cecilia; Jensen, Thomas

    2016-01-01

    Ankylosis is the abnormal adhesion of alveolar bone to dentin or cementum and commonly seen after traumatic dental injuries. Treatment of impacted and ankylosed teeth solely by orthodontics alignment may be challenging. Consequently, several treatment alternatives have been proposed for the manag....... A dentoalveolar segmental osteotomy with immediate repositioning of an upper canine was performed. One year after final orthodontic treatment a satisfying occlusal and esthetic treatment outcome was obtained....

  7. Comparison of surgical treatment with direct repair versus conservative treatment in young patients with spondylolysis: a prospective, comparative, clinical trial.

    Science.gov (United States)

    Lee, Gun Woo; Lee, Sun-Mi; Ahn, Myun-Whan; Kim, Ho-Joong; Yeom, Jin S

    2015-07-01

    Although direct repair (DR) with screw fixation at the pars defect is a common surgical treatment for lumbar spondylolysis, it is unknown whether DR leads to better outcomes for young patients with spondylolysis than traditional nonsurgical treatment. The purpose of the study was to investigate whether DR was associated with better outcomes for lumbar spondylolysis in young patients than traditional conservative treatment. This is a prospective cohort study. Of 1,784 patients with low back pain in the reference period, 149 young patients with spondylolysis who followed up for at least 1 year were enrolled in the study. The primary outcome was pain intensity at the lower back measured with a Visual Analog Scale. Secondary outcomes included the functional outcome as measured with the Oswestry disability index (ODI) and the 12-item short-form health survey (SF-12) consisting of the physical component summary (PCS) and mental component summary (MCS) scores, the radiologic outcome as measured with lumbar spine radiographs and computed tomography scans, and complications of treatment. This was a prospective comparative study between two groups of patients who were treated with either conservative treatment or surgery for lumbar spondylolysis. Enrolled patients self-selected their own treatment and were allocated to either the traditional care group with conservative treatment (87 patients) or the surgery group (62 patients). All patients were followed up for at least 1 year. Pain intensity at the lower back did not differ significantly between groups at the final follow-up. Likewise, the ODI and SF-12 (PCS and MCS) scores did not differ significantly between groups (p=.13, .71, and .68, respectively). The change in the gap distance of the pars defect at the final follow-up was significantly different between groups (traditional care group: +0.8±0.4 mm; surgery group: -0.7±0.5; p=.01). The union rate at 1 year after surgical treatment was 52% (32/61). The rate of

  8. Genetic Engineering of a Radiation-Resistant Bacterium for Biodegradation of Mixed Wastes. Final Report

    International Nuclear Information System (INIS)

    Lidstrom, Mary E.

    2003-01-01

    Aqueous mixed low level wastes (MLLW) containing radionuclides, solvents, and/or heavy metals represent a serious current and future problem for DOE environmental management and cleanup. In order to provide low-cost treatment alternatives under mild conditions for such contained wastes, we have proposed to use the radiation-resistant bacterium, Deinococcus radiodurans. This project has focused on developing D. radiodurans strains for dual purpose processes: cometabolic treatment of haloorganics and other solvents and removal of heavy metals from waste streams in an above-ground reactor system. The characteristics of effective treatment strains that must be attained are: (a) high biodegradative and metal binding activity; (b) stable treatment characteristics in the absence of selection and in the presence of physiological stress; (c) survival and activity under harsh chemical conditions, including radiation. The result of this project has been a suite of strains with high biodegradative capabilities that are candidates for pilot stage treatment systems. In addition, we have determined how to create conditions to precipitate heavy metals on the surface of the bacterium, as the first step towards creating dual-use treatment strains for contained mixed wastes of importance to the DOE. Finally, we have analyzed stress response in this bacterium, to create the foundation for developing treatment processes that maximize degradation while optimizing survival under high stress conditions

  9. Integrated process analysis of treatment systems for mixed low level waste

    International Nuclear Information System (INIS)

    Cooley, C.R.; Schwinkendorf, W.E.; Bechtold, T.E.

    1997-10-01

    Selection of technologies to be developed for treatment of DOE's mixed low level waste (MLLW) requires knowledge and understanding of the expected costs, schedules, risks, performance, and reliability of the total engineered systems that use these technologies. Thus, an integrated process analysis program was undertaken to identify the characteristics and needs of several thermal and nonthermal systems. For purposes of comparison, all systems were conceptually designed for a single facility processing the same amount of waste at the same rate. Thirty treatment systems were evaluated ranging from standard incineration to innovative thermal systems and innovative nonthermal chemical treatment. Treating 236 million pounds of waste in 20 years through a central treatment was found to be the least costly option with total life cycle cost ranging from $2.1 billion for a metal melting system to $3.9 billion for a nonthermal acid digestion system. Little cost difference exists among nonthermal systems or among thermal systems. Significant cost savings could be achieved by working towards maximum on line treatment time per year; vitrifying the final waste residue; decreasing front end characterization segregation and sizing requirements; using contaminated soil as the vitrifying agent; and delisting the final vitrified waste form from Resource Conservation and Recovery Act (RCRA) Land Disposal Restriction (LDR) requirements

  10. Characteristics of biosolids from sludge treatment wetlands for agricultural reuse

    DEFF Research Database (Denmark)

    Uggetti, Enrica; Ferrer, Ivet; Nielsen, Steen

    2012-01-01

    Sludge treatment wetlands (STW) consist of constructed wetlands systems specifically developed for sludge treatment over the last decades. Sludge dewatering and stabilisation are the main features of this technology, leading to a final product which may be recycled as an organic fertiliser or soi...... legal limits for land application of the sludge. Our results suggest that biosolids from the studied STW can be valorised in agriculture, especially as soil conditioner....

  11. Treatment of complicated grief

    Directory of Open Access Journals (Sweden)

    Rita Rosner

    2011-11-01

    Full Text Available Following the death of a loved one, a small group of grievers develop an abnormal grieving style, termed complicated or prolonged grief. In the effort to establish complicated grief as a disorder in DSM and ICD, several attempts have been made over the past two decades to establish symptom criteria for this form of grieving. Complicated grief is different from depression and PTSD yet often comorbid with other psychological disorders. Meta-analyses of grief interventions show small to medium effect sizes, with only few studies yielding large effect sizes. In this article, an integrative cognitive behavioral treatment manual for complicated grief disorder (CG-CBT of 25 individual sessions is described. Three treatment phases, each entailing several treatment strategies, allow patients to stabilize, explore, and confront the most painful aspects of the loss, and finally to integrate and transform their grief. Core aspects are cognitive restructuring and confrontation. Special attention is given to practical exercises. This article includes the case report of a woman whose daughter committed suicide.

  12. Waste treatment and immobilization technologies involving inorganic sorbents. Final report of a co-ordinated research programme 1992-1996

    International Nuclear Information System (INIS)

    1997-06-01

    A Coordinated Research Programme (CRP) for the application of inorganic sorbents in liquid waste treatment and immobilization was initiated by the IAEA in 1992. The results of this CRP are presented in this report. Fifteen institutions from fourteen countries were involved in this programme. The framework of this CRP was: (1) to conduct fundamental studies on sorbent structure and sorption mechanism; (2) to obtain thermodynamic and kinetic data of the treatment process; (3) to define sorption mechanism of radionuclides on different soils; (4) to identify sorbents appropriate for treatment of liquid waste streams; (5) to develop standard tests to be able to compare results of different groups of investigations. Refs, figs, tabs

  13. The use of slightly alloyed uranium as fuel: its influence on the dissolution and other stages of treatment

    International Nuclear Information System (INIS)

    Faugeras, P.; Leroy, P.; Lheureux, C.

    1959-01-01

    This report deals chiefly with the treatment of binary alloys (UAI, UMo, UZr, UCr, USi) with a low concentration of the additional element (≤2 per cent). The investigation was pursued with a view to the continued utilisation, with a minimum of modification, of the existing plants for treatment of non-alloyed irradiated uranium. In the first part, the usual process for the treatment of irradiated uranium by solvent extraction is briefly recalled. The second part is devoted to a study of the selective dissolution of the canning around certain of these alloys. The third part gives the behaviour of these different alloys at various phases of the usual treatment: a) dissolution; b) extractions; c) final treatment of fission products; d) final purification of plutonium. To conclude, possible alloys are classed as a function of their repercussions on the normal treatment. (author) [fr

  14. Public Discussion about Completion of Mochovce Units 3 and 4

    International Nuclear Information System (INIS)

    Anon

    2014-01-01

    After the introduction of the Nuclear Regulatory Authority (NRA) reopened NRA, the participants familiarised themselves with the history of M.I.5 (1980-2008), with the decisions of the NRA issued in 2008, with the law-suit and the judgement of the Supreme Court of the Slovak Republic, with the course of the procedure after the judgement, and with the comments, proposals and suggestions of the procedure participants delivered to the Authority within the specified period. The public hearing of the comments was followed by technical comments of the procedure participants focused on events at one unit that can affect the neighbouring unit, containment concept, seismic threat and accidents with fuel melting, which were fully answered by the competent persons. The hearing ended with a discussion.

  15. Septage unit treatment by sludge treatment reed beds for easy management and reuse: performance and design considerations.

    Science.gov (United States)

    Kim, Boram; Bel, Thomas; Bourdoncle, Pascal; Dimare, Jocelyne; Troesch, Stéphane; Molle, Pascal

    2018-01-01

    Sustainable treatment and management of fecal sludge in rural areas require adapted solutions. Rustic and simple operating processes such as sludge treatment reed beds (STRB) have been increasingly considered for this purpose. The biggest full scale (2,600 m 2 of STRB) septage treatment unit in France had been built in Nègrepelisse with the final objectives of reusing treated sludge and leachates for agriculture spreading and tree irrigation, respectively. The aim of this investigation was to validate the treatment chain of this installation. The obtained field data showed firstly that the overall removal efficiencies of STRB were satisfactory and stable. Removal rates higher than 98% for chemical oxygen demand and suspended solids and a 95% for Kjeldahl nitrogen represented so far a beneficial septage treatment by STRB. The highlighted necessity of a suitable complementary leachate treatment (before tree irrigation) justified the presence of the second stage of vertical flow constructed wetland. The sludge deposit drying and mineralization efficiencies were on the right track. According to hydrotextural diagram analysis, surface deposit was however found to have high deformability probably due to the youth of the installation. An in-depth understanding of STRB system needs continuous long-term studies.

  16. Intense pulsed light vs. long-pulsed dye laser treatment of telangiectasia after radiotherapy for breast cancer: a randomized split-lesion trial of two different treatments

    DEFF Research Database (Denmark)

    Nymann, P.; Hedelund, L.; Hædersdal, Merete

    2009-01-01

    Background Chronic radiodermatitis is a common sequela of treatment for breast cancer and potentially a psychologically distressing factor for the affected women. Objectives To evaluate the efficacy and adverse effects of treatments with a long-pulsed dye laser (LPDL) vs. intense pulsed light (IPL......); the interventions were randomly assigned to left/right or upper/lower halves. Primary end-points were reduction in telangiectasia, patient satisfaction and preferred treatment. Secondary end-points were pain and adverse effects. Efficacy was registered by blinded photographic evaluations 3 months after the final...

  17. Application of graphene oxide in water treatment

    Science.gov (United States)

    Liu, Yongchen

    2017-11-01

    Graphene oxide has good hydrophilicity and has been tried to use it into thin films for water treatment in recent years. In this paper, the preparation methods of graphene oxide membrane are reviewed, including vacuum suction filtration, spray coating, spin coating, dip coating and the layer by layer method. Secondly, the mechanism of mass transfer of graphene membrane is introduced in detail. The application of the graphene oxide membrane, modified graphene oxide membrane and graphene hybrid membranes were discussed in RO, vaporization, nanofiltration and other aspects. Finally, the development and application of graphene membrane in water treatment were discussed.

