Program nuclear safety research: report 2000

International Nuclear Information System (INIS)

Muehl, B.

2001-09-01

The reactor safety R and D work of forschungszentrum karlsruhe (FZK) had been part of the nuclear safety research project (PSF) since 1990. In 2000, a new organisational structure was introduced and the Nuclear Safety Research Project was transferred into the nuclear safety research programme (NUKLEAR). In addition to the three traditional main topics - Light Water Reactor safety, Innovative systems, Studies related to the transmutation of actinides -, the new Programme NUKLEAR also covers Safety research related to final waste storage and Immobilisation of HAW. These new topics, however, will only be dealt with in the next annual report. Some tasks related to the traditional topics have been concluded and do no longer appear in the annual report; other tasks are new and are described for the first time. Numerous institutes of the research centre contribute to the work programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2001. (orig.)

Die nuklearen Anlagen von Hanford (1943-1987) Eine Fallstudie über die Schnittstellen von Physik, Biologie und die US-amerikanische Gesellschaft zur Zeit des Kalten Krieges

Science.gov (United States)

Macuglia, Daniele

Die Geschichte des Kalten Krieges eröffnet viele Möglichkeiten, sich näher mit den Schnittstellen von Physik und Biologie während des 20. Jahrhunderts zu befassen. Nicht nur das Unglück in Tschernobyl aus dem Jahr 1986, auch das Beispiel der nuklearen Anlagen in Hanford in den Vereinigten Staaten zeigt die biologischen Folgen von nuklearer Physik.

Approval Procedure for Technical Specifications for Procurement by Quotation and Tender

International Nuclear Information System (INIS)

Shaharum Ramli; Izhar Abu Hussin; Ying, K.K.

2015-01-01

Technical specifications for procurement requires the approval of the Jawatankuasa Penyemak Spesifikasi Teknikal Tender/ Sebutharga Agensi Nuklear Malaysia. This paper provides guidance for those who have to prepare a technical specification. In addition, the technical specification online library is introduced to facilitate them to re-use old technical specifications for new procurements or to make those the bases for drafting new specifications. (author)

Untersuchungen zur Radiotoxizität von Tc-99m-markierten Radiotracern in vitro an FRTL-5- und A431-Zellen

OpenAIRE

Maucksch, Ute

2016-01-01

Einleitung/ Zielstellung Zusätzlich zur Gammastrahlung emittiert 99mTc ca. 5 niederenergetische Auger-Elektronen mit Reichweiten von wenigen Nanometern im Gewebe. Diese haben für die nuklear-medizinische Diagnostik keine Bedeutung. Es wird jedoch über eine therapeutische Nutzung diskutiert, wofür eine Anreicherung der Auger-Elektronen-Emitter in einem strahlensensitiven Zellkompartiment erforderlich ist. Ziel der Arbeit war es, verschiedene [99mTc]Tc-Radiopharmaka hinsichtlich ihres U...

Radiation and environmental radioactivity

International Nuclear Information System (INIS)

Muhamat Omar; Ismail Sulaiman; Zalina Laili

2015-01-01

This book is written based on 25 years authors experience especially in scientifc research of radiation and environmental radioactivity field at Malaysian Nuclear Agency (Nuklear Malaysia). Interestingly, from the authors experience in managing the services and consultancies for radiological environmental monitoring, it is also helpful in preparing the ideas for this book. Although this book focuses on Malaysian radiation information environmental radioactivity, but the data collected by the international bodies are also included in this book.

Study of Physical Protection System at PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Ligam, A.S.; Ina, I.; Zarina Masood

2016-01-01

Physical protection program at PUSPATI TRIGA Reactor (RTP) which is located at Nuklear Malaysia, Bangi Complex has been strengthened and upgraded from time to time to accommodate current situation needs. However, there is always room for improvement. Hence, study have been made to look deeper into physical protection components such as delay systems, external sensors, PPS intruder alarm sensors, use of video system, personnel security or insider threats, access control operation system operation rules and security culture that may need to take into consideration. (author)

Severe fuel damage projects

International Nuclear Information System (INIS)

Sdouz, G.

1987-10-01

After the descriptions of the generation of a Severe Fuel Damage Accident in a LWR the hypothetical course of such an accident is explained. Then the most significant projects are described. At each project the experimental facility, the most important results and the concluding models and codes are discussed. The selection of the projects is concentrated on the German Projekt Nukleare Sicherheit (PNS), tests performed at the Idaho National Engineering Laboratory (INEL) and smaller projects in France and Great Britain. 25 refs., 26 figs. (Author)

Nuclear medicine 2009. Abstracts; NuklearMedizin 2009. Vortraege

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

The journal contains the abstracts of 188 lectures and the abstracts of 103 poster contributions concerning the following topics: systemic therapy; oncology: PET/therapy; physics: device technology; oncology: PET/new pharmaceuticals; neurology: receptors; motion correction methods; oncology: PET/FDG; cardiology; malign thyroid tumors; neuroendocrine tumors; radiochemistry {sup 1}8F, oncology: pre-clinic PET; neurology-oncology-activation; physics: quantification; various topics; radiochemistry: radioactive metals; benign thyroid tumors; therapeutical studies; neurology: neurodegeneration; oncology: SPECT/planar scintigraphy; local therapy; inflammation; dosimetry - radiation protection; radiochemistry: halogens.

CASTOR {sup ®} and CONSTOR {sup ®}. A well established system for the dry storage of spent fuel and high level waste

Energy Technology Data Exchange (ETDEWEB)

Wimmer, Hannes; Skrzyppek, Juergen; Koebl, Michael [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany)

2015-06-01

The German company GNS Gesellschaft fuer Nuklear-Service mbH today looks back on more than 30 years of operational experience with dual-purpose casks for the transport and storage of spent nuclear fuel (SNF) from nuclear power plants and high level waste (HLW) from reprocessing. Following customer demands, GNS developed two different cask types for SNF. By now, almost 1,300 GNS-casks are in operation worldwide. This article gives an overview over several national and international projects and shows the bandwidth of customised solutions by GNS.

The nuclear disposal challenge

International Nuclear Information System (INIS)

2011-01-01

In Germany, GNS Gesellschaft fuer Nuklear-Service mbH is in charge of all operations regarding the management of waste and residual materials from nuclear power plants. Jointly with its subsidiaries, GNS is reliably ensuring the safe packaging, treatment, transport and interim storage of these materials. Moreover, as the inventor and manufacturer of the CASTOR registered casks, GNS is the global leader in the field of casks for HLW. At its locations in Essen, Muelheim, Duisburg, Juelich, Karlsruhe, Ahaus and Gorleben, the GNS group has more than 550 employees and achieves a yearly turnover of more than 200 million Euro. (orig.)

Heat transport the cold way

International Nuclear Information System (INIS)

Anon.

1981-01-01

A novel system for long-distance heat transport is being born in the 'Kernforschungsanlage Juelich' with the project being called 'Nukleare Fernenergie' (nuclear district energy). The project is also known as 'EVA/ADAM' [EVA = Einzelrohr-Versuchs-Anlage (single tube test facility); ADAM = Anlage mit Drei Adiabaten Methanisierungsreaktoren (plant provided with three adiabate methanising reactors)] and is based in principle on transport of energy in chemical bond within a closed loop. In the 60ies already this development was discussed both in the 'Kernforschungsanlage Juelich' and in the 'Rheinische Braunkohlenwerke' independent of each other. In 1975 these two organizations concluded a co-operation contract. (orig.) [de

12 Flasktransport of vitrified High Level Waste (HLW)

Energy Technology Data Exchange (ETDEWEB)

Verdier, A.; Lancelot, J. [COGEMA Logistics (AREVA Group) (France); Gisbertz, A.; Graf, W. [GNS (Germany); Bartagnon, O. [COGEMA (AREVA Group) (France)

2004-07-01

The return of HLW to Germany has started in 1996 with the first attribution of 28 glass canisters to German utilities by COGEMA. After several transports comprising 1, 2 and 6 flasks per shipment German and French Authorities requested to transport 12 flasks in a single shipment. The first of these 12-flask-transports was performed with the type CASTOR {sup registered} HAW 20/28 CG flask in 2002 and the second followed in 2003. COGEMA LOGISTICS is responsible for the overall transport assigned by GNS (Gesellschaft fuer Nuklear-Service mbH) being itself entrusted by the German utilities with the return of reprocessing residues.

Facility handling and operational considerations with dry storage casks

International Nuclear Information System (INIS)

Moegling, J.; McCreery, P.N.

1982-09-01

The Tennessee Valley Authority, in conjunction with US DOE and Pacific Northwest Laboratory, is conducting the first US commercial demonstration of spent fuel storage in casks. The two casks selected for this study are the Castor Ic, on loan from Gesellschaft fur Nuklear Service of Essen, West Germany and the DOE supplied REA 2023, manufactured by Ridihalgh, Eggers, and Associates, of Columbus, Ohio. Preparations began in the spring of 1982. The casks are expected to be loaded with fuel at Brown's Ferry Nuclear Station early in 1984, and the test completed about two years later. NRC is issuing a two-year license for this test under 10 CFR 72

12 Flasktransport of vitrified High Level Waste (HLW)

International Nuclear Information System (INIS)

Verdier, A.; Lancelot, J.; Gisbertz, A.; Graf, W.; Bartagnon, O.

2004-01-01

The return of HLW to Germany has started in 1996 with the first attribution of 28 glass canisters to German utilities by COGEMA. After several transports comprising 1, 2 and 6 flasks per shipment German and French Authorities requested to transport 12 flasks in a single shipment. The first of these 12-flask-transports was performed with the type CASTOR registered HAW 20/28 CG flask in 2002 and the second followed in 2003. COGEMA LOGISTICS is responsible for the overall transport assigned by GNS (Gesellschaft fuer Nuklear-Service mbH) being itself entrusted by the German utilities with the return of reprocessing residues

Advanced nuclear systems in comparison; Fortgeschrittene nukleare Systeme im Vergleich

Energy Technology Data Exchange (ETDEWEB)

Brogli, R.; Foskolos, K.; Goetzmann, C.; Kroeger, W.; Stanculescu, A.; Wydler, P. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

1996-09-01

This study aims at a comparison of future reactor concepts, paying particular attention to aspects of safety, of the fuel cycle, the economics, the experience-base and the state of development. Representative examples of typical development lines, that could possibly be `of interest` within a time horizon of 50 years were selected for comparison. This can be divided into three phases: - Phase I includes the next 10 years and will be characterised mainly by evolutionary developments of light water reactors (LWR) of large size; representative: EPR, - Phase II: i.e. the time between 2005 and 2020 approximately, encompasses the forecasted doubling of today`s world-wide installed nuclear capacity; along with evolutionary reactors, innovative systems like AP600, PIUS, MHTGR, EFR will emerge, - Phase III covers the time between 2020 and 2050 and is characterised by the issue of sufficient fissile material resources; novel fast reactor systems including hybrid systems can, thus, become available; representatives: IFR, EA, ITER (the latter being). The evaluated concepts foresee partly different fuel cycles. Fission reactors can be operated in principle on the basis of either a Uranium-Plutonium-cycle or a Thorium-Uranium-cycle, while combinations of these cycles among them or with other reactor concepts than proposed are possible. With today`s nuclear park (comprising mainly LWRs), the world-wide plutonium excess increases annually by about 100 t. Besides strategies based on reprocessing like: - recycling in thermal and fast reactors with mixed oxide fuels, - plutonium `burning` in reactors with novel fuels without uranium or in `hybrid` systems, allowing a reduction of this excess, direct disposal of spent fuel elements including their plutonium content (`one-through`) is being considered. (author) figs., tabs., 32 refs.

KWL annual report 1983

International Nuclear Information System (INIS)

1983-01-01

The application for decommissioning comprises the shutdown of the plant, methods for safe shielding of the nuclear section, and a modification in the utilization of the conventional plant sections. The planning documents are worked out by the Nuklear-Ingenieur-Service GmbH, Hanau. The activities for the Euratom research programmes have been completed by KWL. The final report on the determination of the activation of the biological shield is available. The processing of the enriched uranium originating from unirradiated FE as well as the conversion to UF 6 has been terminated. All spent fuel elements have been transported to BNFL. The joint works management of KWL and the VEW-power plant Emsland has been rearranged. (DG) [de

Practical Application of Monte Carlo Code in RTP

International Nuclear Information System (INIS)

Mohamad Hairie Rabir; Julia Abdul Karim; Muhammad Rawi Mohamed Zin; Na'im Syauqi Hamzah; Mark Dennis Anak Usang; Abi Muttaqin Jalal Bayar; Muhammad Khairul Ariff Mustafa

2015-01-01

Monte Carlo neutron transport codes are widely used in various reactor physics applications in RTP and other related nuclear and radiation research in Nuklear Malaysia. The main advantage of the method is the capability to model geometry and interaction physics without major approximations. The disadvantage is that the modelling of complicated systems is very computing-intensive, which restricts the applications to some extent. The importance of Monte Carlo calculation is likely to increase in the future, along with the development in computer capacities and parallel calculation. This paper presents several calculation activities, its achievements and challenges in using MCNP code for neutronics analysis, nuclide inventory and source term calculation, shielding and dose evaluation. (author)

Solar process heat for industry, seawater desalination and solar chemistry; Solare Prozesswaerme fuer Industrie, Meerwasserentsalzung und Solarchemie

Energy Technology Data Exchange (ETDEWEB)

Hennecke, K. [DLR Deutsches Zentrum fuer Luft- und Raumfahrt e.V., Berlin (Germany); Lokurlu, A. [Solitem GmbH, Aachen (Germany); Rommel, M. [Fraunhofer-Institut fuer Solare Energiesysteme (ISE), Freiburg im Breisgau (Germany); Spaete, F. [Fachhochschule Aachen, Juelich (Germany). Solar-Institut Juelich

2006-02-15

The examples discussed in this paper show that solar process heat can make an important contribution to climate protection and resource conservation. Marketable technologies providing temperatures up to approx. 200 C will be available in the short to medium term future. Continue low prices for fossil fuels and high consulting and planning costs impede the further spread of these technologies. Politicians must be called upon to facilitate the development of the market through suitable promotion programmes. There is still a long-term requirement for research, especially regarding high-temperature applications and solar chemistry.

Design, construction and commissioning of an interim spent fuel store for the decommissioning of Ignalina NPP, Lithuania

International Nuclear Information System (INIS)

Rainer Goehring; Martin Beverungen; Phil Smith

2006-01-01

The contract for the design, construction and commissioning (turn-key) of an interim spent fuel store facility (ISFSF) has been awarded to a Consortium of GNS Gesellschaft fuer Nuklear Service and RWE NUKEM GmbH under the lead of RWE NUKEM. The contract was signed on the 12.01.2005. The Interim Spent Fuel Storage Facility (ISFSF) is financed by the Ignalina Decommissioning Support Fund which is managed by EBRD. All spent fuel assemblies, currently stored in the spent fuel pits at the reactors plus future arising (about 18000 in total) will be loaded in the CONSTOR R RBMK1500/M2 containers, which are stored in the new facility. The initial contract has been awarded for 3500 spent fuel assemblies. (authors)

Nuclear power and nuclear safety 2005; Kernekraft of nuklear sikkerhed 2005

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B.; Oelgaard, P.L.; Kampman, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

2006-03-15

The report is the third report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2005 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

Nuclear power and nuclear safety 2009; Kernekraft og nuklear sikkerhed 2009

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B.; OElgaard, P.L. (eds.); Nonboel, E. (Risoe DTU, Roskilde (Denmark)); Kampmann, D.; Nystrup, P.E.; Thorlaksen, B. (Beredskabsstyrelsen, Birkeroed (Denmark))

2010-05-15

The report is the seventh report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2009 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, conflicts and the European safety directive. (LN)

Institut fuer Nukleare Entsorgungstechnik: Status report on research and development 1984

International Nuclear Information System (INIS)

1985-02-01

Some of the main points tackled by the Institute during 1984 included: Testing the glassification technique for radioactive waste and design and construction of a glassification plant; examination of the properties of glass products, testing of incineration of waste containing plutonium; solidification of concentrate containing alpha particles; separation of actinides and fission products from MAW; examination of the release procedures of radio-nuclides from waste solidified with cement; development of long-term containers for the final storage of HAW glass products in salt; model calculations for thermo-mechanical processes and for release mechanisms in final storage. (RB) [de

Nuclear power and nuclear safety 2006; Kernekraft og nuklear sikkerhed 2006

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B.; Oelgaard, P.L. (eds.); Kampmann, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

2007-04-15

The report is the fourth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2006 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power, and international relations and conflicts. (LN)

Nuclear power and nuclear safety 2010; Kernekraft og nuklear sikkerhed 2010

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B.; OElgaard, P.L. (eds.); Nonboel, E. (Risoe DTU, Roskilde (Denmark)); Kampmann, D.; Nystrup, P.E. (Beredskabsstyrelsen, Birkeroed (Denmark))

2011-07-15

The report is the eighth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2010 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, and conflicts and the Fukushima accident. (LN)

Nuclear power and nuclear safety 2007; Kernekraft og nuklear sikkerhed 2007

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B.; OElgaard, P.L. (eds.); Kampmann, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

2008-05-15

The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2007 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

Nuclear power and nuclear safety 2012; Kernekraft og nuklear sikkerhed 2012

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B.; Nonboel, E. (eds.); Oelgaard, P.L. [Technical Univ. of Denmark. DTU Risoe Campus, Roskilde (Denmark); Israelson, C.; Kampmann, D.; Nystrup, P.E.; Thomsen, J. [Beredskabsstyrelsen, Birkeroed (Denmark)

2013-11-15

The report is the tenth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is prepared in collaboration between DTU Nutech and the Danish Emergency Management Agency. The report for 2012 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the results of the EU stress test. (LN)

Nuclear power and nuclear safety 2008; Kernekraft og nuklear sikkerhed 2008

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B.; OElgaard, P.L. (eds.); Nonboel, E. (Risoe DTU, Roskilde (Denmark)); Kampmann, D. (Beredskabsstyrelsen, Birkeroed (Denmark))

2009-06-15

The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2008 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

Nuclear emergency protection. Today and tomorrow; Nuklearer Notfallschutz. Heute und morgen

Energy Technology Data Exchange (ETDEWEB)

Buettner, Jens Uwe [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Koeln (Germany). Abt. Strahlenschutz; Flury, Christoph [Bundesamt fuer Bevoelkerungsschutz BABS, Bern (Switzerland). Eidgenoessisches Departement fuer Verteidigung Bevoelkerungsschutz und Sport VBS; Gellermann, Rainer [Nuclear Control and Consulting GmbH, Braunschweig (Germany); and others

2016-07-01

The state of affairs of the nuclear emergency protection at accidents in connection with the use of nuclear power, at incidents with dangerous radiation sources as well as in case of criminal use of radioactive substances is presented. Moreover, the organization and the responsibilities as well as the preparation and realization of emergency training are considered and commented.

Nuclear power and nuclear safety 2004; Kernekraft og nuklear sikkerhed 2004

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-03-01

The report is the second report in a new series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2004 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

Nuclear power and nuclear safety 2011; Kernekraft og nuklear sikkerhed 2011

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B.; OElgaard, P.L. (eds.); Hedemann Jensen, P.; Nonboel, E. (Technical Univ. of Denmark. DTU Risoe Campus, Roskilde (Denmark)); Aage, H.K.; Kampmann, D.; Nystrup, P.E.; Thomsen, J. (Beredskabsstyrelsen, Birkeroed (Denmark))

2012-07-15

The report is the ninth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2011 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the Fukushima accident. (LN)

Radiation resistant and decontaminable coatings for shipping, interim storage and repository storage casks containing radioactive wastes

International Nuclear Information System (INIS)

Kunze, S.

1995-02-01

All the Corrobesch-DF-Nukelar coatings - black, yellow, blue, red and white - have been excellently decontaminable without and after radiation exposure with 3x10 5 Gy, despite the slightly higher absorbed dose rate applied at KFA Juelich (DIN 55 991 requires ≤1.0 KGy/h). After a further increase to 3x10 6 Gy in the absorbed dose, with an absorbed dose rate up to 1.0 KGy/h conforming to the standard, the coatings black, yellow, blue were still excellent in their decontamination behavior. After exposure to 10 7 Gy all coatings irradiated at Gammaster in their irradiation room (150 m 3 ) with permanent air changes and at absorbed dose rates of 0.9-1.0 KGy/h have been well decontaminable, and the coatings irradiated at KFA Juelich in the 10 l vessel with discontinuous air changes and variable absorbed dose rate (0.22-2.7 KGy/h) have still been fairly well decontaminable only. To be able to evaluate possible changes occurring upon 10 7 Gy radiation exposure, the test specimens were exposed to the action of chemicals according to DIN 55 991 as well as to decontamination cleansing solutions. Different discolorations, very small reductions in brilliancy, and sometimes minor deteriorations in surface hardness occurred. Detrimental visible changes, e.g. bubble and crack formation, swelling, detachment from the base, etc., have not been found for any of the coatings. These results for the test specimens irradiated at Gammaster are identical with the results for the test specimens irradiated at KFA Juelich, except minor deviations. Contrary to expectations, Corrobesch-DF-Nuklear has proved to be a coating material, which, although it consists of organic base material, nevertheless tolerates radiation exposures without visible damage, i.e. conditions under which only electrodeposited nickel coatings have appeared appropriate until now. This means that application of Corrobesch-Nuklear-DF allows the costs of coating of fuel element shipping and storage casks to be reduced

Forschungszentrum Karlsruhe Technik und Umwelt. Research and development program 2002

International Nuclear Information System (INIS)

2001-01-01

The five main fields of research and the activities under the R and D program 2002 are explained in great detail in five chapters with the following captions: 1. ENVIRONMENT. Programs: - Sustainable development, energy and environmental engineering (UMWELT). - Earth atmosphere and climate research (ATMO). 2. PUBLIC HEALTH. Programs: - Biomedical research (BIOMED). - Medical engineering (MEDTECH). 3. ENERGY. Programs: - Thermonuclear fusion (FUSION). - Nuclear safety (NUKLEAR). 4. KEY TECHNOLOGIES. Programs: - Microsystems engineering (MIKRO). - Nanotechnology (NANO). - Materials science (MATERIAL). - Chemical process engineering (CHEMIE). - Superconductivity (SUPRA). 5. MATTER and STRUCTURE. Program: The structure of matter (STRUKTUR). The sixth chapter presents cross-cutting activities under the program: Technology transfer and marketing (TTM). The concluding chapter lists and briefly presents the activities of the scientific and technical institutes of the Karlsruhe Research Center. (CB) [de

Not the market allowing to quickly pocket money. Siemens/KWU and their commitments in Central and Eastern Europe; ``Kein Markt fuer schnelles Geld``. Das Engagement von Siemens/KWU in Mittel- und Osteuropa

Energy Technology Data Exchange (ETDEWEB)

Schwegmann, P.

1997-05-01

After the break-up of the Eastern Bloc, Siemens very soon concluded strategic alliances with the big and most qualified Russian power plant manufacturers, busy activities currently focusing on the nuclear sector with retrofitting and safety engineering work in a number of NPPs. Points of main interest are systems analysis, recurrent inspection of primary loop components, and the installation of diagnostic systems for operational monitoring, as well as the instrumentation and control systems. (Orig./RHM) [Deutsch] In Russland ist es Siemens nach der politischen Wende gelungen, mit den groessten und qualifiziertesten Kraftwerksherstellern Russlands strategisch bedeutsame Allianzen einzugehen. Sehr ruehrig ist man auf dem Nuklear-Sektor. So werden gegenwaertig die Sicherheitseinrichtungen einer Reihe von Kernkraftwerken nachgebessert. Schwerpunkte sind dabei Analysen, wiederkehrende Pruefungen an Komponenten der Primaerkreislaeufe sowie die Installation von Diagnosesystemen, Betriebs- und Leittechnik. (orig.)

Micronuclei Frequencies in Lymphocytes of Nuclear Malaysia Radiation Workers

International Nuclear Information System (INIS)

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

2016-01-01

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

Pretreatment of Cellulose By Electron Beam Irradiation Method

Science.gov (United States)

Jusri, N. A. A.; Azizan, A.; Ibrahim, N.; Salleh, R. Mohd; Rahman, M. F. Abd

2018-05-01

Pretreatment process of lignocellulosic biomass (LCB) to produce biofuel has been conducted by using various methods including physical, chemical, physicochemical as well as biological. The conversion of bioethanol process typically involves several steps which consist of pretreatment, hydrolysis, fermentation and separation. In this project, microcrystalline cellulose (MCC) was used in replacement of LCB since cellulose has the highest content of LCB for the purpose of investigating the effectiveness of new pretreatment method using radiation technology. Irradiation with different doses (100 kGy to 1000 kGy) was conducted by using electron beam accelerator equipment at Agensi Nuklear Malaysia. Fourier Transform Infrared Spectroscopy (FTIR) and X-Ray Diffraction (XRD) analyses were studied to further understand the effect of the suggested pretreatment step to the content of MCC. Through this method namely IRR-LCB, an ideal and optimal condition for pretreatment prior to the production of biofuel by using LCB may be introduced.

Handbook of nuclear countries 1994/1995

Energy Technology Data Exchange (ETDEWEB)

Kappell, V.

1996-12-01

The third edition of the Handbook covers 86 countries which are reviewed in separate chapters. Depending on the completeness of information available, the review of nuclear activities of a given country covers both peaceful and military uses of atomic energy, as well as the corresponding international trade and cooperations. An appendix reproduces a self-assessment by the Turkish Government, as well as the Treaty of Tlatelolco, the nuclear weapons ban treaty for the countries of Latin America. (orig.) [Deutsch] In dieser 3. Ausgabe des Handbuches werden 86 Laender erfasst, wobei die nunklearen Aktivitaeten jedes Landes in einem eigenen Abschnitt dargestellt werden. Je nach Umfang der verfuegbaren Fakten wird sowohl ueber die friedliche als auch die militaerische Nutzung der Kernenergie und ueber den internationalen Handel und die internationale Zusammenarbeit berichtet. Im Anhang wird eine Eigendarstellung der tuerkischen Regierung wiedergegeben, sowie der Vertrag von TLATELOLCO zum Verbot nuklearer Waffen in Latein-Amerika. (orig.)

Nuclear threshold countries in the Third World. Nukleare Schwellenlaender in der Dritten Welt

Energy Technology Data Exchange (ETDEWEB)

Stahl, K. (FEST, Heidelberg (Germany))

1990-08-01

The article analyses the nuclear-technological capacities and the danger of nuclear weapons proliferation in the six nuclear threshold countries: Argentina, Brazil, India, Pakistan, Israel and South Africa. All six states have developed sensitive nuclear facilities that are not covered by IAEA-safeguards. The risk of nuclear proliferation in Argentina and Brazil is considered at present as non-existent. The economic and especially the nuclear cooperation between the two states and the mutual visits of the unsafeguarded nuclear facilities has promoted a process of confidence building and political detente between them. The risk of nuclear weapons proliferation in the Middle East is considered high. It is estimated that Israel already has built up a nuclear weapons arsenal. The growing political influence of nationalistic groups in India and Pakistan, that favour a course of confrontation between the two states, have augmented the risk of nuclear proliferation in both states. South Africa is economically and militarily clearly dominating its black ruled neighbours. The Apartheid-regime is at present negociating with the nuclear weapons states about its adherence to the NPT, but demands political, economic and military concessions in exchange for its adherence to the treaty. (orig./HSCH).