  18. A process for treatment of residues from dry/semidry APC systems at municipal solid waste incinerators. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Hjelmar, O. [VKI, Hoersholm (Denmark)] Holland, D. [FLS miljoe a/s, Valby (Denmark)] Poulsen, B. [KARA, Roskilde (Denmark)

    1997-08-01

    The main objective of the project has been to establish and test a process for treatment of residues from the semidry (and dry) lime injection based APC processes at MSWIs, which will ensure that the residues can be managed in an environmentally safe manner. In pursuit of this goal, the following activities have been carried out: Performance of pilot scale extractions (approximately 50 kg of residue per batch) at the KARA MSWI in Roskilde of semidry APC system residues in order to establish and optimize process conditions. The optimization includes consideration of the possibilities for subsequent treatment/stabilization of the extracted solid phase as well as the possibility of treatment and safe discharge/utilization of the extract; Performance of chemical characterization, hydrogeochemical model calculations and experimental work in order to improve the understanding of the mechanisms and factors which for several contaminants control the equilibrium between the solid and liquid phases, both in the short and the long germ, and to use this information to obtain an environmentally acceptable method for stabilization/treatment of the extracted residues while at the same time minimizing the necessary amount of additives; production of treated residues and performance of leaching tests on these to assess and demonstrate the effectiveness of the entire process (extraction + stabilization/treatment); Evaluation of the technical, economical and environmental consequences of full scale implementation of the process. (EG) EFP-94. 19 refs.

  19. Behavior of natural radionuclides in wastewater treatment plants

    International Nuclear Information System (INIS)

    Camacho, A.; Montaña, M.; Vallés, I.; Devesa, R.; Céspedes-Sánchez, R.; Serrano, I.; Blázquez, S.; Barjola, V.

    2012-01-01

    56 samples, including influent, primary effluent, secondary effluent and final effluent wastewater from two Spanish municipal wastewater treatment plants (WWTPs), were analyzed to assess both the occurrence and behavior of natural radioactivity during 12 sampling campaigns carried out over the period 2007–2010. Influent and final effluent wastewaters were sampled by taking into account the hydraulic residence time within the WWTP. A wide range of gross alpha activities (15–129 mBq/L) and gross beta activities (477–983 mBq/L) in liquid samples were obtained. A correlation analysis between radioactivity in liquid samples and the performance characteristics of the WWTPs was performed. The results in liquid samples showed that gross beta activities were not influenced by treatment in the studied WWTPs. However, gross alpha activities behave differently and an increase was detected in the effluent values compared with influent wastewater. This behavior was due to the increase in the total dissolved uranium produced during secondary treatment. The results indicate that the radiological characteristics of the effluents do not present a significant radiological risk and make them suitable for future applications. - Highlights: ► Liquids from WWTPs were analyzed to know the behavior of natural radionuclides. ► Gross beta activities were not influenced by treatment in the studied WWTPs. ► Increase in gross alpha activity was observed due to uranium desorption/solubilisation. ► Correlation between gross alpha activity and the chemical oxygen demand was found

  20. Efficacy of Combined Treatment with Acupuncture and Bee Venom Acupuncture as an Adjunctive Treatment for Parkinson's Disease.

    Science.gov (United States)

    Cho, Seung-Yeon; Lee, Young-Eun; Doo, Kyeong-Hee; Lee, Ji-Hyun; Jung, Woo-Sang; Moon, Sang-Kwan; Park, Jung-Mi; Ko, Chang-Nam; Kim, Ho; Rhee, Hak Young; Park, Hi-Joon; Park, Seong-Uk

    2018-01-01

    The aim of this study was to evaluate the efficacy of acupuncture and bee venom acupuncture (BVA) for idiopathic Parkinson's disease (IPD) through a sham-controlled trial. We also investigated whether there is a sustained therapeutic effect by completing follow-up assessments after treatment completion. A single center, double-blind, three-armed randomized controlled trial. This study was performed at a university hospital in Seoul, Republic of Korea. Seventy-three (73) patients with IPD were the subjects. They were randomly assigned to the active treatment group, sham treatment group, or conventional treatment group. The active treatment group received acupuncture and BVA and the sham group received sham acupuncture and normal saline injections, twice a week for 12 weeks. The conventional treatment group maintained anti-parkinsonian drugs without additional intervention. The Unified Parkinson's Disease Rating Scale (UPDRS) part II and part III score, postural instability and gait disturbance (PIGD) score, gait speed and number, Parkinson's Disease Quality of Life Questionnaire, Beck Depression Inventory, and postural stability at baseline and at 12, 16, and 20 weeks. Sixty-three (63) patients provided a complete data of assessments, including a final follow-up. After 12 weeks of treatment, a significant difference was observed between the active treatment group and the conventional treatment group. After the end of the treatment, the treatment effects were maintained significantly in the active treatment group only. It is suggested that the combined treatment of acupuncture and BVA might be safe and useful adjunctive treatment for patients with IPD.

  1. Final Focus Systems in Linear Colliders

    International Nuclear Information System (INIS)

    Raubenheimer, Tor

    1998-01-01

    In colliding beam facilities, the ''final focus system'' must demagnify the beams to attain the very small spot sizes required at the interaction points. The first final focus system with local chromatic correction was developed for the Stanford Linear Collider where very large demagnifications were desired. This same conceptual design has been adopted by all the future linear collider designs as well as the SuperConducting Supercollider, the Stanford and KEK B-Factories, and the proposed Muon Collider. In this paper, the over-all layout, physics constraints, and optimization techniques relevant to the design of final focus systems for high-energy electron-positron linear colliders are reviewed. Finally, advanced concepts to avoid some of the limitations of these systems are discussed

  2. Effect of an Intermediate Heat-treatment on a Change of the Corrosion Resistance and Hardness of a HANA-4 Outer Strip

    International Nuclear Information System (INIS)

    Lee, Myung Ho; Jung, Yang Il; Park, Sang Yoon; Choi, Byoung Kwon; Park, Jeong Yong; Jeong, Yong Hwan; Eom, Kyong Bo; Park, Nam Gyu; Lim, Yoon Soo

    2008-01-01

    KAERI (Korea Atomic Energy Research Institute) in collaboration with KNF (Korea Nuclear Fuel) undertook some researches on the applicability of HANA-4 and HANA-6 alloys for the spacer grid for a PWR (Pressurized Water Reactor) nuclear fuel. As a part of the research, KAERI studied the effect of the final heat-treatment on the mechanical and corrosion properties of a HANA-4 inner strip. The strip was manufactured with a sheet which had been intermediately heat-treated at about 580 .deg. C for 2.5-4 hours after each cold rolling before being processed into the final strip product. It was mentioned that the process with the intermediate heat treatment needed reviewing to establish an improved manufacturing process for the cold rolling. So, this work tried to check the effect of an intermediate heat-treatment on the properties of a HANA-4 strip using a specimen that was taken from a second hot rolled material before a cold-rolling. The manufacturing processes, with three different kinds of annealings, were introduced to investigate the applicable intermediate heat-treatment process. After all the cold-rolling processes, the Vickers hardness was measured for the final annealed specimens and 60 days of corrosion tests were carried out to check on the effect of the intermediate heat-treatment. Finally, an appropriate intermediate heat-treatment was proposed to improve the manufacturability of the HANA-4 strip

  3. Improved final predicted height with the injection of leuprolide in children with earlier puberty: A retrospective cohort study.

    Directory of Open Access Journals (Sweden)

    Yi-Chun Lin

    Full Text Available The adult height of children with early onset puberty is limited by the premature maturation of hypothalamic-pituitary-gonadal axis. To evaluate the effects of gonadotropin-releasing hormone analog (GnRHa treatment on the final height (FH and bone maturation rate (BMR in girls with early puberty (EP or idiopathic central precocious puberty (ICPP, we examined data from girls who were diagnosed with EP or ICPP and underwent GnRHa (Leuplin Depot: 3.75 mg/month at China Medical University Hospital, in Taiwan, between 2006 and 2015. Patients were observed until the achievement of FH and divided into an "EP group" (T-ep and "ICPP group" (T-icpp according to the age of onset of puberty. Eighty-seven patients were enrolled (T-ep, N = 44, puberty onset at 8-10 years; T-icpp, N = 43, puberty onset before 8 years. The demographic data of girls with EP or IPP was characterized. BMR, change in predicted final height (PFH after GnRHa treatment, target height (TH and FH were measured. After GnRHa treatment, the study groups (T-ep: 160.24±6.18 cm, T-icpp: 158.99±5.92 cm both had higher PFH than at initiation (T-ep: 159.83±7.19 cm, T-icpp: 158.58±5.93 cm. There was deceleration of BMR in both groups (T-ep: 0.57±0.39; T-icpp: 0.97±0.97 and a significant difference between the groups (p = 0.027. The gap in FH standard deviation scores (SDS and TH SDS had a significant difference in T-ep (p = 0.045 but not in T-icpp. Moreover, there was no difference in the gap of PFH SDS between the 1st and final treatment in both groups. We concluded that GnRHa decelerated BMR in girls with earlier puberty. Further prospective clinical studies are warranted.

  4. Solidification of radioactive liquid wastes, Treatment options for spent resins and concentrates - 16405

    International Nuclear Information System (INIS)

    Roth, Andreas

    2009-01-01

    Ion exchange is one of the most common and effective treatment methods for liquid radioactive waste. However, spent ion exchange resins are considered to be problematic waste that in many cases require special approaches and pre-conditioning during its immobilization to meet the acceptance criteria for disposal. Because of the function that they fulfill, spent ion exchange resins often contain high concentrations of radioactivity and pose special handling and treatment problems. Another very common method of liquid radioactive waste treatment and water cleaning is the evaporation or diaphragm filtration. Both treatment options offer a high volume reduction of the total volume of liquids treated but generate concentrates which contain high concentrations of radioactivity. Both mentioned waste streams, spent resins as well as concentrates, resulting from first step liquid radioactive waste treatment systems have to be conditioned in a suitable manner to achieve stable waste products for final disposal. Spent resin and concentrate treatment often appear as a specific task in decommissioning projects, because in the past those waste streams typically had been stored in tanks for the lifetime of the plant and needs to be retrieved, conditioned and packed prior to dismantling activities. Additionally a large amount of contaminated liquids will be generated by utilizing decontamination processes and needs to be processed further on. Such treatment options need to achieve waste products acceptable for final disposal, because due to the closure of the site no interim storage can be envisaged. The most common method of treatment of such waste streams is the solidification in a solid matrix with additional inactive material like cement, polymer etc. In the past good results have been achieved and the high concentration of radioactivity can be reduced by adding the inactive material. On the other hand, under the environment of limited space for interim storage and the absence

  5. Improvement of biodegradability of industrial wastewaters by radiation treatment

    International Nuclear Information System (INIS)

    Jo, H.J.; Kim, H.J.; Kim, J.G.; Jung, J.; Choi, J.S.; Park, Y.K.