Report on research and development work 1982 of the Institut fuer Nukleare Entsorgungstechnik

International Nuclear Information System (INIS)

1983-02-01

The R and D work carried out at the Institute of Nuclear Waste Processing during 1982 under the four sections Chemistry, Processing Technology, Final Storage, and Infrastructure and Analysis is reported here. Areas of emphasis were: 1) Development and demonstration of a technical process for embedding highly radioactive solutions of fission products in borosilicate glass blocks, 2) Study of the properties of original glass moulds produced in this process, 3) Solidification of low and medium-active waste concentrates in cement, 4) Separation of actinides and fission products from medium-active waste solutions, 5) Solidification of alpha-containing concentrates in a ceramic matrix and characterization of the products, 6) Demonstration of wet chemical oxidation of combustible wastes containing higher levels of Pu together with the recovery of Pu, 7) Investigation of the release of radionuclides from medium-active waste products by leaching, corrosion, and mechanical or thermal stress, 8) Studies on the development of long-term stable containers suitable for final storage of highly radioactive glass products in salt, 9) Studies on the storage of heat-generating waste in salt, 10) Studies on analytical safety assurance for final storage in geological formations. (orig./RB) [de

Nuclear safety research in HGF 2011; Nukleare Energieforschung 2011. Forschungszentren. Status und Entwicklung

Energy Technology Data Exchange (ETDEWEB)

Tromm, Walter [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Programm NUKLEAR

2012-06-15

After the events at the Japanese nuclear power plant of Fukushima Daiichi, the German federal government decided that Germany will give up electricity generation from nuclear power within a decade. The last reactor will be disconnected from the power grid in 2022. Helping to make this opt-out as safe as possible is one of the duties of the Helmholtz Association with its Nuclear Safety Research Program within the Energy Research Area. Also the demolition of nuclear power plants and the repository problem will keep society, and thus also research, busy for a number of decades to come. Giving up electricity production from nuclear power thus must not mean giving up the required nuclear technology competences. In the fields of reactor safety, demolition, final storage, radiation protection, and crisis management, in critical support of international developments, and for competent evaluation of nuclear facilities around Germany, these competences will be in demand far beyond the German opt-out. This is the reason why the final report by the Ethics Committee on 'Safe Energy Supply' emphasizes the importance of nuclear technology research. Close cooperation on national, European and international levels is indispensable in this effort. Also nuclear safety research in the Helmholtz Association is aligned with the challenges posed by the opt-out of the use of nuclear power. It is important that the high competences in the areas of plant safety and demolition, handling of radioactive waste, and safe final storage as well as radiation protection be preserved. The Nuclear Safety Research Program within the Energy Research Area of the Helmholtz Association therefore will continue studying scientific and technical aspects of the safety of nuclear reactors and the safety of nuclear waste management. These research activities are provident research conducted for society and must be preserved for a long period of time. The work is closely harmonized with the activities of the partners in the Nuclear Competence Association. As of January 2011, the Dresden-Rossendorf Helmholtz Center (HZDR), with its 2 Institutes of Safety Research and for Radiochemistry, is an integral part of the Nuclear Safety Research Program within the Energy Research Area. Both institutes work on topics of safety research for nuclear reactors and safety research for nuclear waste management. In this way, the 2 institutes represent very welcome added value as well as a supplement to the Nuclear Safety Research Program. (orig.)

SSYST, Modular System for Transient Fuel Rod Behaviour Under Accident Condition

International Nuclear Information System (INIS)

Gulden, W.; Meyder, R.; Borgwaldt, H.

1987-01-01

1 - Description of problem or function: SSYST is a code system for analyzing transient fuel rod behaviour under off-normal conditions, developed jointly by the Institut fuer Kernenergetik und Energie-systeme (IKE), Stuttgart, and Kernforschungszentrum Karlsruhe (KfK) under contract for the Projekt Nukleare Sicherheit (PNS) at KfK. Main differences versus codes with similar applications are: (1) an open-ended modular code organisation; (2) a preference for simple models, wherever possible. While feature (1) makes SSYST a very flexible tool, easily adapted to changing requirements, feature (2) leads to short execution times. The analysis of transient rod behaviour under LOCA boundary conditions takes 2 minutes CPU time on IBM 3033, so that extensive parametric studies are feasible. Main differences between SSYST-3 and previous versions are related to a general clean-up of the code system, which reduces the implementation effort: - advanced modules for cladding deformation and oxidation and reflooding conditions are included; - an input processor thoroughly checks all input data

Progress report on R + D activities of the Institute fuer Reaktorenentwicklung in 1980

International Nuclear Information System (INIS)

1981-02-01

The Institute fuer Reaktorentwicklung is mostly concerned with technical problems in the development and safety assurance of nuclear facilities. The tasks, some of which are carried out in cooperation with other internal and external institutions, are of a theoretical and experimental nature, most of them in the field of reactor safety. The two main fields are the Projekt Schneller Brueter (PSB) and Projekt Nukleare Sicherheit (PNS). The contributions for PSB, i.e. layout and safety of sodium-cooled fast breeder reactors, refer to investigations of the thermohydraulic and neutron-kinetical response of the core to accidents of very low probability as well as investigations of the effects of local core coling disturbances, with special consideration to possible damage propagation mechanisms and the possibility of detecting these processes. In the field of LWR safety, dynamic loads on core internals have been investigated during the HDR blowdown experiments as well as dynamic loads on containment structures and fuel rod behaviour during LOCA. (orig.) [de

Spent fuel metal storage cask performance testing and future spent fuel concrete module performance testing

International Nuclear Information System (INIS)

McKinnon, M.A.; Creer, J.M.

1988-10-01

REA-2023 Gesellshaft fur Nuklear Service (GNS) CASTOR-V/21, Transnuclear TN-24P, and Westinghouse MC-10 metal storage casks, have been performance tested under the guidance of the Pacific Northwest Laboratory to determine their thermal and shielding performance. The REA-2023 cask was tested under Department of Energy (DOE) sponsorship at General Electric's facilities in Morris, Illinois, using BWR spent fuel from the Cooper Reactor. The other three casks were tested under a cooperative agreement between Virginia Power Company and DOE at the Idaho National Engineering Laboratory (INEL) by EGandG Idaho, Inc., using intact spent PWR fuel from the Surry reactors. The Electric Power Research Institute (EPRI) made contributions to both programs. A summary of the various cask designs and the results of the performance tests is presented. The cask designs include: solid and liquid neutron shields; lead, steel, and nodular cast iron gamma shields; stainless steel, aluminum, and copper baskets; and borated materials for criticality control. 4 refs., 8 figs., 6 tabs

Studying the Variable Refrigerant Volume (VRV) System and Determining the Root Cause of its Problem in Building 37, Malaysian Nuclear Agency

International Nuclear Information System (INIS)

Suhafizudin Zainal Anuar; Mohamad Suhaimi Yahaya; Jusnan Hasim; Suhilah Mohd Ali; Mohd Khafidz Shamsuddin

2015-01-01

Variable Refrigerant Volume (VRV) system is one of the Heating, Ventilation and Air Conditioning (HVAC) type in the building. VRV system is a multi-split type air conditioner that uses variable refrigerant flow control to provide customers with the ability to maintain individual zone control in each room and floor of a building. VRV used in Building 37 is made by Mitsubishi Heavy Industries that was completely installed in 2011 with two pipes system format. The objectives of this study are to understand the Variable Refrigerant Volume (VRV) system and also to study the root cause of its problem in Building 37, Agensi Nuklear Malaysia. The result of the study study suggests poor workmanship during installation process and insufficient electrical grounding are suspected as the causes of on-going and repeating problems occurred. Hence, Bahagian Kejuruteraan (BKJ) has worked out with the service contractor to identify the main problem and leaking area before proceeding with repair and commissioning activities. (author)

Gained experiences concerning the treatment of radioactive metal scrap from German NPP'S in Studsvik - Gained experience concerning the treatment of radioactive metal scrap from German nuclear power plants

International Nuclear Information System (INIS)

Westerwinter, Boris; Buckanie, Niemma

2014-01-01

The company Gesellschaft fuer Nuklear-Service mbH, Essen/Germany (GNS), operates on behalf of the utilities E.ON, RWE, EnBW and VENE since the nineteen-nineties - amongst its other duties - on the waste management of metal scrap which originates from German nuclear power plants. The main objective within this responsibility is to maximize the value of recyclable fractions for re-use while minimizing the resulting radioactive waste. To achieve the aforementioned objective, melting of metallic scrap proved to be an outstanding choice. The use of this technique combined with all accompanying processes and regulations is accepted by the competent authorities and independent experts as a qualified treatment method over the entire time period. The motivation of this paper is to reflect on the experiences gained concerning the planning, implementation and results, acquired by GNS by using the Studsvik service. The focus will be on characteristics within processing of such campaigns. (authors)

Steam supply for the Principality of Liechtenstein. Process heat for industrial applications; Dampflieferung fuer das Fuerstentum Liechtenstein. Prozesswaerme fuer die Industrie

Energy Technology Data Exchange (ETDEWEB)

Dokter, Ernst [VfA Buchs fuer Kraft-Waerme-Kopplung und das Ferndampfsystem, Buchs (Switzerland)

2009-07-15

Switzerland is leading the world in thermal waste management. There are 29 incinerators (KVA - Kehrichtverbrennungsanlagen) with a capacity of 3.7 million t.p.a. They are operated by industrial or municipal owners and by the Verein fuer Abfallentsorgung Buchs SG. (orig.)

SSYST, a code-system for analysing transient LWR fuel rod behaviour under off-normal conditions

International Nuclear Information System (INIS)

Borgwaldt, H.; Gulden, W.

1983-01-01

SSYST is a code-system for analysing transient fuel rod behaviour under off-normal conditions, developed conjointly by the Institut fuer Kernenergetik und Energiesysteme (IKE), Stuttgart, and Kernforschungszentrum Karlsruhe (KfK) under contract of Projek Nukleare Sicherheit (PNS) at KfK. The main differences between SSYST and similar codes are (1) an open-ended modular code organisation, and (2) a preference for simple models, wherever possible. While the first feature makes SSYST a very flexible tool, easily adapted to changing requirements, the second feature leads to short execution times. The analysis of transient rod behaviour under LOCA boundary conditions takes 2 min cpu-time (IBM-3033), so that extensive parametric studies become possible. This paper gives an outline of the overall code organisation and a general overview of the physical models implemented. Besides explaining the routine application of SSYST in the analysis of loss-of-coolant accidents, examples are given of special applications which have led to a satisfactory understanding of the decisive influence of deviations from rotational symmetry on the fuel rod perimeter. (author)

Comparison of transports expected under different waste management concepts: determination of basic data for application in risk analyses

International Nuclear Information System (INIS)

Alter, U.; Mielke, H.G.; Wehner, G.

1983-01-01

According to the Atomic Act, article 9a, paragraph 1, the licensees of nuclear power plants in the Federal Republic of Germany are obliged to provide for the management of radioactive wastes resulting from the operation of these plants. Concerning the provisions to be made for the management of such wastes, two concepts are discussed: nuclear reprocessing and final waste disposal center (Nukleares Entsorgungszentrum, NEZ); and the integrated spent fuel and waste management concept (Integriertes Entsorgungskonzept, IEK). Unlike the NEZ, the IEK-concept may have different sites for the following fuel cycle facilities: intermediate spent fuel storage, reprocessing, waste conditioning and final disposal, and uranium and plutonium fuel element fabrication facilities. The fundamental differences of the pertinent transports are presented. Transport scenarios expected under the two alternatives NEZ and IEK have been elaborated for the purpose of a data collection covering the following aspects: materials to be shipped, number of packages shipped, number of packages shipped per transport, transport by rail or by road, transport routes and distances, and duration of transports

Progress report on research and development activities of the Institut fuer Neutronenphysik und Reaktortechnik in 1980

International Nuclear Information System (INIS)

1981-02-01

The Institut fuer Neutronenphysik und Reaktortechnik carries out research in nuclear enginering especially in the context of the development of sodium-cooled fast breeder reactors. The institute does theoretical and experimental work in equal shares. Most of the work is done in cooperation with other institutes and industrial groups. In the framework of the Projekt Schneller Brueter , the institute investigates the layout and safety problems, from a reactor physics point of view of large fast breeder cores. Problems concerning the effects of LWR accidents on population and environment are investigated in the Projekt Nukleare Sicherheit . To the Projekt Wiederaufarbeitung , the institute is contributing work on fuel cycle physics and the development of a suitable instrumentation. In the field of nuclear safeguards, the implementation of monitoring systems is being investigated. Research outside projects is being done on technical and physical problems of fusion by inertial confinement and application of nuclear power on the transportation sector with hydrogen as an energy source. The main results obtained in 1980 in the various projects are presented. (orig./RW) [de

A Well Established System For The Dry Storage Of Spent Fuel

Energy Technology Data Exchange (ETDEWEB)

Skrzyppek, Juergen; Kim, Josef Du-III [SMART Power Company, Essen (Germany)

2015-05-15

The German company GNS Gesellschaft fur Nuklear-Service mbH today looks back on more than 30 years of operational experience with dual-purpose casks. Following customer demands, GNS developed two different cask types for SNF the CASTOR and the CONSTOR cask type. While the CASTOR type is optimized for high thermal loads which allows loading after extremely short cooling times and/or high burn-up of the SNF the CONSTOR type is cost optimized for the cost-efficient storage of large quantities of cooler SNF. By now almost 1,300 GNS-casks are in operation worldwide. In Germany alone, more than 1000 CASTOR casks are stored with individual storage periods of up to 30 years. Taking into account the additional casks that have to be manufactured, loaded and stored during the final years of the German Nuclear Phase-Out, there will be 2000 casks by GNS in operation worldwide. The presentation will give an overview over several national and international projects and show the bandwidth of customized solutions by GNS.

SSYST: A code-system for analyzing transient LWR fuel rod behaviour under off-normal conditions

International Nuclear Information System (INIS)

Borgwaldt, H.; Gulden, W.