    2006-01-01

    In order to evaluate the use of gamma-ray treatment as a pretreatment to conventional biological methods, the effects of gamma-irradiation on biodegradability (BOD 5 /COD) of textile and pulp wastewaters were investigated. For all wastewaters studied in this work, the efficiency of treatment based on TOC removal was insignificant even at an absorbed dose of 20 kGy. However, the change of biodegradability was noticeable and largely dependent on the chemical property of wastewaters and the absorbed dose of gamma-rays. For textile wastewaters, gamma-ray treatment increased the biodegradability of desizing effluent due to degradation of polymeric sizing agents such as polyvinyl alcohol. Interestingly, the weight-loss showed the highest value of 0.97 at a relatively low dose of 1 kGy. This may be caused by the degradation of less biodegradable ethylene glycol prior to terephthalic acid decomposition. For pulp wastewater, the gamma-ray treatment did not improve the biodegradability of cooking and bleaching of C/D effluents. However, the biodegradability of bleaching E1 and final effluents was abruptly increased up to 5 kGy then slowly decreased as the absorbed dose was increased. The initial increase of biodegradability may be induced by the decomposition of refractory organic compounds such as chlorophenols, which are known to be the main components of bleaching C/D and final effluents. (author)

  6. Developing strategies for thermal treatment technology R and D in MIREC

    International Nuclear Information System (INIS)

    Muhd Noor Muhd Yunus

    2004-01-01

    The degree of the solid waste management problem in Malaysia is very crucial, needing immediate solutions. The estimated amount of MSW generated is 16,000 ton/day with the initial cost of the entire activity is estimated to worth RM35 billions. However, Malaysia is still negotiating for the best strategies to manage her MSW in the best manner - politically, economically and environmentally. A National Solid Waste Strategic Plan has been established, advocating and adopting the Integrated Solid Waste Management System (IWMS). However, choosing the right mix of the waste management hierarchy is not simple. The 3-R concept with an effective and consistent role by the society at large is still not well taken up despite of various efforts taken by the government. The role of biological treatment such as composting and bio-gasification (AD), is slowly gaining momentum, however, needed much more effort and understanding when applied to local waste and market conditions. The vigor to introduce the-state-of-the-art thermal treatment process has been done as early as in 2000, but the project has faced a severe set back with regard to public acceptance, lingering around the dioxin issues, and the resulting political consequences caused delays in implementation. Finally, there seems to be a more practical and sensible solution nationally to build more Sanitary Landfills (SLF) in various states and municipalities due to economic reasons as well as for final disposal of waste. It is therefore seen that the Mechanical / 3 -R and Biological Treatment (MBT) methods play a better role as a pretreatment process prior to landfills, environmentally speaking. In case the economics does not permit the above practice, direct land filling of the MSW should entails with the Land Fill Gas (LFG) extraction and utilization. Despite of the general trends to import foreign technologies to circumvent the unavailability of local solutions, the needs for local input cannot be denied. Hence, the R

  7. Expanded studies of linear collider final focus systems at the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Tenenbaum, P.G.

    1995-12-01

    In order to meet their luminosity goals, linear colliders operating in the center-of-mass energy range from 3,50 to 1,500 GeV will need to deliver beams which are as small as a few Manometers tall, with x:y aspect ratios as large as 100. The Final Focus Test Beam (FFTB) is a prototype for the final focus demanded by these colliders: its purpose is to provide demagnification equivalent to those in the future linear collider, which corresponds to a focused spot size in the FFTB of 1.7 microns (horizontal) by 60 manometers (vertical). In order to achieve the desired spot sizes, the FFTB beam optics must be tuned to eliminate aberrations and other errors, and to ensure that the optics conform to the desired final conditions and the measured initial conditions of the beam. Using a combination of incoming-beam diagnostics. beam-based local diagnostics, and global tuning algorithms, the FFTB beam size has been reduced to a stable final size of 1.7 microns by 70 manometers. In addition, the chromatic properties of the FFTB have been studied using two techniques and found to be acceptable. Descriptions of the hardware and techniques used in these studies are presented, along with results and suggestions for future research

  8. Expanded studies of linear collider final focus systems at the Final Focus Test Beam

    Energy Technology Data Exchange (ETDEWEB)

    Tenenbaum, Peter Gregory [Stanford Univ., CA (United States)

    1995-12-01

    In order to meet their luminosity goals, linear colliders operating in the center-of-mass energy range from 3,50 to 1,500 GeV will need to deliver beams which are as small as a few Manometers tall, with x:y aspect ratios as large as 100. The Final Focus Test Beam (FFTB) is a prototype for the final focus demanded by these colliders: its purpose is to provide demagnification equivalent to those in the future linear collider, which corresponds to a focused spot size in the FFTB of 1.7 microns (horizontal) by 60 manometers (vertical). In order to achieve the desired spot sizes, the FFTB beam optics must be tuned to eliminate aberrations and other errors, and to ensure that the optics conform to the desired final conditions and the measured initial conditions of the beam. Using a combination of incoming-beam diagnostics. beam-based local diagnostics, and global tuning algorithms, the FFTB beam size has been reduced to a stable final size of 1.7 microns by 70 manometers. In addition, the chromatic properties of the FFTB have been studied using two techniques and found to be acceptable. Descriptions of the hardware and techniques used in these studies are presented, along with results and suggestions for future research.

  9. Brief strategic family therapy for young people in treatment for drug use

    DEFF Research Database (Denmark)

    Lindstrøm, Maia; Filges, Trine; Jørgensen, Anne-Marie Klint

    2015-01-01

    This review evaluates the evidence on the effects of brief strategic family therapy (BSFT) on drug use reduction for young people in treatment for nonopioid drug use. Method: We followed Campbell Collaboration guidelines to prepare this review and ultimately located three studies for final analysis...... and interpretation. Results: The results are mixed: BSFT does not seem to have better or worse effects on drug use frequency and family functioning than other treatments but has positive effects on treatment retention compared to control conditions. Longer retention in treatment has been identified as a consistent...

  10. Final focus nomenclature

    International Nuclear Information System (INIS)

    Erickson, R.

    1986-01-01

    The formal names and common names for all devices in the final focus system of the SLC are listed. The formal names consist of a device type designator, microprocessor designator, and a four-digit unit number

  11. INNOVATIVE FOSSIL FUEL FIRED VITRIFICATION TECHNOLOGY FOR SOIL REMEDIATION. FINAL REPORT

    International Nuclear Information System (INIS)

    J. Hnat; L.M. Bartone; M. Pineda

    2001-01-01

    This Final Report summarizes the progress of Phases 3,3A and 4 of a waste technology Demonstration Project sponsored under a DOE Environmental Management Research and Development Program and administered by the U.S. Department of Energy National Energy Technology Laboratory-Morgantown (DOE-NETL) for an ''Innovative Fossil Fuel Fired Vitrification Technology for Soil Remediation''. The Summary Reports for Phases 1 and 2 of the Program were previously submitted to DOE. The total scope of Phase 3 was to have included the design, construction and demonstration of Vortec's integrated waste pretreatment and vitrification process for the treatment of low level waste (LLW), TSCA/LLW and mixed low-level waste (MLLW). Due to funding limitations and delays in the project resulting from a law suit filed by an environmental activist and the extended time for DOE to complete an Environmental Assessment for the project, the scope of the project was reduced to completing the design, construction and testing of the front end of the process which consists of the Material Handling and Waste Conditioning (MH/C) Subsystem of the vitrification plant. Activities completed under Phases 3A and 4 addressed completion of the engineering, design and documentation of the MH/C System such that final procurement of the remaining process assemblies can be completed and construction of a Limited Demonstration Project be initiated in the event DOE elects to proceed with the construction and demonstration testing of the MH/C Subsystem. Because of USEPA policies and regulations that do not require treatment of low level or low-level/PCB contaminated wastes, DOE terminated the project because there is no purported need for this technology

  12. FameLab - Swiss Semi Finals

    CERN Multimedia

    Corinne Pralavorio

    2012-01-01

    Twenty-two young scientists participated in the FameLab semi-final at CERN's Globe of Science and Innovation on 4 February, supported by a large audience and by more than 100 fans following via webcast. A panel of judges chose Lemmer and four other candidates to join five other semi-finalists at the national finals in Zurich on 30 March.

  13. Catarse e Final Feliz

    Directory of Open Access Journals (Sweden)

    Myriam Ávila

    2001-12-01

    Full Text Available Resumo: É a certeza de que nada mais – ou nada importante – pode acontecer após o final de um conto que permite o acontecimento da catarse. Se na maioria das narrativas existe algum tipo de dénouement, em algumas delas isso acontece de maneira especialmente satisfatória e afirmativa. O conto de fadas é uma dessas formas narrativas onde o efeito catártico é extremo e preenche objetivos específicos, de acordo com Bruno Bettelheim. Hollywood mimetizou essa forma como estratégia de sedução, iniciando a tradição do final feliz no cinema. A partir do conto de fadas Cinderela, em diferentes versões, juntamente com a animação homônima da Disney e ainda duas versões do filme Sabrina, será traçada aqui uma relação entre a catarse e o final feliz nos contos de fada, bem como seu uso pela indústria cultural. Palavras-chave: catarse, contos de fada, Hollywood

  14. Design parameters for waste effluent treatment unit from beverages production

    Directory of Open Access Journals (Sweden)

    Mona A. Abdel-Fatah

    2017-09-01

    Full Text Available Based on a successful experimental result from laboratory and bench scale for treatment of wastewater from beverages industry, an industrial and efficient treatment unit is designed and constructed. The broad goal of this study was to design and construct effluent, cost effective and high quality treatment unit. The used technology is the activated sludge process of extended aeration type followed by rapid sand filters and chlorination as tertiary treatment. Experimental results have been considered as the basis for full scale design of the industrial capacity of 1600 m3/day treatment plant. Final effluent characteristics after treatment comply with Egyptian legalizations after reducing COD and BOD5 by about 97% and 95% respectively. So it is recommended to reuse treated effluent in textile industry in dyeing process.

  15. COMPARISON OF ESCHERICHIA COLI, TOTAL COLIFORM, AND FECAL COLIFORM POPULATIONS AS INDICATORS OF WASTEWATER TREATMENT EFFICIENCY

    Science.gov (United States)

    Escherichia coli, total coliform, and fecal coliform data were collected from two wastewater treatment facilities, a subsurface constructed wetlands, and the receiving stream. Results are presented from individual wastewater treatment process streams, final effluent and river sit...

  16. Treatment of Medial Tibial Stress Syndrome With Radial Soundwave Therapy in Elite Athletes: Current Evidence, Report on Two Cases, and Proposed Treatment Regimen.

    Science.gov (United States)

    Saxena, Amol; Fullem, Brian; Gerdesmeyer, Ludger

    Two case reports of high-level athletes with medial tibial stress syndrome (MTSS), 1 an Olympian with an actual stress fracture, are presented. Successful treatment included radial soundwave therapy, pneumatic leg braces, relative rest using an antigravity treadmill, and temporary foot orthoses. Radial soundwave therapy has a high level of evidence for treatment of MTSS. We also present recent evidence of the value of vitamin D assessment. Both patients had a successful outcome with minimal downtime. Finally, a suggested treatment regimen for MTSS is presented. Copyright © 2017 American College of Foot and Ankle Surgeons. Published by Elsevier Inc. All rights reserved.

  17. Nuclear safety in Slovak Republic. Safety analysis reports for WWER 440 reactors

    International Nuclear Information System (INIS)

    Rohar, S.

    1999-01-01

    Implementation of nuclear power program is connected to establishment of regulatory body for safe regulation of siting, construction, operation and decommissioning of nuclear installations. Licensing being one of the most important regulatory surveillance activity is based on independent regulatory review and assessment of information on nuclear safety for particular nuclear facility. Documents required to be submitted to the regulatory body by the licensee in Slovakia for the review and assessment usually named Safety Analysis Report (SAR) are presented in detail in this paper. Current status of Safety Analysis Reports for Bohunice V-1, Bohunice V-2 and Mochovce NPP is shown

  18. 3. General principles of assessing seismic resistance of technological equipment of nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

    The evaluation of the seismic resistance of technological equipment is performed by computation, experimental trial, possibly by combining both methods. Existing and prepared standards in the field of seismic resistance of nuclear power plants are mentioned. Accelerograms and response spectra of design-basis earhtquake and maximum credible earthquake serve as the basic data for evaluating seismic resistance. The nuclear power plant in Mochovce will be the first Czechoslovak nuclear power plant with so-called partially seismic design. The problem of dynamic interaction of technological equipment and nuclear power plant systems with a bearing structure is discussed. (E.F.)

  19. Construction history and construction management

    International Nuclear Information System (INIS)

    Agh, S.

    1999-01-01

    The process of pre-design and design preparation of the Mochovce NPP as well as the construction history of the plant is highlighted, including the financing aspect and problems arising from changes in the technological and other conditions of start-up of the reactor units. The results of international audits performed to improve the level of nuclear safety and implementation of the measures suggested are also described. The milestones of the whole construction process and start-up process, the control and quality system, and the methods of control and management of the complex construction project are outlined. (author)

  20. Slovenske elektrarne has fulfilled the plan of electric power production at 101 %

    International Nuclear Information System (INIS)

    Anon

    2004-01-01

    Slovenske elektrarne, a. s., produced in 2003 year the electric power in capacity 26,047.6 GWh, whereby they fulfilled business plan at 101 %. In compare with the last year it is a reduction in production by 1,397.3 GWh. The biggest share of production - till 68.6 % of overall production of the Slovenske elektrarne, was provided by nuclear sources. Nuclear power plants fulfilled business plan at 104 %, when Jaslovske Bohunice NPP has produced 11,625 GWh and Mochovce NPP 6,238 GWh. The share of other power plants on the electricity production is presented

  1. Internal flooding analyses results of Slovak NPPs

    International Nuclear Information System (INIS)

    Sopira, Vladimir

    2000-01-01

    The assessment of the flood risk was the objective of the internal flooding analysis for NPPs Bohunice V1, V2 and Mochovce. All important flooding sources were identified. The rooms containing safety important components were analyzed from the point of view of: Integrity of flood boundaries; Capability for drainage; Flood signalisation; Flood localization and liquidation; Vulnerability of safety system component. The redundancies of safety systems are located mostly separately and no flood can endanger more than single train. It can be concluded that NPPs with WWER-440 are very safe against the flooding initiating event

  2. Containment leak-tightness enhancement at VVER 440 NPPs

    International Nuclear Information System (INIS)

    Prandorfy, M.

    2001-01-01

    The hermetic compartments of VVER 440 NPPs fulfil the function of the containment used at NPPs all over the word. The purpose of the containment is to protect the NPP personal against radioactive impact as well as to prevent radioactive leakage to the environment during a lost of coolant accident. Leak-tightness enhancement in NPPs with VVER 440/213 and VVER 440/230 reactors is an important safety issue. New procedures, measures and methods were adopted at NPPs in Mochovce, J. Bohunice, Dukovany and Paks for leak identification and sealing works performed by VUEZ Levice. (authors)

  3. Containment leak-tightness enhancement at VVER 440 NPPs

    International Nuclear Information System (INIS)

    Prandorfy, M.

    2000-01-01

    The hermetic compartments of WWER 440 NPPs fulfil the function of the containment used at NPPs all over the world. The purpose of the containment is to protect the NPP personnel against radioactive impact as well as to prevent radioactive leakage to the. environ ent during a lost of coolant accident. Leak-tightness enhancement in NPPs with WWER 440/213 and WWER 440/230 reactors is an important safety issue. New procedures, measures and methods were adopted at NPPs in Mochovce, Jaslovske Bohunice, Dukovany and PAKS for leak identification and sealing works performed by VUEZ Levice. (authors)

  4. Rapid separation and determination of 107Pd in radioactive waste produced during NPP A-1 decommissioning

    International Nuclear Information System (INIS)

    Boris Andris; Miroslav Prazsky; Ferdinand Sebesta

    2015-01-01

    Procedure for 107 Pd determination in radioactive wastes coming from decommissioning of NPP A-1 is proposed and verified. 107 Pd was separated and purified by Pd precipitation with dimethylglyoxime (DMG) and/or ferric hydroxide precipitation. 107 Pd yield was determined gravimetrically by weighing the Pd(DMG) 2 precipitate. 107 Pd counting was performed using liquid scintillation counter (LSC-TDCR) and scintillation cocktail Hionic Fluor. In all analyzed samples the determined activities of 107 Pd were lower than MDA. Nevertheless such analyses permit the decision concerning the storage of solidified wastes in the Mochovce regional repository. (author)

  5. The use of ion exchange chromatography methods for the determination of {sup 93}Zr in the samples of radioactive wastes; Vyuzitie metod ionovymennej chromatografie pre stanovenie {sup 93}Zr vo vzorkach radioaktivnych odpadov

    Energy Technology Data Exchange (ETDEWEB)

    Gardonova, V; Dulanska, S; Remenec, B; Matel, L [Univerzita Komenskeho v Bratislave, Prirodovedecka fakulta, Katedra jadrovej chemie, 84215 Bratislava (Slovakia)

    2012-04-25

    A simple and rapid method of preconcentration, separation and purification of {sup 93}Zr based on the methods of ion exchange chromatography with ion exchangers made by Eichrom Technologies, Inc. was developed. Multi-stage method of {sup 93}Zr separation proved to be suitable for the analysis of samples highly contaminated with radioactive waste in a relatively short time and with a high decontamination factor. The use and effectiveness of the method was successfully tested by analysis of heterogeneous waste from Mochovce nuclear power plant, which belongs to the most complex matrixes of radiochemical analysis. (authors)

  6. Final focus nomenclature

    Energy Technology Data Exchange (ETDEWEB)

    Erickson, R.

    1986-08-08

    The formal names and common names for all devices in the final focus system of the SLC are listed. The formal names consist of a device type designator, microprocessor designator, and a four-digit unit number. (LEW)

  7. 10 CFR 603.890 - Final performance report.

    Science.gov (United States)

    2010-01-01

    ... to Other Administrative Matters Financial and Programmatic Reporting § 603.890 Final performance report. A TIA must require a final performance report that addresses all major accomplishments under the... 10 Energy 4 2010-01-01 2010-01-01 false Final performance report. 603.890 Section 603.890 Energy...

  8. Usefulness of Arthroscopic Treatment of Painful Hip after Acetabular Fracture or Hip Dislocation.

    Science.gov (United States)

    Hwang, Jung-Taek; Lee, Woo-Yong; Kang, Chan; Hwang, Deuk-Soo; Kim, Dong-Yeol; Zheng, Long

    2015-12-01

    Painful hip following hip dislocation or acetabular fracture can be an important signal for early degeneration and progression to osteoarthritis due to intraarticular pathology. However, there is limited literature discussing the use of arthroscopy for the treatment of painful hip. The purpose of this retrospective study was to analyze the effectiveness and benefit of arthroscopic treatment for patients with a painful hip after major trauma. From July 2003 to February 2013, we reviewed 13 patients who underwent arthroscopic treatment after acetabular fracture or hip dislocation and were followed up for a minimum of 2 postoperative years. The degree of osteoarthritis based on the Tonnis classification pre- and postoperatively at final follow-up was determined. Clinical outcomes were evaluated using visual analogue scale for pain (VAS) and modified Harris hip score (MHHS), and range of motion (ROM) of the hip pre- and postoperatively at final follow-up. There were nine male and four female patients with a mean age at surgery of 28 years (range, 20 to 50 years). The mean follow-up period of the patients was 59.8 months (range, 24 to 115 months), and the mean interval between initial trauma and arthroscopic treatment was 40.8 months (range, 1 to 144 months). At the final follow-up, VAS and MHHS improved significantly from 6.3 and 53.4 to 3.0 and 88.3, respectively (p = 0.002 and p hip flexion, abduction, adduction, external rotation, and internal rotation as minor improvements from 113.1°, 38.5°, 28.5°, 36.5°, and 22.7° to 118.5°, 39.0°, 29.2°, 38.9°, and 26.5° were observed, respectively (p = 0.070, p = 0.414, p = 0.317, p = 0.084, and p = 0.136, respectively). None of the patients exhibited progression of osteoarthritis of the hip at the final follow-up. Arthroscopic treatment after acetabular fracture or hip dislocation is effective and delays the progression of traumatic osteoarthritis.

  9. Growth and final height of children with Gaucher disease: A 15-year follow-up at an Israeli Gaucher center.

    Science.gov (United States)

    Mendelsohn, Espen; Meir, Amos; Abrahamov, Aya; Elstein, Deborah; Zimran, Ari; Levy-Khademi, Floris

    2018-02-01

    It is held that enzyme replacement therapy (ERT) accelerates the growth rate in children with Gaucher disease, but its effect on final height has not been established with certainty. This study presents final heights of Gaucher patients followed up for 15years. The study included 41 adults with non-neuronopathic Gaucher disease. The final height of the patients and age at puberty was compared to their mid-parental target height and to their siblings' heights. Mean final height standard deviation score (HSDS) in the patients was -0.22, but none of the patients was abnormally short (HSDS of less than -2.2). Mean age at menarche of the female patients (14.7years) was significantly delayed compared to that of their mothers (P=0.0005), and mean age at first shaving in the boys was 16years. Our study showed that the mean final height of Gaucher patients fell below the mean of the 2000 CDC growth charts, but the patients were not of short stature (height less than the 3rd percentile). ERT treatment did not significantly impact the mean final HSDS. The onset of puberty, as indicated by the age at menarche, was delayed in girls with Gaucher disease. Copyright © 2016 Elsevier Inc. All rights reserved.

  10. Electron beam flue gas treatment process. Review

    International Nuclear Information System (INIS)

    Honkonen, V.A.

    1996-01-01

    The basis of the process for electron beam flue gas treatment are presented in the report. In tabular form the history of the research is reviewed. Main dependences of SO 2 and NO x removal efficiencies on different physico-chemical parameters are discussed. Trends concerning industrial process implementation are presented in the paper,finally. (author). 74 refs, 11 figs, 1 tab

  11. SLC Final Performance and Lessons

    International Nuclear Information System (INIS)

    Phinney, Nan

    2000-01-01

    The Stanford Linear Collider (SLC) was the first prototype of a new type of accelerator, the electron-positron linear collider. Many years of dedicated effort were required to understand the physics of this new technology and to develop the techniques for maximizing performance. Key issues were emittance dilution, stability, final beam optimization and background control. Precision, non-invasive diagnostics were required to measure and monitor the beams throughout the machine. Beam-based feedback systems were needed to stabilize energy, trajectory, intensity and the final beam size at the interaction point. variety of new tuning techniques were developed to correct for residual optical or alignment errors. The final focus system underwent a series of refinements in order to deliver sub-micron size beams. It also took many iterations to understand the sources of backgrounds and develop the methods to control them. The benefit from this accumulated experience was seen in the performance of the SLC during its final run in 1997-98. The luminosity increased by a factor of three to 3*10 30 and the 350,000 Z data sample delivered was nearly double that from all previous runs combined

  12. Total System Performance Assessment Sensitivity Analyses for Final Nuclear Regulatory Commission Regulations

    International Nuclear Information System (INIS)

    Bechtel SAIC Company

    2001-01-01

    This Letter Report presents the results of supplemental evaluations and analyses designed to assess long-term performance of the potential repository at Yucca Mountain. The evaluations were developed in the context of the Nuclear Regulatory Commission (NRC) final public regulation, or rule, 10 CFR Part 63 (66 FR 55732 [DIRS 156671]), which was issued on November 2, 2001. This Letter Report addresses the issues identified in the Department of Energy (DOE) technical direction letter dated October 2, 2001 (Adams 2001 [DIRS 156708]). The main objective of this Letter Report is to evaluate performance of the potential Yucca Mountain repository using assumptions consistent with performance-assessment-related provisions of 10 CFR Part 63. The incorporation of the final Environmental Protection Agency (EPA) standard, 40 CFR Part 197 (66 FR 32074 [DIRS 155216]), and the analysis of the effect of the 40 CFR Part 197 EPA final rule on long-term repository performance are presented in the Total System Performance Assessment--Analyses for Disposal of Commercial and DOE Waste Inventories at Yucca Mountain--Input to Final Environmental Impact Statement and Site Suitability Evaluation (BSC 2001 [DIRS 156460]), referred to hereafter as the FEIS/SSE Letter Report. The Total System Performance Assessment (TSPA) analyses conducted and documented prior to promulgation of the NRC final rule 10 CFR Part 63 (66 FR 55732 [DIRS 156671]), were based on the NRC proposed rule (64 FR 8640 [DIRS 101680]). Slight differences exist between the NRC's proposed and final rules which were not within the scope of the FEIS/SSE Letter Report (BSC 2001 [DIRS 156460]), the Preliminary Site Suitability Evaluation (PSSE) (DOE 2001 [DIRS 155743]), and supporting documents for these reports. These differences include (1) the possible treatment of ''unlikely'' features, events and processes (FEPs) in evaluation of both the groundwater protection standard and the human-intrusion scenario of the individual

  13. Frailty Markers and Treatment Decisions in Patients Seen in Oncogeriatric Clinics: Results from the ASRO Pilot Study.