1983-01-01

SSYST is a code-system for analyzing transient fuel rod behaviour under off-normal conditions, developed conjointly by the Institut fur Kernenergetik und Energiesysteme (IKE), Stuttgart, and Kernforschungszentrum Karlsruhe (KfK) under contract of Projekt Nukleare Sicherheit (PNS) at KfK. The main differences between SSYST and similar codes are an open-ended modular code organization, and a preference for simple models, wherever possible. While the first feature makes SSYST a very flexible tool, easily adapted to changing requirements, the second feature leads to short execution times. The analysis of transient rod behaviour under LOCA boundary conditions takes 2 min cpu-time (IBM-3033), so that extensive parametric studies become possible. This paper gives an outline of the overall code organisation and a general overview of the physical models implemented. Besides explaining the routine application of SSYST in the analysis of loss-of-coolant accidents, examples are given of special applications which have led to a satisfactory understanding of the decisive influence of deviations from rotational symmetry on the fuel rod perimeter

Vitrification of HLLW in the People's Republic of China

International Nuclear Information System (INIS)

Sun Dong; Wang Xian; Pu Yong; Weisenburger, S.

1993-01-01

An important part of the nuclear fuel cycle management in the People's Republic of China is the solidification of high level liquid waste (HLLW) and its safe disposal. In recent years, efforts have been directed to the Liquid-Fed Ceramic Melter process (LFCM). The first step in the established HLLW management program is the design and construction of a full scale nonradioactive mock-up facility designated VPM (Vitrification Plant Mock-up). The joint design of the VPM was performed in 1991 within the scope of an engineering contract carried out by the Beijing Institute of Nuclear Engineering (BINE), the Institut fuer Nukleare Entsorgungstechnik (INE) of the Karlsruhe Nuclear Research Centre (KfK) and a German consortium (KKN) of Siemens-KWU, KAH and NUKEM. The large scale melter has been constructed at INE in 1992 and will be tested in an existing test plant of INE before delivery to China in 1994 for further use in the VPM facility. This facility will be constructed and operated by CNEIC (China Nuclear Energy Industry Corporation)

The INE-Beamline for Actinide Research at ANKA

Science.gov (United States)

Brendebach, Boris; Denecke, Melissa A.; Rothe, Jörg; Dardenne, Kathy; Römer, Jürgen

2007-02-01

The INE-Beamline for actinide research at the synchrotron source ANKA is now fully operational. This beamline was designed, built, and commissioned by the Institut für Nukleare Entsorgung (INE) at the Forschungszentrum Karlsruhe (FZK), Germany. It is dedicated to actinide speciation investigations related to nuclear waste disposal as well as applied and basic actinide research. Experiments on radioactive samples with activities up to 106 times the limit of exemption inside a safe and flexible double containment concept are possible. The close proximity of the beamline to INE's active laboratories is unique in Europe. Currently, experiments can be performed in an X-ray energy range from around 2.15 keV (P K edge) to 24.35 keV (Pd K edge). The INE-Beamline design is optimized for spectroscopy with emphasis on surface sensitive techniques. A microfocus option is presently being installed at the INE-Beamline. Access to the INE-Beamline is possible through cooperation with INE, through the ANKA proposal system and via the European Network of Excellence for Actinide Sciences (ACTINET).

Research and development activities of the Institut fuer Nukleare Entsorgungstechnik on the decontamination of surfaces

International Nuclear Information System (INIS)

Dippel, T.; Hentschel, D.; Kunze, S.

1983-06-01

After developing a procedure for the ''Testing of Surface Coating Materials for the Decontamination'' about 900 different surface coating materials had been tested and evaluated for the domestic and foreign industry. The results prove the following basic facts: Surface coatings, low in porosity, forming a smooth surface and containing limited amounts of filler are in the majority very effectively decontaminated if they are prepared of chemically stable, water repellent materials; Decontamination results are drastically poorer if the degree of filling of the materials is high especially if hygroscopic fillers and/or hygroscopic colouring matters are used. Currently available cleansers and washing powders used for decontamination did not fulfill the three basic demands for a decontamination agent: high efficiency, small foam generation and sufficient thermal stability. Therefore for the decontamination of walls, floors, etc. a water delutable, liquid cleanser was developed. In the same context a washing powder was optimized for the decontamination of contaminated clothing. The experiments on the decontamination of stainless steels ended up with the formulation of a pickling paste. Furthermore all investigations were aimed at a minimization of the waste generation by the decontamination process. This resulted in decontamination techniques, in which the decontaminating agents were applied in thin layers. A comparison of the currently practiced dipping technique with the coating technique showed that the latter one gave the better decontamination results and that the amount of decontamination waste was reduced. (orig./HP) [de

Nuclear safety research in HGF 2012; Fortschrittsbericht 2012. Programm 'Nukleare Sicherheitsforschung' Helmholtz-Gemeinschaft

Energy Technology Data Exchange (ETDEWEB)

Anon.

2013-06-15

After the events at the Japanese nuclear power plant of Fukushima Daiichi, the German Federal government decided that Germany will give up electricity generation from nuclear power within a decade. The last reactor will be disconnected from the power grid in 2022. Helping to make this opt-out safe is one of the duties of the Helmholtz Association with its Nuclear Safety Research Program within the Energy Research Area. Also the demolition of nuclear power plants and the repository problem will keep society, and thus also research, busy for a number of decades to come. Giving up electricity production from nuclear power thus must not mean giving up the required nuclear technology competences. In the fields of reactor safety, demolition, final storage, radiation protection, and crisis management, in critical support of international developments, and for competent evaluation of nuclear facilities around Germany, these competences will be in demand far beyond the German opt-out. This is the reason why the final report by the Ethics Committee on 'Safe Energy Supply' emphasizes the importance of nuclear technology research. Close cooperation on national, European and international levels is indispensable in this effort. Also nuclear safety research in the Helmholtz Association is aligned with the challenges posed by the opt-out of the use of nuclear power. It is important that the high competences in the areas of plant safety and demolition, handling of radioactive waste, and safe final storage as well as radiation protection be preserved. The Nuclear Safety Research Program within the Energy Research Area of the Helmholtz Association therefore will continue studying scientific and technical aspects of the safety of nuclear reactors and the safety of nuclear waste management. These research activities are provident research conducted for society and must be preserved for a long period of time. The work is closely harmonized with the activities of the partners in the Nuclear Competence Association. The Forschungszentrum Juelich GmbH, HZDR Helmholtz-Zentrum Dresden-Rossendorf and the KIT Karlsruhe Institute of Technology are involved in the Nuclear Safety Research Program within the Helmholtz Association. The work and results in 2012 are presented. (orig.)

The international regime for nuclear safety after Fukushima; Das internationale System nuklearer Sicherheit nach Fukushima

Energy Technology Data Exchange (ETDEWEB)

Raetzke, Christian [CONLAR Consulting on Nuclear Law and Regulation, Leipzig (Germany)

2014-05-15

The Chernobyl catastrophe in 1986 lead to a new foundation of the international regime for nuclear safety: the 1994 Convention on Nuclear Safety introduced for the first time obligations on adhering states to adopt certain principles to achieve a high level of safety. The Convention, however, does not contain detailed standards, nor does it install a 'hard' mechanism for control and enforcement. While the system has undoubtedly lead to improvements in nuclear safety worldwide, it was not able to detect and remedy the deficiencies in the Japanese system. Ideas voiced immediately after the Fukushima accident to take a further decisive step towards a more stringent international system seemed not to be met with enthusiasm. The general tendency is to use the existing instruments and mechanisms in a more effective manner. However, very recently (in April 2014) the member states of the Convention on Nuclear Safety decided to stage a diplomatic conference with the aim to amend the Convention and to insert safety objectives. Time will eventually show whether this is a first, but decisive step towards the idea of an international system of mandatory and enforceable nuclear safety standards. (orig.)

Release of fission products during controlled loss-of-coolant accidents and hypothetical core meltdown accidents

International Nuclear Information System (INIS)

Albrecht, H.; Malinauskas, A.P.

1978-01-01

A few years ago the Projekt Nukleare Sicherheit joined the United States Nuclear Regulatory Commission in the development of a research program which was designed to investigate fission product release from light water reactor fuel under conditions ranging from spent fuel shipping cask accidents to core meltdown accidents. Three laboratories have been involved in this cooperative effort. At Argonne National Laboratory (ANL), the research effort has focused on noble gas fission product release, whereas at Oak Ridge National Laboratory (ORNL) and at Kernforschungszentrum Karlsruhe (KfK), the studies have emphasized the release of species other than the noble gases. In addition, the ORNL program has been directed toward the development of fission product source terms applicable to analyses of spent fuel shipping cask accidents and controlled loss-of-coolant accidents, and the KfK program has been aimed at providing similar source terms which are characteristic of core meltdown accidents. The ORNL results are presented for fission product release from defected fuel rods into a steam atmosphere over the temperature range 500 to 1200 0 C, and the KfK results for release during core meltdown sequences

Castor-1C spent fuel storage cask decay heat, heat transfer, and shielding analyses

International Nuclear Information System (INIS)

Rector, D.R.; McCann, R.A.; Jenquin, U.P.; Heeb, C.M.; Creer, J.M.; Wheeler, C.L.

1986-12-01

This report documents the decay heat, heat transfer, and shielding analyses of the Gesellschaft fuer Nuklear Services (GNS) CASTOR-1C cask used in a spent fuel storage demonstration performed at Preussen Elektra's Wurgassen nuclear power plant. The demonstration was performed between March 1982 and January 1984, and resulted in cask and fuel temperature data and cask exterior surface gamma-ray and neutron radiation dose rate measurements. The purpose of the analyses reported here was to evaluate decay heat, heat transfer, and shielding computer codes. The analyses consisted of (1) performing pre-look predictions (predictions performed before the analysts were provided the test data), (2) comparing ORIGEN2 (decay heat), COBRA-SFS and HYDRA (heat transfer), and QAD and DOT (shielding) results to data, and (3) performing post-test analyses if appropriate. Even though two heat transfer codes were used to predict CASTOR-1C cask test data, no attempt was made to compare the two codes. The codes are being evaluated with other test data (single-assembly data and other cask data), and to compare the codes based on one set of data may be premature and lead to erroneous conclusions

No advantages in terms of safety. 'Energy in a Dialog' about the 'Final disposal site selection law'

International Nuclear Information System (INIS)

Anon.

2013-01-01

The current legislative process for the site selection law (StandAG) was topic of the DAtF event 'Energy in a Dialog' on 6 June 2013 in Berlin: 'Is the path the goal: purpose and results of the site selection law'. The President of the German Atomic Forum (DAtF), Dr. Ralf Gldner, moderated the discussion with Prof. Dr. Ortwin Renn of the University of Stuttgart and the CEO of the Gesellschaft fuer Nuklear-Service (GNS), Hannes Wimmer. The opportunities and risks of a new site search for high-level radioactive waste were the main topics. Professor Renn summarized some findings to conditions of acceptance perceived in connection with industrial projects. Dr. Wimmer said in his keynote that social acceptance for site selection for a repository must be maintained for a long time. During the ensuing discussion, a common understanding was evident on some aspects of the topic. This is especially true for a limitation of the new location search method in terms of its objective. As a realistic objective to determine a secure suitable site was considered instead of a 'best' location proposed by the new law. (orig.)

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-01-22

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

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Stakeholder engagement for promoting the Comprehensive Nuclear-Test-Ban Treaty (CTBT): Malaysia’s experience

Science.gov (United States)

Rashid, F. I. A.; Zolkaffly, M. Z.; Jamal, N.

2018-01-01

In order to keep abreast on issues related to CTBT in Malaysia, Malaysian Nuclear Agency (Nuklear Malaysia), as the CTBT National Authority in Malaysia, has collaborated with local partners to implement various stakeholder engagement programme. This paper aims at highlighting Malaysia’s approach in promoting CTBT through stakeholder engagement programme targeted at multilevel stakeholders, both national and international. Such programmes includes participation in the international forums, inter-agency meetings, awareness seminars, training courses, technical visits to IMS station, promoting civil and scientific application of International Monitoring System (IMS) data and International Data Centre (IDC) products using Virtual Data Exploitation Center (vDEC), inviting youth groups to participate in the CTBTO Youth Group, and publications of CTBT-related topics. This approach has successfully fortify Malaysia’s commitments at the international level, enhanced national awareness of global multilateral framework, increased stakeholders awareness and their roles related to CTBT, as well as building domestic capacity on CTBT matters. In conclusion, stakeholder engagement is crucial in promoting and enhancing stakeholders understanding on CTBT. Continuous engagement with relevant stakeholders will enable effective dissemination and smooth implementation of CTBT related matters that will eventually support global universalization of CTBT.

Swedish-German actinide migration experiment at ÄSPÖ hard rock laboratory

Science.gov (United States)

Kienzler, B.; Vejmelka, P.; Römer, J.; Fanghänel, E.; Jansson, M.; Eriksen, T. E.; Wikberg, P.

2003-03-01

Within the scope of a bilateral cooperation between Svensk Kärnbränslehantering (SKB) and Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung (FZK-INE), an actinide migration experiment is currently being performed at the Äspö Hard Rock Laboratory (HRL) in Sweden. This paper covers laboratory and in situ investigations on actinide migration in single-fractured granite core samples. For the in situ experiment, the CHEMLAB 2 probe developed by SKB was used. The experimental setup as well as the breakthrough of inert tracers and of the actinides Am, Np and Pu are presented. The breakthrough curves of inert tracers were analyzed to determine hydraulic properties of the fractured samples. Postmortem analyses of the solid samples were performed to characterize the flow path and the sorbed actinides. After cutting the cores, the abraded material was analyzed with respect to sorbed actinides. The slices were scanned optically to visualize the flow path. Effective volumes and inner surface areas were measured. In the experiments, only breakthrough of Np(V) was observed. In each experiment, the recovery of Np(V) was ≤40%. Breakthrough of Am(III) and Pu(IV) as well as of Np(IV) was not observed.