    Science.gov (United States)

    Farcet, Anaïs; de Decker, Laure; Pauly, Vanessa; Rousseau, Frédérique; Bergman, Howard; Molines, Catherine; Retornaz, Frédérique

    2016-01-01

    Comprehensive Geriatric Assessment (CGA) is the gold standard to help oncologists select the best cancer treatment for their older patients. Some authors have suggested that the concept of frailty could be a more useful approach in this population. We investigated whether frailty markers are associated with treatment recommendations in an oncogeriatric clinic. This prospective study included 70 years and older patients with solid tumors and referred for an oncogeriatric assessment. The CGA included nine domains: autonomy, comorbidities, medication, cognition, nutrition, mood, neurosensory deficits, falls, and social status. Five frailty markers were assessed (nutrition, physical activity, energy, mobility, and strength). Patients were categorized as Frail (three or more frailty markers), pre-frail (one or two frailty markers), or not-frail (no frailty marker). Treatment recommendations were classified into two categories: standard treatment with and without any changes and supportive/palliative care. Multiple logistic regression models were used to analyze factors associated with treatment recommendations. 217 patients, mean age 83 years (± Standard deviation (SD) 5.3), were included. In the univariate analysis, number of frailty markers, grip strength, physical activity, mobility, nutrition, energy, autonomy, depression, Eastern Cooperative Oncology Group Scale of Performance Status (ECOG-PS), and falls were significantly associated with final treatment recommendations. In the multivariate analysis, the number of frailty markers and basic Activities of Daily Living (ADL) were significantly associated with final treatment recommendations (pmarkers are associated with final treatment recommendations in older cancer patients. Longitudinal studies are warranted to better determine their use in a geriatric oncology setting.

  14. Chemical treatment of mixed waste at the FEMP

    International Nuclear Information System (INIS)

    Honigford, L.; Sattler, J.; Dilday, D.; Cook, D.

    1996-01-01

    The Chemical Treatment Project is one in a series of projects implemented by the Fernald Environmental Management Project (FEMP) to treat mixed waste. The projects were initiated to address concerns regarding treatment capacity for mixed waste and to comply with requirements established by the Federal Facility Compliance Act. The Chemical Treatment Project is designed to utilize commercially available mobile technologies to perform treatment at the FEMP site. The waste in the Project consists of a variety of waste types with a wide range of hazards and physical characteristics. The treatment processes to be established for the waste types will be developed by a systematic approach including waste streams evaluation, projectization of the waste streams, and categorization of the stream. This information is utilized to determine the proper train of treatment which will be required to lead the waste to its final destination (i.e., disposal). This approach allows flexibility to manage a wide variety of waste in a cheaper, faster manner than designing a single treatment technology diverse enough to manage all the waste streams

  15. Chapter No.5. Nuclear materials and physical protection of nuclear installations

    International Nuclear Information System (INIS)

    2002-01-01

    The State System of Accounting for and Control of Nuclear Material (SSAC) is based on requirements resulting from the Safeguards Agreement between the Government of the Slovak Republic and the IAEA. UJD performs this activity according to the 'Atomic Act' and relevant decree. The purpose of the SSAC is also to prevent unauthorised use of nuclear materials, to detect loses of nuclear materials and provide information that could lead to the recovery of missing material. The main part of nuclear materials under jurisdiction of the Slovak Republic is located at NPP Jaslovske Bohunice, NPP Mochovce and at interim storage in Jaslovske Bohunice. Even though that there are located more then 99% of nuclear materials in these nuclear facilities, there are not any significant problems with their accountancy and control due to very simply identification of accountancy units - fuel assemblies, and due to stability of legal subjects responsible for operation and for keeping of information continuity, which is necessary for fulfilling requirements of the Agreement. The nuclear material located outside nuclear facilities is a special category. There are 81 such subjects of different types and orientations on the territory of the Slovak Republic. These subjects use mainly depleted uranium as a shielding and small quantity of natural uranium, low enrichment uranium and thorium for experimental purposes and education. Frequent changes of these subjects, their transformations into the other subjects, extinction and very high fluctuation of employees causes loss of information about nuclear materials and creates problems with fulfilling requirements resulting from the Agreement. In 2001, the UJD carried out 51 inspections of nuclear materials, of which 31 inspections were performed at nuclear installations in co-operation with the IAEA inspectors. No discrepancies concerning the management of nuclear materials were found out during inspections and safeguards goals in year 2001 were

  16. Satisfaction with treatment decision-making and treatment regret among Latinas and non-Latina whites with DCIS

    Science.gov (United States)

    López, Mónica E.; Kaplan, Celia P.; Nápoles, Anna M.; Hwang, E. Shelly; Livaudais, Jennifer C.; Karliner, Leah S.

    2013-01-01

    Objective To examine differences in treatment decision-making participation, satisfaction, and regret among Latinas and non-Latina whites with DCIS. Methods Survey of Latina and non-Latina white women diagnosed with DCIS. We assessed women’s preferences for involvement in decision-making, primary treatment decision maker, and participatory decision-making. We examined primary outcomes of satisfaction with treatment decision-making and treatment regret by ethnic-language group. Results Among 745 participants (349 Latinas, 396 white) Spanish-speaking Latinas (SSL) had the highest mean preference for involvement in decision-making score and the lowest mean participatory decision-making score and were more likely to defer their final treatment decision to their physicians than English-speaking Latinas or whites (26%, 13%, 18%, pdecision-making (OR 0.4; CI 95%, 0.2-0.8) and expressed more regret than whites (OR 6.2; CI 95%, 3.0-12.4). More participatory decision-making increased the odds of satisfaction (OR 1.5; CI 95%, 1.3-1.8) and decreased the odds of treatment regret (OR 0.8; CI 95%, 0.7-1.0), independent of ethnicity-language. Conclusion Language barriers impede the establishment of decision-making partnerships between Latinas and their physicians, and result in less satisfaction with the decision-making process and more treatment regret. Practice Implications Use of professional interpreters may address communication-related disparities for these women. PMID:24207116

  17. Biochemical and physical characterisation of urinary nanovesicles following CHAPS treatment.

    Directory of Open Access Journals (Sweden)

    Luca Musante

    Full Text Available Urinary exosomes represent a precious source of potential biomarkers for disease biology. Currently, the methods for vesicle isolation are severely restricted by the tendency of vesicle entrapment, e.g. by the abundant Tamm-Horsfall protein (THP polymers. Treatment by reducing agents such as dithiothreitol (DTT releases entrapped vesicles, thus increasing the final yield. However, this harsh treatment can cause remodelling of all those proteins which feature extra-vesicular domains stabilized by internal disulfide bridges and have detrimental effects on their biological activity. In order to optimize exosomal yield, we explore two vesicle treatment protocols - dithiothreitol (DTT and 3-[(3-cholamidopropyldimethylammonio]-1-propanesulfonic (CHAPS - applied to the differential centrifugation protocol for exosomal vesicle isolation. The results show that CHAPS treatment does not affect vesicle morphology or exosomal marker distribution, thus eliminating most of THP interference. Moreover, the recovery and preservation of catalytic activity of two trans-membrane proteases, dipeptidyl peptidase IV and nephrilysin, was examined and found to be clearly superior after CHAPS treatment compared to DTT. Finally, proteomic profiling by mass spectrometry (MS revealed that 76.2% of proteins recovered by CHAPS are common to those seen for DTT treatment, which illustrates underlining similarities between the two approaches. In conclusion, we provide a major improvement to currently-utilized urinary vesicle isolation strategies to allow recovery of urinary vesicles without the deleterious interference of abundant urinary proteins, while preserving typical protein folding and, consequently, the precious biological activity of urinary proteins which serve as valuable biomarkers.

  18. Effect of different seed treatments on maize seed germination parameters under optimal and suboptimal temperature conditions

    Directory of Open Access Journals (Sweden)

    Vujošević Bojana

    2017-01-01

    Full Text Available The aim of this study was to determine the effect of different seed treatments on germination parameters of three maize genotypes under optimal and suboptimal temperature conditions. Seed was treated with recommended doses of three commercial pesticide formulations: metalaxyl-m 10 g/L + fludioxonil 25 g/L, metalaxyl 20 g/kg + prothioconazole 100 g/kg and thiacloprid 400 g/L. Testing was conducted at 25°C and 15°C. Results of the study indicate that there are differences in response of maize genotypes to applied seed treatments, as well as to a specific treatment at optimal and suboptimal temperatures. Some treatments, depending on the mixing partner and temperature conditions, can affect final germination. In other cases, germination rate can be accelerated or prolonged, but with no effect on final germination. In order to provide fast and uniform emergence under different temperature conditions, further examination of the response of maize genotypes to specific seed treatments would be beneficial.

  19. Cassini's Grand Finale Science Highlights

    Science.gov (United States)

    Spilker, Linda

    2017-10-01

    After 13 years in orbit, the Cassini-Huygens Mission to Saturn ended in a science-rich blaze of glory. Cassini returned its final bits of unique science data on September 15, 2017, as it plunged into Saturn's atmosphere satisfying planetary protection requirements. Cassini's Grand Finale covered a period of roughly five months and ended with the first time exploration of the region between the rings and planet.The final close flyby of Titan in late April 2017 propelled Cassini across Saturn’s main rings and into its Grand Finale orbits; 22 orbits that repeatedly dove between Saturn’s innermost rings and upper atmosphere making Cassini the first spacecraft to explore this region. The last orbit turned the spacecraft into the first Saturn upper atmospheric probe.The Grand Finale orbits provided highest resolution observations of both the rings and Saturn, and in-situ sampling of the ring particle composition, Saturn's atmosphere, plasma, and innermost radiation belts. The gravitational field was measured to unprecedented accuracy, providing information on the interior structure of the planet, winds in the deeper atmosphere, and mass of the rings. The magnetic field provided insight into the physical nature of the magnetic dynamo and structure of the internal magnetic field. The ion and neutral mass spectrometer sampled the upper atmosphere for molecules that escape the atmosphere in addition to molecules originating from the rings. The cosmic dust analyzer directly sampled the composition from different parts of the main rings for the first time. Fields and particles instruments directly measured the plasma environment between the rings and planet.Science highlights and new mysteries gleaned to date from the Grand Finale orbits will be discussed.The research described in this paper was carried out in part at the Jet Propulsion Laboratory, California Institute of Technology, under a contract with the National Aeronautics and Space Administration. Copyright 2017

  20. Predicting outgrowth and inactivation of Clostridium perfringens in meat products during low temperature long time heat treatment

    DEFF Research Database (Denmark)

    Duan, Zhi; Holst Hansen, Terese; Hansen, Tina Beck

    OBJECTIVE Sous-vide cooking and molecular gastronomy has started a wave of experimenting with Low Temperature Long Time (LTLT) heat treatments. Heat treatments, at temperatures as low as 50°C, have been suggested by celebrity chefs. LTLT treatments often take hours to reach to the final core...

  1. Shelf-life and quality evaluation of clementine following a combined treatment with γ-irradiation

    International Nuclear Information System (INIS)

    Mahrouz, M.; Lacroix, M.; D'Aprano, G.; Oufedjikh, H.; Boubekri, C.

    2004-01-01

    In order to enhance the shelf-life of a late variety of Moroccan Citrus clementina (Nour), ionizing treatments were applied at 0.3 kGy, as well as washing (cold water) and waxing treatments. It has been found that, despite the irradiation treatment, the washing and waxing treatment do not improve the quality of C. clementina, but rather result in peel injury. Finally, sensory evaluation confirmed that irradiation had no detrimental effect on the quality of clementines

  2. [Limiting factors in the class III camouflage treatment: a potential protocol].

    Science.gov (United States)

    Chaques Asensi, José

    2016-06-01

    The Class III skeletal malocclusion has been traditionally treated with a combined approach of orthodontics and orthognathic surgery or with a strategy of orthodontic camouflage. Some severe cases can be identified as ideal candidates for a surgical treatment whereas some others can be handled with orthodontics alone, with a reasonable expectation of an acceptable result. However, the problem remains for the borderline patient. In fact, limited information is available in the literature regarding the identification of the factors that can help in establishing the limits for one treatment modality or the other. Furthermore, the quantification of some of these factors, for practical purposes, is practically missing or very seldom suggested. Therefore, the decision making process remains a subjective reflection based on the "good clinical sense" of the orthodontist or just reduced to an "educated guess". In order to add some information, hopefully useful in deciding the most suitable treatment option for the individual patient, we propose a clinical protocol based on four different factors. Namely: the skeletal discrepancy, the occlusal discrepancy, the periodontal condition and facial aesthetics. For each one of these factors several parameters will be evaluated and, for some of them, an attempt to provide some reference numerical values will be made. Finally, clinical examples will be presented to illustrate the concepts discussed and the treatment alternatives, final treatment plan and treatment outcome will be analyzed for each one of them. © EDP Sciences, SFODF, 2016.

  3. Final focus systems for linear colliders

    International Nuclear Information System (INIS)

    Helm, R.; Irwin, J.

    1992-08-01

    Final focus systems for linear colliders present many exacting challenges in beam optics, component design, and beam quality. Efforts to resolve these problems as they relate to a new generation of linear colliders are under way at several laboratories around the world. We will outline criteria for final focus systems and discuss the current state of understanding and resolution of the outstanding problems. We will discuss tolerances on alignment, field quality and stability for optical elements, and the implications for beam parameters such as emittance, energy spread, bunch length, and stability in position and energy. Beam-based correction procedures, which in principle can alleviate many of the tolerances, will be described. Preliminary results from the Final Focus Test Beam (FFTB) under construction at SLAC will be given. Finally, we mention conclusions from operating experience at the Stanford Linear Collider (SLC)

  4. Final focus systems for linear colliders

    International Nuclear Information System (INIS)

    Helm, R.; Irwing, J.

    1992-01-01

    Final focus systems for linear colliders present many exacting challenges in beam optics, component design, and beam quality. Efforts to resolve these problems as they relate to a new generation of linear colliders are under way at several laboratories around the world. We outline criteria for final focus systems and discuss the current state of understanding and resolution of the outstanding problems. We discuss tolerances on alignment, field quality and stability for optical elements, and the implications for beam parameters such as emittance, energy spread , bunch length, and stability in position and energy. Beam-based correction procedures, which in principle can alleviate many of the tolerances, are described. Preliminary results from the Final Focus Test Beam (FFTB) under construction at SLAC are given. Finally, we mention conclusions from operating experience at the Stanford Linear Collider (SLC). (Author) 16 refs., 4 tabs., 6 figs

  5. Final focus systems for linear colliders

    International Nuclear Information System (INIS)

    Erickson, R.A.

    1987-11-01

    The final focus system of a linear collider must perform two primary functions, it must focus the two opposing beams so that their transverse dimensions at the interaction point are small enough to yield acceptable luminosity, and it must steer the beams together to maintain collisions. In addition, the final focus system must transport the outgoing beams to a location where they can be recycled or safely dumped. Elementary optical considerations for linear collider final focus systems are discussed, followed by chromatic aberrations. The design of the final focus system of the SLAC Linear Collider (SLC) is described. Tuning and diagnostics and steering to collision are discussed. Most of the examples illustrating the concepts covered are drawn from the SLC, but the principles and conclusions are said to be generally applicable to other linear collider designs as well. 26 refs., 17 figs

  6. Final infarct size measured by cardiovascular magnetic resonance in patients with ST elevation myocardial infarction predicts long-term clinical outcome

    DEFF Research Database (Denmark)

    Lønborg, Jacob Thomsen; Vejlstrup, Niels Grove; Kelbæk, Henning Skov

    2013-01-01

    AIMS: Tailored heart failure treatment and risk assessment in patients following ST-segment elevation myocardial infarction (STEMI) is mainly based on the assessment of the left ventricular (LV) ejection fraction (EF). Assessment of the final infarct size in addition to the LVEF may improve...

  7. Further development of vertical-flow final sedimentation tanks; Weiterentwicklung vertikal durchstroemter Nachklaerbecken

    Energy Technology Data Exchange (ETDEWEB)

    John, K.; Purschke, A.; Schuessler, I. [Mannesmann Seiffert GmbH, Berlin (Germany)

    1999-07-01

    Because of scarcity of space, the last extension stage of the Berlin-Ruhleben sewage treatment plant was executed with vertical-flow final sedimentation tanks with a square surface. The sedimentation efficiency of these tanks in permanent operation is excellent. In the year past, the operation of such a tank at the limits of its capacity was tested under long-term conditions as a master thesis project with a view to further optimization. Subsequently, this Berlin-type tank was developed further into a multi-cell final sedimentation tank, whose effectiveness was verified by means of flow-technical simulation. (orig.) [German] Im KW Berlin-Ruhleben kamen in der letzten Ausbaustufe infolge sehr begrenzter Bauflaeche vertikal durchstroemte Nachklaerbecken mit quadratischer Oberflaeche zum Einsatz. Diese Becken zeigen im Dauerbetrieb eine hervorragende Klaerwirkung, und im vorigen Jahr wurde im Rahmen einer Diplomarbeit zwecks weiterer Optimierung langfristig unter Betriebsbedingungen die Fahrweise eines solchen Beckens an der Auslegungsgrenze getestet. Unter dem Gesichtspunkt der Kostenreduzierung wurde anschliessend der Typ Berliner Becken zum Mehrzellen-Nachklaerbecken weiterentwickelt und seine Wirksamkeit mittels stroemungstechnischer Simulation ueberprueft. (orig.)

  8. Mine-by experiment final design report

    International Nuclear Information System (INIS)

    Read, R.S.; Martin, C.D.

    1991-12-01

    The Underground Research Laboratory (URL) Mine-by Experiment is designed to provide information on rock mass response to excavation that will be used to assess important aspects of the design of a nuclear fuel waste disposal vault in a granitic pluton. The final experiment design is the result of a multidisciplinary approach, drawing on experience gained at other sites as well as the URL, and using both internal expertise and the external consultants. The final experiment design, including details on characterization, construction, instrumentation, and numerical modelling, is presented along with final design drawings

  9. Optimal partial-arcs in VMAT treatment planning

    International Nuclear Information System (INIS)

    Wala, Jeremiah; Salari, Ehsan; Chen Wei; Craft, David

    2012-01-01

    We present a method for improving the delivery efficiency of VMAT by extending the recently published VMAT treatment planning algorithm vmerge to automatically generate optimal partial-arc plans. A high-quality initial plan is created by solving a convex multicriteria optimization problem using 180 equi-spaced beams. This initial plan is used to form a set of dose constraints, and a set of partial-arc plans is created by searching the space of all possible partial-arc plans that satisfy these constraints. For each partial-arc, an iterative fluence map merging and sequencing algorithm (vmerge) is used to improve the delivery efficiency. Merging continues as long as the dose quality is maintained above a user-defined threshold. The final plan is selected as the partial-arc with the lowest treatment time. The complete algorithm is called pmerge. Partial-arc plans are created using pmerge for a lung, liver and prostate case, with final treatment times of 127, 245 and 147 s. Treatment times using full arcs with vmerge are 211, 357 and 178 s. The mean doses to the critical structures for the vmerge and pmerge plans are kept within 5% of those in the initial plan, and the target volume covered by the prescription isodose is maintained above 98% for the pmerge and vmerge plans. Additionally, we find that the angular distribution of fluence in the initial plans is predictive of the start and end angles of the optimal partial-arc. We conclude that VMAT delivery efficiency can be improved by employing partial-arcs without compromising dose quality, and that partial-arcs are most applicable to cases with non-centralized targets. (paper)

  10. Probiotics and Treatment of Vulvovaginal Candidiasis

    Directory of Open Access Journals (Sweden)

    somayeh saleki

    2018-02-01

    Full Text Available Background: Genital infections are among the most common diseases for which women refer to gynecologists. Vulvovaginal candidiasis is the second most common infection among women. Objective: A few studies have been conducted on new therapeutic regimens improving the effectiveness of current medications; accordingly, the present study was conducted to compare the effectiveness of clotrimazole with clotrimazole plus probiotics in the treatment of vulvovaginal candidiasis. Materials and Methods: The present double-blind clinical trial was conducted on 80 women admitted to Shohada hospital in Tehran in 2014. The participants were randomly divided into 2 groups of clotrimazole and clotrimazole plus probiotics. The collected data included the participants’ sociodemographic information and their medical records along with their symptoms and laboratory results before and after the treatment. Finally, the collected data were analyzed using chi-square test, t test, McNemar test and Fisherexact test. Results: The results showed that both treatments (i.e. clotrimazole and clotrimazole plus probiotics are equally effective in the treatment of vulvovaginal candidiasis (P = 0.499. Conclusion: The results of the present study indicated that supplementing clotrimazole with probiotics results in similar effects compared to administering clotrimazole alone in the treatment of vulvovaginal candidiasis.

  11. A Decision Fusion Framework for Treatment Recommendation Systems.

    Science.gov (United States)

    Mei, Jing; Liu, Haifeng; Li, Xiang; Xie, Guotong; Yu, Yiqin

    2015-01-01

    Treatment recommendation is a nontrivial task--it requires not only domain knowledge from evidence-based medicine, but also data insights from descriptive, predictive and prescriptive analysis. A single treatment recommendation system is usually trained or modeled with a limited (size or quality) source. This paper proposes a decision fusion framework, combining both knowledge-driven and data-driven decision engines for treatment recommendation. End users (e.g. using the clinician workstation or mobile apps) could have a comprehensive view of various engines' opinions, as well as the final decision after fusion. For implementation, we leverage several well-known fusion algorithms, such as decision templates and meta classifiers (of logistic and SVM, etc.). Using an outcome-driven evaluation metric, we compare the fusion engine with base engines, and our experimental results show that decision fusion is a promising way towards a more valuable treatment recommendation.

  12. Solidification of radioactive liquid wastes. A comparison of treatment options for spent resins and concentrates

    International Nuclear Information System (INIS)

    Roth, A.; Willmann, F.; Ebata, M.; Wendt, S.

    2008-01-01

    Ion exchange is one of the most common and effective treatment methods for liquid radioactive waste. However, spent ion exchange resins are considered to be problematic waste that in many cases require special approaches and pre-conditioning during its immobilization to meet the acceptance criteria for disposal. Because of the function that they fulfill, spent ion exchange resins often contain high concentrations of radioactivity and pose special handling and treatment problems. Another very common method of liquid radioactive waste treatment and water cleaning is the evaporation or diaphragm filtration. Both treatment options offer a high volume reduction of the total volume of liquids treated but generate concentrates which contain high concentrations of radioactivity. Both mentioned waste streams, spent resins as well as concentrates, resulting from first step liquid radioactive waste treatment systems have to be conditioned in a suitable manner to achieve stable waste products for final disposal. The most common method of treatment of such waste streams is the solidification in a solid matrix with additional inactive material like cement, polymer etc. In the past good results have been achieved and the high concentration of radioactivity can be reduced by adding the inactive material. On the other hand, under the environment of limited space for interim storage and the absence of a final repository site, the built-up of additional volume has to be considered as very critical. Moreover, corrosive effects on cemented drums during long-term interim storage at the surface have raised doubts about the long-term stability of such waste products. In order to avoid such disadvantages solidification methods have been improved in order to get a well-defined product with a better load factor of wastes in the matrix. In a complete different approach, other technologies solidify the liquid radioactive wastes without adding of any inactive material by means of drying

  13. A centralized hazardous waste treatment plant: the facilities of the ZVSMM at Schwabach as an example

    Energy Technology Data Exchange (ETDEWEB)

    Amsoneit, Norbert [Zweckverband Sondermuell-Entsorgung Mittelfranken, Rednitzhembach (Germany)

    1994-12-31

    In this work a centralized hazardous waste treatment plant is described and its infra-structure is presented. Special emphasis is given to the handling of the residues produced and the different treatment processes at the final disposal. 2 refs., 4 figs.