Neutronic simulation calculations to assess the proliferation resistance of nuclear technologies; Neutronenphysikalische Simulationsrechnungen zur Proliferationsresistenz nuklearer Technologien

Energy Technology Data Exchange (ETDEWEB)

Englert, Matthias

2009-07-13

This thesis investigates the proliferation resistance of nuclear technologies on the basis of three case studies. After a brief description of the concept of proliferation resistance the utilized computer codes and methods are presented. The first case study investigates the potential of monolithic fuel for the conversion of one-fuel-element high-flux research reactors from highly enriched to low enriched uranium using the example of the german research reactor FRM-II. The second case study assesses the proliferation potential of future tokamak based fusion reactors by using neutronic simulations of a possible plutonium production. The third example investigates the proliferation potential of spallation neutron sources to produce nuclear weapon relevant material and the proliferation resistance of such facilities. (orig.)

NUKEM. Innovative solutions for nuclear engineering

International Nuclear Information System (INIS)

Scheffler, Beate

2011-01-01

Management of radioactive waste, handling spent fuel elements, decommissioning of nuclear facilities, and engineering and consulting activities are services associated with the name of NUKEM all over the world. The company's scientists and engineers develop solution concepts combining the latest technologies with proven techniques and many years of experience. The company;s history and the services offered to the nuclear industry began more than 5 decades ago. The predecessor, NUKEM Nuklear-Chemie-Metallurgie, was founded in 1960 as one of the earliest nuclear companies in Germany. Originally, the firm produced fuel elements for a variety of reactor lines. As early as in the 1970s, logical extensions of these business activities were nuclear engineering and plant construction. In the meantime, NUKEM Technologies GmbH has developed a worldwide reputation for its activities. Numerous reference projects bear witness to optimum project management and customer satisfaction. Since 2009, NUKEM Technologies has been a wholly owned subsidiary of the Russian Atomstroyexport. NUKEM Technologies operates sales and project offices outside Germany, e.g. in Russia, China, Lithuania, France, and Bulgaria. In this way, the company is present in its target markets of Russia, Western and Eastern Europe as well as Asia, offering customers and partners fast and direct contacts. (orig.)

SSYST. A code system to analyze LWR fuel rod behavior under accident conditions

International Nuclear Information System (INIS)

Gulden, W.; Meyder, R.; Borgwaldt, H.

1982-01-01

SSYST (Safety SYSTem) is a modular system to analyze the behavior of light water reactor fuel rods and fuel rod simulators under accident conditions. It has been developed in close cooperation between Kernforschungszentrum Karlsruhe (KfK) and the Institut fuer Kerntechnik und Energiewandlung (IKE), University Stuttgart, under contract of Projekt Nukleare Sicherheit (PNS) at KfK. Although originally aimed at single rod analysis, features are available to calculate effects such as blockage ratios of bundles and wholes cores. A number of inpile and out-of-pile experiments were used to assess the system. Main differences versus codes like FRAP-T with similar applications are (1) an open-ended modular code organisation, (2) availability of modules of different sophistication levels for the same physical processes, and (3) a preference for simple models, wherever possible. The first feature makes SSYST a very flexible tool, easily adapted to changing requirements; the second enables the user to select computational models adequate to the significance of the physical process. This leads together with the third feature to short execution times. The analysis of transient rod behavior under LOCA boundary conditions e.g. takes 2 mins cpu-time (IBM-3033), so that extensive parametric studies become possible

Development of integrated radioactive waste packaging and conditioning solutions in the UK

Energy Technology Data Exchange (ETDEWEB)

Sibley, Peter; Butter, Kevin; Zimmerman, Ian [EnergySolutions EU Ltd., Swindon, Wiltshire (United Kingdom); Viermann, Joerg [GNS Gesellschaft fur Nuklear-Service mbH, Essen (Germany); Messer, Matthias [GNS Gesellschaft fur Nuklear-Service mbH, Bristol (United Kingdom)

2013-07-01

In order to offer a more cost effective, safer and efficient Intermediate Level Waste (ILW) management service, EnergySolutions EU Ltd. and Gesellschaft fur Nuklear-Service mbH (GNS) have been engaged in the development of integrated radioactive waste retrieval, packaging and conditioning solutions in the UK. Recognising the challenges surrounding regulatory endorsement and on-site implementation in particular, this has resulted in an alternative approach to meeting customer, safety regulator and disposability requirements. By working closely with waste producers and the organisation(s) responsible for endorsing radioactive waste management operations in the UK, our proposed solutions are now being implemented. By combining GNS' off-the-shelf, proven Ductile Cast Iron Containers (DCICs) and water removal technologies, with EnergySolutions EU Ltd.'s experience and expertise in waste retrieval, safety case development and disposability submissions, a fully integrated service offering has been developed. This has involved significant effort to overcome technical challenges such as onsite equipment deployment, active commissioning, conditioning success criteria and disposability acceptance. Our experience in developing such integrated solutions has highlighted the importance of working in collaboration with all parties to achieve a successful and viable outcome. Ultimately, the goal is to ensure reliable, safe and effective delivery of waste management solutions. (authors)

Handbook on criticality. Vol. 1. Criticality and nuclear safety; Handbuch zur Kritikalitaet. Bd. 1. Kritikalitaet und nukleare Sicherheit

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-04-15

This handbook was prepared primarily with the aim to provide information to experts in industry, authorities or research facilities engaged in criticality-safety-related problems that will allow an adequate and rapid assessment of criticality safety issues already in the planning and preparation of nuclear facilities. However, it is not the intention of the authors of the handbook to offer ready solutions to complex problems of nuclear safety. Such questions have to remain subject to an in-depth analysis and assessment to be carried out by dedicated criticality safety experts. Compared with the previous edition dated December 1998, this handbook has been further revised and supplemented. The proven basic structure of the handbook remains unchanged. The handbook follows in some ways similar criticality handbooks or instructions published in the USA, UK, France, Japan and the former Soviet Union. The expedient use of the information given in this handbook requires a fundamental understanding of criticality and the terminology of nuclear safety. In Vol. 1, ''Criticality and Nuclear Safety'', therefore, first the most important terms and fundamentals are introduced and explained. Subsequently, experimental techniques and calculation methods for evaluating criticality problems are presented. The following chapters of Vol. 1 deal i. a. with the effect of neutron reflectors and absorbers, neutron interaction, measuring methods for criticality, and organisational safety measures and provide an overview of criticality-relevant operational experience and of criticality accidents and their potential hazardous impact. Vol. 2 parts 1 and 2 finally compile criticality parameters in graphical and tabular form. The individual graph sheets are provided with an initially explained set of identifiers, to allow the quick finding of the information of current interest. Part 1 includes criticality parameters for systems with {sup 235}U as fissile material, while part 2 deals with systems comprising {sup 233}U, plutonium and higher actinides.

Environmental protection and nuclear safety in the European nuclear policy; Umweltschutz und nukleare Sicherheit in der europaeischen Atompolitik

Energy Technology Data Exchange (ETDEWEB)

Frenz, Walter; Ehlenz, Christian [RWTH Aachen (Germany)

2011-07-01

The facilities' security significantly affects the health production of the population and the environmental protection. With the introduction of the Treaty of the European Atomic Energy Community, security aspects were not in the foreground. From today's perspective, the safety aspects were taken into account adequately. The opportunity to adjust the EAG in the framework of the Lisbon Treaty has not been noticed. This is the 54th Declaration to the Final Act of the Intergovernmental Conference which adopted the Lisbon Treaty signed on 13th December, 2007. Till to this date, the factual questions characterized by the risks of use on a broad interpretation of the EAG can be controlled.

Germany and the nuclear non-proliferation; Current situation and prospects; Deutschland und die nukleare Nichtverbreitung; Zwischenbilanz und Ausblick

Energy Technology Data Exchange (ETDEWEB)

Preisinger, J.

1993-07-01

A summary is given of the consequences, both positive and negative, of international non-proliferation policy. The numerous, complex branches and connections of national measures and inter-stake agreements for the peaceful, controlled uses of nuclear technology and related military technologies are expertly described, and assessed on their effectiveness. Weak aspects of the nuclear non-proliferation regime are pointed out and past reforms are illustrated and assessed in the light of recent developments. The interests of the German Federal Republic from the centre of this analysis. The author shows that, after a certain hesitary, German diplomacy has now become active in the establishment of an international non-proliferation regime. He concludes that Germany should take a strong initiative role in maintaining a peaceful international nuclear order. (orig.) [Deutsch] Es wird ein Resuemee der bisherigen Erfolge und Misserfolge internationaler Nichtverbreitungspolitik gezogen. Die komplexen, vielfach veraestelten und verschachtelten nationalen Massnahmen und zwischenstaatlichen Vereinbarungen zur Ueberwachung und friedlichen Zweckbindung von Nukleartechnologie und militaerisch relevanten Anschlusstechnologien werden sachkundig erlaeutert und auf ihre Wirksamkeit ueberprueft. Schwachstellen des nuklearen Nichtverbreitungsregimes werden offengelegt, Reformschritte der vergangenen Jahre werden dargestellt und im Lichte der juengsten Entwicklungen bewertet. Dabei steht die Interessenlage der Bundesrepublik Deutschland im Zentrum der Analyse. Der Autor zeigt, dass die deutsche Diplomatie sich nach einer gewissen Zurueckhaltung schliesslich aktiv in die Gestaltung des internationalen Nichtverbreitungsregimes eingeschaltet hat. Er plaediert fuer eine kraftvolle Initiativrolle Deutschlands zur Erhaltung einer friedlichen internationalen Nuklearordnung. (orig.)

Research program on nuclear technology and nuclear safety; Forschungsprogramm Kerntechnik und Nukleare Sicherheit - Synthesebericht 2009 des BFE-Programmleiters

Energy Technology Data Exchange (ETDEWEB)

Dreier, J.

2010-04-15

This paper elaborated for the Swiss Federal Office of Energy (SFOE) presents the synthesis report for 2009 made by the SFOE's program leader on the research program concerning nuclear technology and nuclear safety. Work carried out, knowledge gained and results obtained in the various areas are reported on. These include projects carried out in the Laboratory for Reactor Physics and System Behaviour LRS, the LTH Thermohydraulics Laboratory, the Laboratory for Nuclear Materials LNM, the Laboratory for Final Storage Safety LES and the Laboratory for Energy Systems Analysis LEA of the Paul Scherrer Institute PSI. Work done in 2009 and results obtained are reported on, including research on transients in Swiss reactors, risk and human reliability. Work on the 'Proteus' research reactor is reported on, as is work done on component safety. International co-operation in the area of serious accidents and the disposal of nuclear wastes is reported on. Future concepts for reactors and plant life management are discussed. The energy business in general is also discussed. Finally, national and international co-operation is noted and work to be done in 2010 is reviewed.

Research program on nuclear technology and nuclear safety - Overview report 2010; Forschungsprogramm Kerntechnik und Nukleare Sicherheit. Ueberblicksbericht 2010

Energy Technology Data Exchange (ETDEWEB)

Cavedon, J.-M.

2011-07-01

This comprehensive report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2010 and the results obtained. The main highlights of the research program, which was co-ordinated by the Paul Scherrer Institute PSI are presented and discussed. Work done within the STARS program on third-generation nuclear power stations is discussed, as is that carried out on probabilistic safety analyses and human reliability. Analysis of activated materials and MOX nuclear fuel assemblies is discussed. A further project examined aging mechanisms in pressure-loaded components. Processes involved in serious accidents and cooling media loss were also examined. Other fluid-dynamic processes involved, along with other factors, are discussed. Work done on the upgrade of the PROTEUS experimental reactor is discussed, as is that done in connection with PSI's hot laboratory and on radiation-induced creeping in structural materials. Fuel cycles and the disposal of radioactive wastes are looked at and the optimisation of safety in sodium-cooled reactors is discussed. Energy economics aspects and national and international co-operation are briefly looked at and work to be done in 2011 is reviewed. A list of current and completed projects completes the report.

Health effects of measures and technologies of the energy transition. The views expressed in this paper need not necessarily coincide with those of the Environment Agency; Gesundheitliche Auswirkungen von Massnahmen und Technologien der Energiewende. Die in diesem Beitrag geaeusserten Ansichten muessen nicht notwendigerweise mit denen des Umweltbundesamtes uebereinstimmen

Energy Technology Data Exchange (ETDEWEB)

Plass, Dietrich [Umweltbundesamt, Berlin (Germany). Fachrichtung: Expositionsschaetzung, gesundheitsbezogene Indikatoren; Conrad, Andre

2017-06-01

A sustainable supply of future generations with energy is not possible on the basis of fossil and nuclear energy sources. With the measures and technologies used, energy transition offers the opportunity to gradually reduce the use of these energy sources and to convert the energy supply system to the use of renewable energies. This chapter has shown that the departure from the existing system can contribute to a significant improvement in the health of the population. However, it is important parallel to the nationwide implementation of measures and technologies of the energy transition to ensure a continuous monitoring of possible health effects in order to be able to respond to potential risks at an early stage and to take adequate measures to reduce them. [German] Eine nachhaltige Versorgung zukuenftiger Generationen mit Energie ist auf Basis fossiler und nuklearer Energiequellen nicht moeglich. Die Energiewende bietet mit den eingesetzten Massnahmen und Technologien die Moeglichkeit, die Nutzung dieser Energiequellen sukzessiv abzubauen und das Energieversorgungssystem auf die Verwendung erneuerbarer Energien umzustellen. Das vorliegende Kapitel hat aufgezeigt, dass die Abkehr vom bestehenden System zu einer deutlichen Verbesserung der Bevoelkerungsgesundheit beitragen kann. Es ist jedoch wichtig, bei der flaechendeckenden Einfuehrung von Massnahmen und Technologien der Energiewende eine kontinuierliche Beobachtung moeglicher Effekte auf die Gesundheit sicherzustellen, um fruehzeitig auf potenzielle Risiken reagieren zu koennen und adaequate Massnahmen zu ihrer Reduktion zu ergreifen.