  14. A centralized hazardous waste treatment plant: the facilities of the ZVSMM at Schwabach as an example

    Energy Technology Data Exchange (ETDEWEB)

    Amsoneit, Norbert [Zweckverband Sondermuell-Entsorgung Mittelfranken, Rednitzhembach (Germany)

    1993-12-31

    In this work a centralized hazardous waste treatment plant is described and its infra-structure is presented. Special emphasis is given to the handling of the residues produced and the different treatment processes at the final disposal. 2 refs., 4 figs.

  15. Rebuttal Finale

    DEFF Research Database (Denmark)

    Howells, John; Katznelson, Ron D

    2011-01-01

    asserts that our critique engaged in ad hominem attack. Our critique notes that he “neglected” to mention critical facts, that “his scholarship is unreliable,” and that “no reader should take his radical proposals for new patent law seriously.” We regret that Lemley regards this treatment of his treatment...

  16. HTR 500: Final report of the project '' uniaxial creep tests at controlled temperature''

    International Nuclear Information System (INIS)

    1992-03-01

    The report presents the results of creep trials with HTR-concrete, which were carried out in the scope of development of prestressed concrete - reactor pressure vessels at the ETH Lausanne Institute for Steel and Prestressed Concrete. With temperature, an increase of creep and shrinkage was observed, a lesser dependence on exhaustion and type of concrete. The point in time of reaching the final value is not dependent on temperature for creep, but is for shrinkage. The modulus of elasticity depends on the temperature pre-treatment, but only insignificantly on the test temperature. figs., tabs

  17. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Stinis, Panos [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-08-07

    This is the final report for the work conducted at the University of Minnesota (during the period 12/01/12-09/18/14) by PI Panos Stinis as part of the "Collaboratory on Mathematics for Mesoscopic Modeling of Materials" (CM4). CM4 is a multi-institution DOE-funded project whose aim is to conduct basic and applied research in the emerging field of mesoscopic modeling of materials.

  18. ENGINEERING STUDY FOR THE 200 AREA EFFLUENT TREATMENT FACILITY (ETF) SECONDARY WASTE TREATMENT OF PROJECTED FUTURE WASTE FEEDS

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2004-01-01

    This report documents an engineering study conducted to evaluate alternatives for treating secondary waste in the secondary treatment train (STT) of the Hanford Site 200 Area Effluent Treatment Facility (ETF). The study evaluates ETF STT treatment alternatives and recommends preferred alternatives for meeting the projected future missions of the ETF. The preferred alternative(s) will process projected future ETF influents to produce a solid waste acceptable for final disposal on the Hanford Site. The main text of this report summarizes the ETF past and projected operations, lists the assumptions about projected operations that provide the basis for the engineering evaluation, and summarizes the evaluation process. The evaluation process includes identification of available modifications to the current ETF process, screens those modifications for technical viability, evaluates the technically viable alternatives, and provides conclusions and recommendations based on that evaluation

  19. Technically enhanced naturally occurring radioactive materials; identification, characterization and treatment

    International Nuclear Information System (INIS)

    Aly, H.F.

    2001-01-01

    Radioactive materials (TENORM) is produced in a relatively large amount with relatively small radioactivity, however in many instances the radioactivity levels exceeds that permissible. In this presentation, the different industries where enhanced levels of natural radioactivity is identified and characterized will be given. The different approaches for treatment of this enhanced radioactivity will be addressed. Finally, our research and development activities in characterization and treatment of TENORM produced from the oil fields in Egypt will be presented. (authors)

  20. US Department of Energy, Office of Technology Development, mixed-waste treatment research, development, demonstration, testing, and evaluation

    International Nuclear Information System (INIS)

    Berry, J.B.; Backus, P.M.; Conley, T.B.; Coyle, G.J.; Lurk, P.W.; Wolf, S.M.

    1993-01-01

    Department of Energy (DOE) mixed waste is contaminated with both chemically hazardous and radioactive species. The DOE is responsible for regulating radioactive species while the Environmental Protection Agency (EPA) is responsible for regulating hazardous species. Dual regulations establish treatment standards and therefore affect the treatment technologies used to process mixed waste. This duality is reflected in technology development initiatives. Significant technology development has been conducted for either radioactive or hazardous waste, but limited technology development, specifically addressing mixed waste treatment issues, has been completed. Technology has not been designed, developed, demonstrated, or tested to produce a low-risk final waste form that increases the probability that the final waste form will be disposed

  1. Treatment Deployment Evaluation Tool

    International Nuclear Information System (INIS)

    M. A. Rynearson; M. M. Plum

    1999-01-01

    The U.S. Department of Energy (DOE) is responsible for the final disposition of legacy spent nuclear fuel (SNF). As a response, DOE's National Spent Nuclear Fuel Program (NSNFP) has been given the responsibility for the disposition of DOE-owned SNF. Many treatment technologies have been identified to treat some forms of SNF so that the resulting treated product is acceptable by the disposition site. One of these promising treatment processes is the electrometallurgical treatment (EMT) currently in development; a second is an Acid Wash Decladding process. The NSNFP has been tasked with identifying possible strategies for the deployment of these treatment processes in the event that a treatment path is deemed necessary. To support the siting studies of these strategies, economic evaluations are being performed to identify the least-cost deployment path. This model (tool) was developed to consider the full scope of costs, technical feasibility, process material disposition, and schedule attributes over the life of each deployment alternative. Using standard personal computer (PC) software, the model was developed as a comprehensive technology economic assessment tool using a Life-Cycle Cost (LCC) analysis methodology. Model development was planned as a systematic, iterative process of identifying and bounding the required activities to dispose of SNF. To support the evaluation process, activities are decomposed into lower level, easier to estimate activities. Sensitivity studies can then be performed on these activities, defining cost issues and testing results against the originally stated problem

  2. Characterization of the radon source in North-Central Florida. Final report part 1 -- Final project report; Final report part 2 -- Technical report

    International Nuclear Information System (INIS)

    1997-01-01

    This report contains two separate parts: Characterization of the Radon Source in North-Central Florida (final report part 1 -- final project report); and Characterization of the Radon Source in North-Central Florida (technical report). The objectives were to characterize the radon 222 source in a region having a demonstrated elevated indoor radon potential and having geology, lithology, and climate that are different from those in other regions of the U.S. where radon is being studied. Radon availability and transport in this region were described. Approaches for predicting the radon potential of lands in this region were developed

  3. 5 CFR 1201.126 - Final decisions.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 3 2010-01-01 2010-01-01 false Final decisions. 1201.126 Section 1201.126 Administrative Personnel MERIT SYSTEMS PROTECTION BOARD ORGANIZATION AND PROCEDURES PRACTICES AND PROCEDURES Procedures for Original Jurisdiction Cases Special Counsel Disciplinary Actions § 1201.126 Final...

  4. Risk-informing special treatment requirements for reactors

    International Nuclear Information System (INIS)

    McKenna, E.M.; Reed, T.A.

    2001-01-01

    The U.S. Nuclear Regulatory Commission (NRC) is proposing to make regulatory changes to the scope of structures, systems, and components (SSCs) requiring special treatment. ''Special treatment requirements'' refers to those specific examples of regulations that are applied in order to provide a high degree of assurance that SSC will be capable of performing their intended functions when needed. The current scope of SSCs covered by the special treatment requirements governing commercial nuclear reactors is deterministically based and stems primarily from the evaluation of selected design basis events, as described in updated final safety analysis reports (UFSARs). This regulatory framework provides reasonable assurance of no undue risk to the health and safety of the public. However, recent advances in technology, coupled with operating reactor experience, have suggested that an alternative approach that would use a risk-informed process for evaluating SSC safety significance, would, in turn, result in a more focused determination of which SSCs should receive special treatment requirements. (author)

  5. Effect of intracanal cryotherapy on pain after single-visit root canal treatment.

    Science.gov (United States)

    Keskin, Cangül; Özdemir, Özgür; Uzun, İsmail; Güler, Buğra

    2017-08-01

    The purpose of this study was to evaluate the effect of 2.5°C cold saline irrigation as final irrigant on postoperative pain after single-visit root canal treatment of teeth with vital pulps. One-hundred and seventy patients were assessed as eligible and included to the study. The teeth were randomly divided into two groups (n = 85) (i.e. the control group and the cryotherapy group). In the cryotherapy group, final irrigation with 2.5°C 0.9% physiological saline solution for 5 min was performed following completion of biomechanical preparation, whereas in control group same solution stored at the root temperature was used. Treatments were performed in a single visit. Participants were asked to rate the intensity of their postoperative pain using visual analogue scale at 24 and 48 h. Data were analysed by Mann-Whitney U test and Student's t test. In the cryotherapy group level of reported postoperative pain was significantly lower than the control group (P < 0.05, Mann-Whitney U test). The outcome of this investigation indicates that 2.5°C cold saline irrigation as final irrigant can result a significant reduction in postoperative pain levels in comparison to the control group. Cryotherapy is a simple, cost-effective, and non-toxic option for postoperative pain control in single visit root canal treatment. © 2016 Australian Society of Endodontology Inc.

  6. Development of a treatment process for the removal of heavy metals from raw water for drinking water supply using chelating ion exchange resins. Subproject 1. Final report; Entwicklung der Verfahrenstechnik zur Eliminierung von Schwermetallen aus Rohwaessern zur Trinkwassergewinnung mit chelatbildenden Kationenaustauscherharzen zur technischen Reife. Teilprojekt 1. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Overath, H.; Stetter, D.; Doerdelmann, O.

    2002-07-01

    Chelating cation exchange resins with iminodiacetic acid group (Lewatit TP 207 and Amberlite IRC 748) were tested for the removal of heavy metals in a drinking water treatment plant. The pilot scale filtration experiments were conducted by varying the operating conditions, such as flow rate and feed concentrations. Heavy metal concentrations (nickel, lead, cadmium, zinc) in the feed were adjusted between 20 and 200 {mu}g/L. Different methods for regeneration and conditioning of the resins were developed and investigated. Finally the ion exchange resins were tested according to German health regulations for ion exchangers in drinking water treatment. (orig.)

  7. Mucosal Perforation During Laparoscopic Heller Myotomy Has No Influence on Final Treatment Outcome.

    Science.gov (United States)

    Salvador, Renato; Spadotto, Lorenzo; Capovilla, Giovanni; Voltarel, Guerrino; Pesenti, Elisa; Longo, Cristina; Cavallin, Francesco; Nicoletti, Loredana; Ruol, Alberto; Valmasoni, Michele; Merigliano, Stefano; Costantini, Mario

    2016-12-01

    The aims of the study were (a) to examine the final outcome in patients experiencing accidental mucosal perforation during laparoscopic Heller myotomy with Dor fundoplication (LHD) and (b) to evaluate whether perforation episodes might influence the way in which surgeons subsequently approached the LHD procedure. We studied all consecutive patients that underwent LHD between 1992 and 2015. Patients were divided into two main groups: those who experienced an intraoperative mucosal perforation (group P) and those whose LHD was uneventful (group NP). Two additional groups were compared: group A, which consisted of patients operated by a given surgeon immediately before a perforation episode occurred, and group B, which included those operated immediately afterwards. Eight hundred seventy-five patients underwent LHD; a mucosal perforation was detected in 25 patients (2.9 %), which was found unrelated to patients' symptom's score and age, radiological stage, manometric pattern, or the surgeon's experience. The median postoperative symptom score was similar for the two groups as the failure rate: 92 failures in group NP (10.8 %) and 4 in group P (16 %) (p = 0.34); moreover, symptoms recurred in 2 patients of group A (10 %) and 3 patients of group B (15 %) (p = 0.9). Accidental perforation during LHD is infrequent and impossible to predict on the grounds of preoperative therapy or the surgeon's personal experience. Despite a longer surgical procedure and hospital stay, the outcome of LHD is much the same as for patients undergoing uneventful myotomy. A recent mucosal perforation does not influence the surgeon's subsequent performance.

  8. Final disposal of the rad waste materials - question of the nuclear energy implementation and application perspectives

    International Nuclear Information System (INIS)

    Plecas, I.