The nuclear era. From the nuclear fission to the disposal; Das nukleare Zeitalter. Von der Kernspaltung bis zur Entsorgung

Energy Technology Data Exchange (ETDEWEB)

Eidemueller, Dirk

2012-07-01

Nuclear energy is a controverse theme - and the debate between proponents and opponents is often very emotional. by this not only the sober scientific facts but also socially significant points can easily lose sight. These information gaps Dirk Eidemueller will close with his book. He explains the foundations of the atomic force and the risks, which are connected with this: In the uranium mining, in the proliferation of nuclear weapons, but particularly in the operation of nuclear power plants and the disposal of atomic waste, which will us still keep busy for generations.

Consequences of nuclear accidents for human beings and the environment; Auswirkungen nuklearer Unfaelle auf den Menschen und die Umwelt

Energy Technology Data Exchange (ETDEWEB)

Huebner, Felix; Jung, Jennifer Jana; Schultmann, Frank

2017-03-15

In the 1950s and 1960s many countries believed that they could become energy self-efficient with the help of nuclear power plants. For this reason, nuclear energy experienced internationally an enormous upswing during these years. In the following decades, many nuclear power plants were planned and built. Despite a few critics, who drew attention to the dangers of nuclear power use, an end to the upturn was not foreseeable. But in 1979, the nuclear accident in Three Mile Island in Harrisburg (USA) caused international attention and the critics of the nuclear power became stronger. However, many Europeans only were aware of the danger by nuclear power plants when in 1986 the nuclear disaster occurred in the Ukrainian nuclear power plant in Chernobyl. The effects of this nuclear disaster were also felt in Central Europe. Recently, the nuclear disaster at the Fukushima nuclear power plant has prompted a nuclear phase-out in Germany and the rest of the world. This work focuses not on the political implications of these nuclear accidents, but rather on the impacts of nuclear accidents on human beings, animals and the environment. In particular, reports on the incidents in Chernobyl and Fukushima as well as studies on their effects are analysed and summarised.

Nuclear disarmament. Options for the coming non-proliferation treaty surveillance cycle; Nukleare Abruestung. Optionen fuer den kommenden Ueberpruefungszyklus des NVV

Energy Technology Data Exchange (ETDEWEB)

Mueller, Harald

2011-07-01

The report is aimed on the nuclear disarmament discussion with respect to the disagreement of nuclear weapon states and those without nuclear weapons, esp. the non-aligned movement (NAM) concerning the non-proliferation treaty. The report covers the following issues: The role of the non-proliferation treaty, nuclear disarmament in the last surveillance conference 2010, the different disarmament philosophies, the possibilities of bridging the disagreement, further disarmament options for the future non-proliferation treaty surveillance cycle, German options for the future surveillance cycle.

Spectacular energy technology: Panorama-Sauna Holzweiler. KfW funds indoor swimming pools as 'process heat'; Energetisch spektakulaer: Panorama-Sauna Holzweiler. KfW foerdert Schwimmbaeder als 'Prozesswaerme'

Energy Technology Data Exchange (ETDEWEB)

Meissner, Rolf

2008-11-15

The ''Panorama-Sauna'' at Grafschaft is a big indoor swimming pool and Sauna centre in a rural region not far from Cologne and Koblenz. The charm of this spectacular solar project is in its minimalism. Conventional solar thermal power systems, in contrast, tend to be complex and prone to failure. (orig.)

Regulatory oversight report 2007 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2007 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-04-15

This annual report issued by the Swiss Federal Nuclear Inspectorate (HSK) reports on the work carried out by the Inspectorate in 2007. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions and personnel and provides an assessment of operations from the point of view of safety. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management. Finally, the disposal of nuclear wastes and work done in the rock laboratories in Switzerland is commented on.

Regulatory oversight report 2008 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2008 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-04-15

This annual report issued by the Swiss Federal Nuclear Inspectorate (ENSI) reports on the work carried out by the Inspectorate in 2008. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions, personnel and provides an assessment of operations from the safety point of view. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management, earthquake damage analysis and agreements on nuclear safety. The underground disposal of highly-radioactive nuclear wastes and work done in the rock laboratories are discussed, as are proposals for additional nuclear power stations.

Nuclear solid-state physics. Nuclear-physics measureing methods and their applications. 4. upd. ed.; Nukleare Festkoerperphysik. Kernphysikalische Messmethoden und ihre Anwendungen

Energy Technology Data Exchange (ETDEWEB)

Schatz, Guenter; Weidinger, Alois; Deicher, Manfred

2010-07-01

This book is thought as accompanying textbook for a course about nuclear solid-state physics, as book for the preparation of experiments in the physical graduate practicum, and as introducing book in one of the treated fields of research. At each theme theory and measurement technique are presented, measurement results shown, detectors explained, and experimental slopes explained. The text was for the 4th edition completely modernized and revised. Newly included were sections about the radiotracer methods (trace diffusion, photoluminescence, and capacitance-transient spectroscopy with radioactive probes), which were hitherto not presented. In the neutron diffraction the for the application especially important field of the small-angle scattering and the reflectometry were newly included in the book, in the Moessbauer effect the application of the synchrotron radiation for Moessbauer studies is described. Important applications like the magnetic-resonance tomography and the positron-emission tomography are also treated in the new edition.

Radiological and nuclear emergency preparedness and response. How well are we prepared?; Radiologischer und nuklearer Notfallschutz. Wie gut sind wir vorbereitet?

Energy Technology Data Exchange (ETDEWEB)

Geick, Gunther H.G. [Dataport, Altenholz (Germany); Herrmann, Andre R. [HERRMANN Consultant, Basel (Switzerland); Koch, Doris [Ministerium fuer Justiz, Gleichstellung und Integration, Kiel (Germany); Meisenberg, Oliver [Helmholtz Zentrum Muenchen Deutsches Forschungszentrum fuer Gesundheit und Umwelt GmbH, Neuherberg (Germany); Rauber, Dominique [Bundesamt fuer Bevoelkerungsschutz (BABS), Zuerich (CH). Eidgenoessisches Dept. fuer Verteidigung, Bevoelkerungsschutz und Sport (VBS); Stuerm, Rolf P. [SafPro AG, Basel (Switzerland); Weiss, Wolfgang [Bundesamt fuer Strahlenschutz, Salzgitter (Germany); Miska, Horst; Schoenhacker, Stefan

2011-07-01

The contributions to this topic are dealing, in a broad overview, with important aspects of Nuclear Emergency Preparedness and Response, like the influence of the new ICRP recommendations number 103 and number 109 on emergency preparedness and on planning for response, possible problems in installing and operating emergency care centres, experience from exercises as well as the training of response personnel in Austria and Germany. Finally, measures in emergency preparedness with regard to a dirty bomb attack are reported by means of an INEX-4-exercise in Switzerland. (orig.)

Castor-V/21 PWR spent fuel storage cask performance test

International Nuclear Information System (INIS)

Creer, J.M.; Schoonen, D.H.

1986-01-01

Performance testing of a CASTOR-V/21 PWR spent fuel storage cask manufactured by Gesellschaft fur Nuklear Service (GNS) was performed as part of a cooperative program between Virginia Power and the US Department of Energy. The performance test consisted of obtaining cask handling experience and heat transfer, shielding, and limited fuel integrity data. Five heat transfer test runs were performed with 21 Surry reactor spent fuel assemblies generating approximately 28 kW. Test runs were performed vacuum, nitrogen, and helium backfill environments with the cask in both vertical and horizontal orientations. Cask exterior surface gamma and neutron dose rates were measured with the cask fully loaded. Gas samples were obtained at the beginning and end of each run with nitrogen or helium environments to verify fuel integrity. The heat transfer performance of the CASTOR-V/21 cask was exceptionally good. Peak clad temperatures with helium and nitrogen environments with the cask in a vertical orientation and with helium with the cask in a horizontal orientation were less than 380 0 C. Vertical vacuum and horizontal nitrogen test runs resulted in peak clad temperatures over 380 0 , but the temperatures were not excessively high ( 0 C). The shielding performance of the cask met the design goal of less than 200 mrem/hr. Cask surface dose rates of <75 mrem/hr can easily be established with minor gamma shielding design refinements if desired. Gas samples obtained during testing indicated no leaking fuel rods were present in the cask. It was concluded that the cask performed satisfactorily from heat transfer and shielding perspectives

Conditioning of spent fuel for interim and final storage in the pilot conditioning plant (PKA) at Gorleben

International Nuclear Information System (INIS)

Lahr, H.; Willax, H.O.; Spilker, H.

1999-01-01

In 1994, due to the change of the nuclear law in Germany, the concept of direct final disposal for spent fuel was developed as an equivalent alternative to the waste management with reprocessing. Since 1979, tests for the direct final disposal of spent fuel have been conducted in Germany. In 1985, the State and the utilities came to an agreement to develop this concept of waste management to technical maturity. Gesellschaft fuer Nuklear-Service (GNS) was commissioned by the utilities with the following tasks: to develop and test components with regard to conditioning technology, to construct and operate the pilot conditioning plant (PKA), and to develop casks suitable for final disposal. Since 1990, the construction of the PKA has taken place at the Brennelementlager Gorleben site. The PKA has been designed as a multipurpose facility and can thus fulfil various tasks within the framework of the conditioning and management of spent fuel assemblies and radioactive waste. The pilot character of the plant allows for development and testing in the field of spent fuel assembly conditioning. The objectives of the PKA may be summarized as follows: to condition spent fuel assemblies, to reload spent fuel assemblies and waste packages, to condition radioactive waste, and to do maintenance work on transport and storage casks as well as on waste packages. Currently, the buildings of the PKA are constructed and the technical facilities are installed. The plant will be ready for service in the middle of 1999. It is the first plant of its kind in the world. (author)

CASTOR-V/21 PWR spent fuel storage cask performance test

International Nuclear Information System (INIS)

Creer, J.M.; Schoonen, D.H.

1986-01-01

Performance testing of a CASTOR-V/21 PWR spent fuel storage cask manufactured by Gesellschaft fur Nuklear Service (GNS) was performed as part of a cooperative program between Virginia Power and the US Department of Energy. The performance test consisted of obtaining cask handling experience and heat transfer, shielding, and limited fuel integrity data. Five heat transfer test runs were performed with 21 Surry reactor spent fuel assemblies generating approximately 28 kW. Test runs were performed with vacuum, nitrogen, and helium backfills in both vertical and horizontal orientations. Cask exterior surface gamma and neutron dose rates were measured with the cask fully loaded. Gas samples were obtained at the beginning and end of each run with nitrogen or helium backfills to verify fuel integrity. The heat transfer performance of the CASTOR-V/21 cask was exceptionally good. Peak clad temperatures with helium and nitrogen backfills in a vertical orientation and with helium in a horizontal orientation were less than 380 0 C. Vertical vacuum and horizontal nitrogen runs resulted in peak clad temperatures over 380 0 , but the temperatures were not excessively high ( 0 C). The shielding performance of the cask met the design expectation of less than 200 mrem/h. Cask surface dose rates of <75 mrem/h can easily be established with minor gamma shielding design refinements if desired. Gas samples obtained during testing indicated no leaking fuel rods were present in the cask. It was concluded that the cask performed satisfactorily from heat transfer and shielding perspectives

Dry Cask Storage Characterization Project - Phase 1: CASTOR V/21 Cask Opening and Examination

Energy Technology Data Exchange (ETDEWEB)

Bare, Walter Claude; Ebner, Matthias Anthony; Torgerson, Laurence Dale

2001-08-01

This report documents visual examination and testing conducted in 1999 and early 2000 at the Idaho National Engineering and Environmental Laboratory (INEEL) on a Gesellschaft für Nuklear Service (GNS) CASTOR V/21 pressurized water reactor (PWR) spent fuel dry storage cask. The purpose of the examination and testing is to develop a technical basis for renewal of licenses and Certificates of Compliance for dry storage systems for spent nuclear fuel and high-level waste at independent spent fuel storage installation sites. The examination and testing was conducted to assess the condition of the cask internal and external surfaces, cask contents consisting of 21 Westinghouse PWR spent fuel assemblies from Dominion’s (formerly named Virginia Power) Surry Power Station and cask concrete storage pad. The assemblies have been continuously stored in the CASTOR cask since 1985. Cask exterior surface and selected fuel assembly temperatures, and cask surface gamma and neutron dose rates were measured. Cask external/internal surfaces, fuel basket components including accessible weldments, fuel assembly exteriors, and primary lid seals were visually examined. Selected fuel rods were removed from one fuel assembly, visually examined, and then shipped to Argonne National Laboratory for nondestructive, destructive, and mechanical examination. Cask interior crud samples and helium cover gas samples were collected and analyzed. The results of the examination and testing indicate the concrete storage pad, CASTOR V/21 cask, and cask contents exhibited sound structural and seal integrity and that long-term storage has not caused detectable degradation of the spent fuel cladding or the release of gaseous fission products between 1985 and 1999.

Generating electricity and heat from lean gas. Dual fuel engine generates electricity and process heat from cupola furnace gas; Strom und Waerme aus Schwachgas gewinnen. Zuendstrahlmotor erzeugt Strom und Prozesswaerme aus Kupolofengas

Energy Technology Data Exchange (ETDEWEB)

Hirn, Gerhard

2012-07-01

White-hot molten iron flows into the launder. The blast of heat released provides visitors with an impressive demonstration of the amount of energy flowing in foundries. Large volumes of carbon (coke) are used for the melting process in the cupola furnace, whereby a combustible process gas is formed as a by-product. This so-called cupola furnace gas has a low heating value and has previously been completely combusted for generating the hot blast in the cupola furnace's recuperator. However, in this process only around 35 % of the contained energy is used thermally. Now it is possible to utilise the remaining 65 % of the chemically bound energy that was previously not used in most foundries: a modified biogas combined heat and power plant runs with cupola furnace gas (CFG) from the melting furnace. (orig.)