    1995-01-01

    Two main problems that are denying and slowing down the development of nuclear energy are safe work of the nuclear power facilities (NEF) and disposal of the radioactive waste materials, produced from the NEF and infrastructure facilities of the nuclear fuel cycle (NFC). Although nowadays worldwide knowledge, based on the 45 year of experiences in handling the radioactive waste materials, do not treat the problems of final disposal of the rad waste materials as a task of the primary importance in NFC, this subject still engage experts from this field of investigations, especially in the countries that developed all aspects of the nuclear fuel cycle. Techniques for final disposal of low and intermediate level rad waste materials, are well known and are in state of implementation. The importance of the fundamental safety principles, implemented in the IAEA documents, concerning handling, treatment and final disposal of the rad waste materials, is presented. Future usage of nuclear energy, taking into account all the facts that are dealing with problems of the rad waste materials produced in the NFC, can be a reality. (author.)

  9. Staging laparoscopy improves treatment decision-making for advanced gastric cancer.

    Science.gov (United States)

    Hu, Yan-Feng; Deng, Zhen-Wei; Liu, Hao; Mou, Ting-Yu; Chen, Tao; Lu, Xin; Wang, Da; Yu, Jiang; Li, Guo-Xin

    2016-02-07

    To evaluate the clinical value of staging laparoscopy in treatment decision-making for advanced gastric cancer (GC). Clinical data of 582 patients with advanced GC were retrospectively analyzed. All patients underwent staging laparoscopy. The strength of agreement between computed tomography (CT) stage, endoscopic ultrasound (EUS) stage, laparoscopic stage, and final stage were determined by weighted Kappa statistic (Kw). The number of patients with treatment decision-changes was counted. A χ(2) test was used to analyze the correlation between peritoneal metastasis or positive cytology and clinical characteristics. Among the 582 patients, the distributions of pathological T classifications were T2/3 (153, 26.3%), T4a (262, 45.0%), and T4b (167, 28.7%). Treatment plans for 211 (36.3%) patients were changed after staging laparoscopy was performed. Two (10.5%) of 19 patients in M1 regained the opportunity for potential radical resection by staging laparoscopy. Unnecessary laparotomy was avoided in 71 (12.2%) patients. The strength of agreement between preoperative T stage and final T stage was in almost perfect agreement (Kw = 0.838; 95% confidence interval (CI): 0.803-0.872; P advanced GC and decrease unnecessary exploratory laparotomy.

  10. Cost analysis for final disposal of double-shell tank waste

    International Nuclear Information System (INIS)

    Seifert, T.W.; Markillie, K.D.

    1996-01-01

    The Cost Analysis For Final Disposal of Double-Shell Tank Waste provides the Department of Energy (DOE) and DOE contractors with a better understanding of costs associated with the transfer, storage, and treatment of liquid mixed wasted within the Double-Shell Tank System (DST). In order to evaluate waste minimization/pollution prevention ideas, it is necessary to have reliable cost data that can be used in cost/benefit analyses; preparation of funding requests and/or proposals; and provide a way for prioritizing and allocating limited resources. This cost per gallon rate will be used by DST waste generators to assess the feasibility of Pollution Prevention Opportunity Assessments (P20A) and to determine the cost avoidances or savings associated with the implementation of those P20As

  11. Treatment and immobilization of intermediate level radioactive wastes

    International Nuclear Information System (INIS)

    Lerch, R.E.; Greenhalgh, W.O.; Partridge, J.A.; Richardson, G.L.

    1977-01-01

    This paper discusses a new program underway to develop and demonstrate treatment and immobilization technologies for intermediate level wastes (ILW) generated in the nuclear fuel cycle. Initial work has defined the sources, quantities and types of wastes which comprise ILW. Laboratory studies are underway to define treatment technologies for liquid ILW which contains volatile contaminants and to define immobilization parameters for the residues resulting from treatment of ILW. Immobilization agents initially being evaluated for the various residues include cement, urea-formaldehyde, and bitumen although other immobilization agents will be studied. The program also includes development of acceptable test procedures for the final immobilized products as well as development of proposed criteria for storage, transportation, and disposal of the immobilized ILW. 20 figures, 10 tables

  12. Beneficial Treatment Management with Trifluridine/Tipiracil in a Patient with Metastatic Colorectal Cancer and Pronounced Hematological Event History during Previous Treatments

    Directory of Open Access Journals (Sweden)

    Volker Kaechele

    2018-01-01

    Full Text Available Trifluridine/tipiracil (FTD/TPI significantly improves overall survival in patients with metastatic colorectal cancer (mCRC. The most common treatment-related event (grade ≥3 was hematological toxicity. We here report long-term disease-stabilizing FTD/TPI treatment of an mCRC patient (KRAS wild-type, ECOG performance status 1 at baseline and at the end of FTD/TPI therapy with multifocal synchronous metastases and a longstanding history of extensive hematological events during previous treatments. Finally, this 62-year-old male patient was treated for 10 months with FTD/TPI by consecutive alteration of treatment parameters: (i initial daily dose reduction to 80 mg (72% of the recommended dose, (ii 20 days dose delay, (iii a second and later third dose reduction to 70 mg and 60 mg (about 64% and 55%, respectively, of the recommended dose, and (iv 30 µg per day of granulocyte colony-stimulating factor administration first for 3 days, and later for 5 days, for each treatment cycle.

  13. 17 CFR 8.20 - Final decision.

    Science.gov (United States)

    2010-04-01

    ... 17 Commodity and Securities Exchanges 1 2010-04-01 2010-04-01 false Final decision. 8.20 Section 8.20 Commodity and Securities Exchanges COMMODITY FUTURES TRADING COMMISSION EXCHANGE PROCEDURES FOR DISCIPLINARY, SUMMARY, AND MEMBERSHIP DENIAL ACTIONS Disciplinary Procedure § 8.20 Final decision. Each...

  14. Potential Impact of Diet on Treatment Effect from Anti-TNF Drugs in Inflammatory Bowel Disease

    DEFF Research Database (Denmark)

    Andersen, Vibeke; Hansen, Axel Kornerup; Heitmann, Berit Lilienthal

    2017-01-01

    We wanted to investigate the current knowledge on the impact of diet on anti-TNF response in inflammatory bowel diseases (IBD), to identify dietary factors that warrant further investigations in relation to anti-TNF treatment response, and, finally, to discuss potential strategies for such invest...... inflammation and potentially impact treatment response to anti-TNF drugs. Further studies using hypothesis-driven and data-driven strategies in prospective observational, animal and interventional studies are warranted.......We wanted to investigate the current knowledge on the impact of diet on anti-TNF response in inflammatory bowel diseases (IBD), to identify dietary factors that warrant further investigations in relation to anti-TNF treatment response, and, finally, to discuss potential strategies......% CI: 1.73-4.31, p impact of diet on anti-TNF treatment response for clinical use is scarce. Here we propose a mechanism by which Western style diet high in meat and low in fibre may promote colonic...

  15. 40 CFR 268.44 - Variance from a treatment standard.

    Science.gov (United States)

    2010-07-01

    ... complete petition may be requested as needed to send to affected states and Regional Offices. (e) The... provide an opportunity for public comment. The final decision on a variance from a treatment standard will... than) the concentrations necessary to minimize short- and long-term threats to human health and the...

  16. Some comments on clinical studies in orthodontics and their applications to orthodontic treatment.

    Science.gov (United States)

    Baumrind, S

    1999-06-01

    This article indicates the origins and background of the current series of National Institute of Dental and Craniofacial Research-funded, university-based clinical studies of orthodontic treatment. It suggests that future studies should be less focused on refining our estimates of mean changes during treatment and concentrate research on the systematic analysis of individual differences among patients' responses to treatment, and study how skilled clinicians make in-course corrections in response to unexpected changes in treatment conditions. Finally, some suggestions are made concerning optimization of decision making in the presence of uncertainty.

  17. The combined use of virtual reality exposure in the treatment of agoraphobia.

    Science.gov (United States)

    Pitti, Carmen T; Peñate, Wenceslao; de la Fuente, Juan; Bethencourt, Juan M; Roca-Sánchez, María J; Acosta, Leopoldo; Villaverde, María L; Gracia, Ramón

    2015-01-01

    This study compares the differential efficacy of three groups of treatments for agoraphobia: paroxetine combined with cognitive-behavioral therapy, paroxetine combined with cognitive-behavioral therapy and virtual reality exposure, and a group with only paroxetine. 99 patients with agoraphobia were finally selected. Both combined treatment groups received 11 sessions of cognitive-behavioral therapy, and one of the groups was also exposed to 4 sessions of virtual reality treatment. Treatments were applied in individual sessions once a week for 3 months. The three treatment groups showed statistically significant improvements. In some measures, combined treatment groups showed greater improvements. The virtual reality exposure group showed greater improvement confronting phobic stimuli. Treatments combining psychopharmacological and psychological therapy showed greater efficacy. Although the use of new technologies led to greater improvement, treatment adherence problems still remain.

  18. Mechanical Thrombectomy using a solitaire stent in acute ischemic stroke; The relationship between the visible antegrade flow on first device deployment and final success in revascularization

    International Nuclear Information System (INIS)

    Lee, Sung Ho; Lee, Byung Hon; Hwang, Yoon Joon; Kim, Su Young; Lee, Ji Young; Hong, Keun Sik; Cho, Yong Jin

    2015-01-01

    The purpose of the study was to evaluate the relationship between the successful revascularization on the first Solitaire stent deployment and the successful revascularization on the final angiography in acute ischemic stroke. From February 2012 to April 2014, 24 patients who underwent Solitaire stent thrombectomy as the first thrombectomy method for treatment of acute ischemic strokes were retrospectively reviewed. When the first Solitaire stent was deployed, 9 patients showed revascularization (Group 1) and 15 patients did not show revascularization (Group 2). Revascularization immediately after the first Solitaire stent removal and on the final angiography were comparatively assessed between the 2 groups. Statistical analysis was performed by the Fisher exact test and Student's t-test. The rates of revascularization maintenance immediately after the first Solitaire stent removal were 89% in Group 1 and 27% in Group 2, respectively (p = 0.009), and the rates of final successful revascularization were 100% in Group 1 and 47% in Group 2, respectively (p = 0.009). There was a statistically significant difference between the 2 groups. Revascularization on the first Solitaire stent deployment can be a useful predictor in evaluating the success of final revascularization in the treatment of acute ischemic stroke.

  19. An investigation of client mood in the initial and final sessions of cognitive-behavioral therapy and psychodynamic-interpersonal therapy.

    Science.gov (United States)

    Mcclintock, Andrew S; Stiles, William B; Himawan, Lina; Anderson, Timothy; Barkham, Michael; Hardy, Gillian E

    2016-01-01

    Our aim was to examine client mood in the initial and final sessions of cognitive-behavioral therapy (CBT) and psychodynamic-interpersonal therapy (PIT) and to determine how client mood is related to therapy outcomes. Hierarchical linear modeling was applied to data from a clinical trial comparing CBT with PIT. In this trial, client mood was assessed before and after sessions with the Session Evaluation Questionnaire-Positivity Subscale (SEQ-P). In the initial sessions, CBT clients had higher pre-session and post-session SEQ-P ratings and greater pre-to-post session mood change than did clients in PIT. In the final sessions, these pre, post, and change scores were generally equivalent across CBT and PIT. CBT outcome was predicted by pre- and post-session SEQ-P ratings from both the initial sessions and the final sessions of CBT. However, PIT outcome was predicted by pre- and post-session SEQ-P ratings from the final sessions only. Pre-to-post session mood change was unrelated to outcome in both treatments. These results suggest different change processes are at work in CBT and PIT.

  20. Superconducting quadrupoles for the SLC final focus

    International Nuclear Information System (INIS)

    Erickson, R.; Fieguth, T.; Murray, J.J.

    1987-01-01

    The final focus system of the SLC will be upgraded by replacing the final quadrupoles with higher gradient superconducting magnets positioned closer to the interaction point. The parameters of the new system have been chosen to be compatible with the experimental detectors with a minimum of changes to other final focus components. These parameter choices are discussed along with the expected improvement in SLC performance