Evaluation of finite element codes for demonstrating the performance of radioactive material packages in hypothetical accident drop scenarios

International Nuclear Information System (INIS)

Tso, C.F.; Hueggenberg, R.

2004-01-01

Drop testing and analysis are the two methods for demonstrating the performance of packages in hypothetical drop accident scenarios. The exact purpose of the tests and the analyses, and the relative prominence of the two in the license application, may depend on the Competent Authority and will vary between countries. The Finite Element Method (FEM) is a powerful analysis tool. A reliable finite element (FE) code when used correctly and appropriately, will allow a package's behaviour to be simulated reliably. With improvements in computing power, and in sophistication and reliability of FE codes, it is likely that FEM calculations will increasingly be used as evidence of drop test performance when seeking Competent Authority approval. What is lacking at the moment, however, is a standardised method of assessing a FE code in order to determine whether it is sufficiently reliable or pessimistic. To this end, the project Evaluation of Codes for Analysing the Drop Test Performance of Radioactive Material Transport Containers, funded by the European Commission Directorate-General XVII (now Directorate-General for Energy and Transport) and jointly performed by Arup and Gesellschaft fuer Nuklear-Behaelter mbH, was carried out in 1998. The work consisted of three components: Survey of existing finite element software, with a view to finding codes that may be capable of analysing drop test performance of radioactive material packages, and to produce an inventory of them. Develop a set of benchmark problems to evaluate software used for analysing the drop test performance of packages. Evaluate the finite element codes by testing them against the benchmarks This paper presents a summary of this work

Evaluation of finite element codes for demonstrating the performance of radioactive material packages in hypothetical accident drop scenarios

Energy Technology Data Exchange (ETDEWEB)

Tso, C.F. [Arup (United Kingdom); Hueggenberg, R. [Gesellschaft fuer Nuklear-Behaelter mbH (Germany)

2004-07-01

Drop testing and analysis are the two methods for demonstrating the performance of packages in hypothetical drop accident scenarios. The exact purpose of the tests and the analyses, and the relative prominence of the two in the license application, may depend on the Competent Authority and will vary between countries. The Finite Element Method (FEM) is a powerful analysis tool. A reliable finite element (FE) code when used correctly and appropriately, will allow a package's behaviour to be simulated reliably. With improvements in computing power, and in sophistication and reliability of FE codes, it is likely that FEM calculations will increasingly be used as evidence of drop test performance when seeking Competent Authority approval. What is lacking at the moment, however, is a standardised method of assessing a FE code in order to determine whether it is sufficiently reliable or pessimistic. To this end, the project Evaluation of Codes for Analysing the Drop Test Performance of Radioactive Material Transport Containers, funded by the European Commission Directorate-General XVII (now Directorate-General for Energy and Transport) and jointly performed by Arup and Gesellschaft fuer Nuklear-Behaelter mbH, was carried out in 1998. The work consisted of three components: Survey of existing finite element software, with a view to finding codes that may be capable of analysing drop test performance of radioactive material packages, and to produce an inventory of them. Develop a set of benchmark problems to evaluate software used for analysing the drop test performance of packages. Evaluate the finite element codes by testing them against the benchmarks This paper presents a summary of this work.

Nuclear waste disposal. A wicked and highly conflict bearing societal problem; Nukleare Entsorgung. Ein ''wicked'' und hoechst konfliktbehaftetes Gesellschaftsproblem

Energy Technology Data Exchange (ETDEWEB)

Brunnengraeber, Achim; Mez, Lutz [Freie Univ. Berlin (Germany). Forschungszentrum fuer Umweltpolitik; Di Nucci, Maria Rosaria; Schreuers, Miranda [Freie Univ. Berlin (Germany)

2012-12-15

The final disposal of nuclear wastes is called ''messy'' or ''wicked'' in the political science literature. The highly complicated problems are characterized by a number of features such as intra- and inter-generational aspects and ethical questions. In the case of stakeholders the differences concern ideologies, interests, merits and preferences that cause conflicts. The search for solutions is complicated due to interacting political, social, ecologic, economic and technical aspects. The concepts ''wicked problems'' and ''multi-level-governance'' are promising approaches to solve the complicated situation.

Loading and transport of high-active waste (HAW) with the TN85 flask in 2008

International Nuclear Information System (INIS)

Rys, Michael; Horn, Thomas; Graf, Wilhelm; Bonface, Jean-Michael

2009-01-01

As a part of the operation of nuclear power plants, it is essential to safely manage the radioactive waste. With new developments in science and technology, it is a dynamic process to adapt procedures, equipment and flasks to be used in the future. This is a task for specialists - a task for GNS Gesellschaft fuer Nuklear-Service mbH and for TN International. Until 1994 reprocessing of spent fuel from German nuclear power plants was mandatory for the Utilities (EVU) in Germany. Basis for the reprocessing was the German Atomic Act. The German Utilities concluded contracts on reprocessing with Compagnie Generale des Matieres Nucleaires (COGEMA, now AREVA NC) in France and British Nuclear Fuels plc (BNFL, now INS) in England. The total amount to be reprocessed comes to 5309 t HM contracted to AREVA NC and 768 t HM contracted to INS. The waste generated from reprocessing - or an equivalent amount of radioactive material - has to be returned to the country of origin. In 1979 already an exchange of notes took place between the German and the French government with the obligation of both sides to enable and support the return of reprocessing residues or equivalents. The return of high-active waste (HAW) from France has started in 1996 with the first attribution of 28 glass canisters (one flask) to German Utilities by AREVA NC. Until 2007, 75 flasks loaded with vitrified residue (VR) canisters have been transported to Gorleben. For these transports CASTOR registered HAW 20/28 CG flasks have been used. This presentation will give some background information about the last HAW transport in 2008 with the new flask generation of the type TN85. It will also describe the assembly of the new flask, the preparation of the flask for the loading campaign as well as the loading procedure. (orig.)

New developments at the INE-Beamline for actinide research at ANKA

Science.gov (United States)

Dardenne, K.; Brendebach, B.; Denecke, M. A.; Liu, X.; Rothe, J.; Vitova, T.

2009-11-01

The INE-Beamline for actinide research at the synchrotron source ANKA is operated by the Institut für Nukleare Entsorgung (INE) at the Forschungszentrum Karlsruhe. Experiments on radioactive samples with activities up to 106 times the limit of exemption inside a safe and flexible double containment concept are possible. One great advantage of the beamline is its close proximity to INE's active laboratories with its equipment for manipulation of actinide materials and state-of-the-art spectroscopic, analytical, and microscopic instrumentation. This constellation is unique in Europe. The INE-Beamline is built primarily to serve INE in-house research associated with safe disposal of high level nuclear waste such as actinide speciation or coordination-, redox-, and geo-chemistry of actinides. A wide energy range from around 2.1 keV to 25 keV covering the K-edges from P to Pd and the L3, L2, and L1 edges for actinides from Th to Cm can be used. The INE-Beamline is optimized for X-ray absorption spectroscopy techniques (XANES/EXAFS), but x-ray fluorescence (XRF) analysis and powder diffraction (XRD) are also possible, as well as surface sensitive measurements in grazing incidence geometry (GI-XAFS). Upgrades of instrumentation and extension of experimental capabilities at the INE-Beamline are driven by user needs. Two of the recent upgrades are presented: 1) installation of a microfocus option for spatially resolved studies (μ-XRF, μ-XANES, μ-XRD) and investigations of small volumes (e.g., heterogeneous natural samples and diamond anvil high pressure cells); 2) construction, and commissioning of a high resolution x-ray emission spectrometer (HRXES); 3) availability of an electrochemical cell for investigation of redox sensitive systems.

Loading and transport of high-active waste (HAW) with the TN85 flask in 2008

Energy Technology Data Exchange (ETDEWEB)

Rys, Michael; Horn, Thomas; Graf, Wilhelm [GNS Gesellschaft fuer Nuklear-Service mbH (Germany); Bonface, Jean-Michael [TN International, Montigny-le-Bretonneux (France)

2009-07-01

As a part of the operation of nuclear power plants, it is essential to safely manage the radioactive waste. With new developments in science and technology, it is a dynamic process to adapt procedures, equipment and flasks to be used in the future. This is a task for specialists - a task for GNS Gesellschaft fuer Nuklear-Service mbH and for TN International. Until 1994 reprocessing of spent fuel from German nuclear power plants was mandatory for the Utilities (EVU) in Germany. Basis for the reprocessing was the German Atomic Act. The German Utilities concluded contracts on reprocessing with Compagnie Generale des Matieres Nucleaires (COGEMA, now AREVA NC) in France and British Nuclear Fuels plc (BNFL, now INS) in England. The total amount to be reprocessed comes to 5309 t HM contracted to AREVA NC and 768 t HM contracted to INS. The waste generated from reprocessing - or an equivalent amount of radioactive material - has to be returned to the country of origin. In 1979 already an exchange of notes took place between the German and the French government with the obligation of both sides to enable and support the return of reprocessing residues or equivalents. The return of high-active waste (HAW) from France has started in 1996 with the first attribution of 28 glass canisters (one flask) to German Utilities by AREVA NC. Until 2007, 75 flasks loaded with vitrified residue (VR) canisters have been transported to Gorleben. For these transports CASTOR {sup registered} HAW 20/28 CG flasks have been used. This presentation will give some background information about the last HAW transport in 2008 with the new flask generation of the type TN85. It will also describe the assembly of the new flask, the preparation of the flask for the loading campaign as well as the loading procedure. (orig.)

Nuclear catastrophes and their consequences. 30 years after Chernobyl, 5 years after Fukushima; Nukleare Katastrophen und ihre Folgen. 30 Jahre nach Tschernobyl, 5 Jahre nach Fukushima

Energy Technology Data Exchange (ETDEWEB)

Liebert, Wolfgang; Gepp, Christian; Reinberger, David (eds.)

2016-07-01

The book on nuclear catastrophes covers the following issues: A historical oversight on nuclear power; two catastrophic reactor accidents: Chernobyl and Fukushima; presentation of important experiences on the radiological consequences of the severe accidents; regulatory reactions in Europe as a consequence of Fukushima; beyond Chernobyl and Fukushima: fundamental problems with nuclear energy.

Heavy concrete shieldings made of recycled radio-active steel

International Nuclear Information System (INIS)

Holland, D.; Quade, U.; Sappok, M.; Heim, H.

1998-01-01

Maintenance and decommissioning of nuclear installations will generate increasing quantities of radioactively contaminated metallic residues. For many years, Siempelkamp has been melting low-level radioactive scrap in order to re-use it for containers of nuclear industry. Another new recycling path has recently been developed by producing steel granules from the melt. These granules are used as replacement for hematite (iron ore) in the production of heavy concrete shieldings. In the CARLA plant (central plant for the recycling of low-level radioactive waste) of Siempelkamp Nuklear- und Umwelttechnik GmbH and Co., the scrap is melted in a medium frequency induction furnace. The liquid iron is poured into a cooling basin through a water jet, which splits the iron into granules. The shape of these granules is determined by various factors, such as water jet speed, pouring rate of the liquid iron and different additives to the melt. In this process, massive spheres with diameters ranging from 1 to 8 mm can be produced which add to the density of heavy concrete elements for optimum shielding. In close cooperation with Boschert, which indeed is an expert for the production of concrete shieldings, a new technology for manufacturing heavy concrete shieldings, containing low-level radioactive steel granules, has been developed. The portion of steel granules in the concrete is approx. 50 weight-%. A concrete density between 2.4 kg/dm 3 and 4.0 kg/dm 3 is available. The compressive strength for the concrete reaches values up to 65 MPa. Different types of Granulate Shielding Casks (GSC) are offered by Siempelkamp. The most famous one is the GSC 200 for 200 1 drums, which has already been qualified for final storage of radioactive wastes at the German Morsleben final repository (ERAM). This newly developed recycling process further increases the quantities of low-level radioactive metallic wastes available for recycling. Expensive storage area can thus be saved respectively

American Prometheus. The Triumph and Tragedy of J. Robert Oppenheimer. Biography; J. Robert Oppenheimer. Die Biographie

Energy Technology Data Exchange (ETDEWEB)

Bird, Kai; Sherwin, Martin J.

2009-07-01

A definitive portrait of legendary scientist J. Robert Oppenheimer, the ''father'' of the atomic bomb, discusses his seminal role in the twentieth-century scientific world, as well as his lesser-known roles as family man, supposed communist, and head of Princeton's Institute for Advanced Studies. ''American Prometheus'' is a rich evocation of America in mid-century and a compelling portrait of scientist J. Robert Oppenheimer, a man shaped by its major events--the Depression, World War II, and the Cold War. (orig.) [German] J. Robert Oppenheimer (1904-1967), der ''Vater der Atombombe'', zaehlt zu den schillerndsten Figuren der juengeren Zeitgeschichte. Fuer ihre glaenzende Biographie des ''amerikanischen Prometheus'' erhielten der Journalist Kai Bird und der Historiker Martin J. Sherwin den Pulitzer-Preis. Exemplarisch lassen sie das Drama eines Forschers lebendig werden, der sich zwischen Erkenntnisdrang und ethischer Verantwortung entscheiden muss. Oppenheimer leitete das streng geheime Manhattan-Projekt in der Wueste von New Mexico, wo am 16. Juli 1945 die erste Atombombe gezuendet wurde. Kurz darauf starben in Hiroshima und Nagasaki mehr als 200 000 Menschen durch die neue ''Wunderwaffe'' - die Menschheit war ins Atomzeitalter eingetreten. Erschuettert von der Zerstoerungskraft seiner Schoepfung, engagierte sich Oppenheimer fortan gegen den Einsatz nuklearer Waffen. Das machte ihn im Amerika der McCarthy-Aera verdaechtig. Er geriet ins Visier des FBI, wurde als Spion der Sowjetunion verleumdet und musste den Staatsdienst quittieren. Sein Privatleben wurde an die Oeffentlichkeit gezerrt, seine Wohnung verwanzt, sein Telefon abgehoert. Erst 1963 rehabilitierte ihn Praesident Kennedy. Ueber dreissig Jahre hinweg haben die Autoren Interviews mit Oppenheimers Angehoerigen, Freunden und Kollegen gefuehrt, FBI-Akten gesichtet, Tonbaender von Reden und Verhoeren

Modelling reactive material transport in the near field of a repository for radioactive waste. Coupling the EMOS near field modules CLAYPOS and LOPOS with thermodynamic equilibrium calculations

International Nuclear Information System (INIS)

Moog, H.C.; Keesmann, S.M.

2007-02-01

This paper reports on the project ''Coupling transport models with thermodynamic equilibrium calculations'' - short title EQLINK, promotion code number 02 E 9723 - in the which the scope for coupling thermodynamic equilibrium model calculations with EMOS was expanded and improved. The first step was to inquire into the current state of research on radiolytic processes. It transpired that there is currently no conclusive description of radiolytic processes. The existing descriptions are too complex and too narrowly geared to specific scenarios to allow a general view on radiolytic processes, which would be a prerequisite for creating suitable long-term geochemical safety analysis modules. It appears that the approximation calculations implemented in EMOS tend to overestimate rather than underestimate radiolytic gas formation. The thermodynamic database which is used at GRS (Society for Plant and Reactor Safety) as a basis for coupled transport calculations has been updated. For this purpose the radionuclide database of the Institut fuer Nukleare Entsorgung (INE = Institute for Nuclear Disposal) was converted to an in-house format which permits creating parameter files for specific requirements. The data of the INE comprise thermodynamic parameters such as equilibrium constants, Gibbs free enthalpies of formation, enthalpies and entropies of formation and Pitzer parameters, which are required for model calculations on high-saline solutions. The database for low-saline solutions which had been developed by PSI/NAGRA for calculations with CLAYPOS was also adopted. Both parameter sets were subjected to test calculations to detect any errors that might have occurred during the data transfer. It is thus now possible to perform coupled transport calculations with the EMOS modules LOPOS and CLAYPOS according to the state of the art of geochemical research. The EQLINK interface which had been developed in an earlier project, titled ''Development of a model for describing the

Most advanced HTP fuel assembly design for EPR

International Nuclear Information System (INIS)

Francillon, Eric; Kiehlmann, Horst-Dieter

2006-01-01

End 2003, the Finnish electricity utility Teollisuuden Voima Oy (TVO) signed the contract for building an EPR in Olkiluoto (Finland). Mid 2004, the French electricity utility EDF selected an EPR to be built in France. In 2005, Framatome ANP, an AREVA and Siemens company, announced that they will be pursuing a design certification in the U.S. The EPR development is based on the latest PWR product lines of former Framatome (N4) and Siemens Nuklear (Konvoi). As an introductory part, different aspects of the EPR core characteristics connected to fuel assembly design are presented. It includes means of ensuring reactivity control like hybrid AIC/B4C control rod absorbers and gadolinium as burnable absorber integrated in fuel rods, and specific options for in-core instrumentation, such as Aeroball type instrumentation. Then the design requirements for the EPR fuel assembly are presented in term of very high burnup capacity, rod cladding and fuel assembly reliability. Framatome ANP fuel assembly product characteristics meeting these requirements are then described. EPR fuel assembly design characteristics benefit from the experience feedback of the latest fuel assembly products designed within Framatome ANP, leading to resistance to assembly deformation, high fuel rod restraint and prevention of handling hazards. EPR fuel assembly design features the best components composing the cornerstones of the upgraded family of fuel assemblies that FRAMATOME ANP proposes today. This family is based on a set of common characteristics and associated features, which include the HMP grid as bottom end spacer, the MONOBLOC guide tube and the Robust FUELGUARD as lower tie plate, the use of the M5 Alloy, as cladding and structure material. This fully re-crystallized, ternary Zr-Nb-O alloy produces radically improved in-reactor corrosion, very low hydrogen uptake and growth and an excellent creep behavior, which are described there. EPR fuel assembly description also includes fuel rod

Institute for Nuclear Waste Disposal. Annual Report 2009

International Nuclear Information System (INIS)

Geckeis, H.; Stumpf, T.

2010-01-01

On October 01, 2009, the Karlsruhe Institute of Technology (KIT) was founded by a merger of Forschungszentrum Karlsruhe and Universitaet Karlsruhe (TH). KIT bundles the missions of both precursory institutions: a university of the state of Baden- Wuerttemberg with teaching and research tasks and a large-scale research institution of the Helmholtz Association conducting program-oriented provident research on behalf of the Federal Republic of Germany. Within these missions, KIT is operating along the three strategic fields of action, research, teaching, and innovation. With about 8000 employees and an annual budget of about EUR 700 million, KIT is one of the largest research and teaching institutions worldwide. It has the potential to assume a top position worldwide in selected fields of research. The objective: KIT will become an institution of excellent research and scientific education, as well as a prominent location of academic life, life-long learning, comprehensive advanced training, unrestricted exchange of know-how and sustainable innovation culture. The largest organizational units of KIT are the KIT Centers. They focus on problems of fundamental importance to the existence and further development of our society or on key issues of basic science. KIT Centers are characterized by the uniqueness of their scientific approach, their strategic objective and mission and by a long-term perspective. The Institut fuer Nukleare Entsorgung, INE, (Institute for Nuclear Waste Disposal) belongs to the KIT Energy Center. The KIT Energy Center comprises some 40 institutes of the Universitaet Karlsruhe (TH) and 18 large institutes of the Forschungszentrum Karlsruhe with, at present, a total of approx. 1100 staff members. The participating institutes and research groups are the operating research units. An interdisciplinary KIT School of Energy establishes ideal framework conditions for teaching. For external partners from industry, the KIT Center develops solutions in

Encapsulation plant at Forsmark

International Nuclear Information System (INIS)

Nystroem, Anders

2007-08-01

SKB has already carried out a preliminary study of an encapsulation plant detached from Clab (Central interim storage for spent fuels). This stand-alone encapsulation plant was named FRINK and its assumed siting was the above-ground portion of the final repository, irrespective of the repository's location. The report previously presented was produced in cooperation with BNFL Engineering Ltd in Manchester and the fuel reception technical solution was examined by Gesellschaft fuer Nuklear-Service mbH (GNS) in Hannover and by Societe Generale pour les Techniques Nouvelles (SGN) in Paris. This report is an update of the earlier preliminary study report and is based on the assumption that the encapsulation plant and also the final repository will be sited in the Forsmark area. SKB's main alternative for siting the encapsulation plant is next to Clab. Planning of this facility is ongoing and technical solutions from the planning work have been incorporated in this report. An encapsulation plant placed in proximity to any final repository in Forsmark forms part of the alternative presentation in the application for permission to construct and operate an installation at Clab. The main technical difference between the planned encapsulation plant at Clab and an encapsulation plant at a final repository at Forsmark is how the fuel is managed and prepared before actual encapsulation. Fuel reception at the encapsulation plant in Forsmark would be dry, i.e. there would be no water-filled pools at the facility. Clab is used for verificatory fuel measurements, sorting and drying of the fuel before transport to Forsmark. This means that Clab will require a measure of rebuilding and supplementary equipment. In purely technical terms, the prospects for building an encapsulation plant sited at Forsmark are good. A description of the advantages and drawbacks of siting the encapsulation plant at Clab as opposed to any final repository at Forsmark is presented in a separate report

Encapsulation plant at Forsmark

Energy Technology Data Exchange (ETDEWEB)

Nystroem, Anders

2007-08-15

SKB has already carried out a preliminary study of an encapsulation plant detached from Clab (Central interim storage for spent fuels). This stand-alone encapsulation plant was named FRINK and its assumed siting was the above-ground portion of the final repository, irrespective of the repository's location. The report previously presented was produced in cooperation with BNFL Engineering Ltd in Manchester and the fuel reception technical solution was examined by Gesellschaft fuer Nuklear-Service mbH (GNS) in Hannover and by Societe Generale pour les Techniques Nouvelles (SGN) in Paris. This report is an update of the earlier preliminary study report and is based on the assumption that the encapsulation plant and also the final repository will be sited in the Forsmark area. SKB's main alternative for siting the encapsulation plant is next to Clab. Planning of this facility is ongoing and technical solutions from the planning work have been incorporated in this report. An encapsulation plant placed in proximity to any final repository in Forsmark forms part of the alternative presentation in the application for permission to construct and operate an installation at Clab. The main technical difference between the planned encapsulation plant at Clab and an encapsulation plant at a final repository at Forsmark is how the fuel is managed and prepared before actual encapsulation. Fuel reception at the encapsulation plant in Forsmark would be dry, i.e. there would be no water-filled pools at the facility. Clab is used for verificatory fuel measurements, sorting and drying of the fuel before transport to Forsmark. This means that Clab will require a measure of rebuilding and supplementary equipment. In purely technical terms, the prospects for building an encapsulation plant sited at Forsmark are good. A description of the advantages and drawbacks of siting the encapsulation plant at Clab as opposed to any final repository at Forsmark is presented in a separate

Dictionary of the energy-producing industry. Nuclear and non-nuclear energy sources. Vol. 1. Fachwoerterbuch zur Energiewirtschaft. Nukleare und nichtnukleare Energietraeger. Bd. 1. Deutsch-Englisch/Englisch-Deutsch

Energy Technology Data Exchange (ETDEWEB)

Mannhardt, K H

1981-01-01

This technical dictionary, compiled in everyday practice, gives an outline of the terminology and phraseology of a modern field of engineering. Users should have some basic knowledge of the English language and also of engineering as well as access to standard-language dictionaries. Core subjects of the dictionary are nuclear power, reactor engineering, fusion technology, solar energy, wind energy, tidal energy, radiation protection, nuclear safety, coal gasification and coal liquefaction, cooperative agreements and managerial problems.

Safety techniques in the change of nuclear systems. Radiation protection at spallation neutron sources and transmutation facilities; Sicherheitstechnik im Wandel Nuklearer Systeme. Strahlenschutz bei Spallationsneutronenquellen und Transmutationsanlagen

Energy Technology Data Exchange (ETDEWEB)

Nuenighoff, Kay

2009-07-01

To push the boundary towards higher neutron fluxes concepts based on spallation reactions have been discussed. Here neutrons are produced by bombarding a heavy metal target (e.g. mercury, tungsten, or tantalum) with high energetic protons. Up to now such facilities could not be realised because of the high power particle accelerators needed. Recent developments of the accelerator technology open the possibility of construction and operating proton accelerators in the MW region. This is demonstrated by construction and commissioning of two MW spallation neutron sources, namely SNS (Oak Ridge, Tennessee, USA) with a power of 1.4 MW and J-PARC (Japan) with 1 MW. The realisation of proton accelerators at this power level will open the way towards energy amplifiers, as proposed e.g. by Carlo Rubbia. Such a facility will not only produce electric power. Furthermore longliving radionuclides can be transmutated into shortlived or even stable nuclides by neutron induced nuclear reactions. A mitigation of the problem of nuclear waste disposal. The above discussed developments prove that accelerators are not only constructed for research, moreover application of these technology became state of the art. With the emergence of particle accelerators in the MW region, radiation protection is confronted with new kind of problems to be solved. Especially the higher kinetic energies of the primary beam particles requires modification and expansion of computer programs well known in nuclear engineering. In contrast to nuclear reactors with kinetic energies up to 2-3 MeV, in spallation reaction secondary particles up to the incident energy in the GeV region will be produced. Problems related to radiation protection have to be considered in an energy range three orders of magnitude higher than known from nuclear reactors. In this thesis existing computer codes are compared and validated with data from selected experiments. Questions concerning radiation protection covers a broad range: production of secondary particles, induced radiotoxicity, energy deposition, and the moderation of neutrons and their transport through neutron guides. All these topics are discussed, and numerical solutions are presented. To answer questions concerning the radiation protection of such facilities complex numerical simulations are mandatory. Especially the strong interest in the field of basic research in cold neutron beams requires not only the study of the interaction of high energetic particles with matter, but furthermore the investigation of the influence of neutron optical phenomenons. The presented numerical methods allow the engineer responsible for radiation protection to analyse radiological hazards during the design phase of a project and the early and cheap implementation of technical solutions improving safety. Quoted as an example spallation neutron sources as well as energy amplifiers are discussed. At the end the philosophy of the safety of high power accelerator driven systems are discussed from the point of view of a safety scientist. (orig.)

Emission control at stationary sources in the Federal Republic of Germany. Vol 1. Sulphur oxide and nitrogen oxide emission control; Massnahmen zur Emissionsminderung bei stationaeren Quellen in der Bundesrepublik Deutschland. Bd. 1. Minderung der SO{sub 2}- und NO{sub x}-Emissionen

Energy Technology Data Exchange (ETDEWEB)

Rentz, O; Schleef, H J; Dorn, R; Sasse, H; Karl, U

1997-05-01

Primaer- und Sekundaermassnahmen in den emissionsrelevanten Industriesektoren fuer SO{sub 2}- und NO{sub x} in Deutschland. Der Bericht gibt einen Ueberblick ueber die Entwicklung der SO{sub 2}- und NO{sub x}-Emissionen in ausgewaehlten europaeischen Laendern waehrend der letzten 20 Jahre und in Europa. Daran schliessen sich aktuelle nationale und europaeische Grenzwerte und Richtlinien zu der SO{sub 2}- und NO{sub x} Emissionen aus stationaeren Quellen an. Der Anwendungsstand von Massnahmen zur Minderung der SO{sub 2}- und NO{sub x}-Emissionen wird fuer jeden relevanten Industriesektor untersucht und primaere Minderungsoptionen beschrieben. Spezielle Prozesseinheiten mit direktem Kontakt von Flamme und Prozessgut werden in den einzelnen Prozessen diskutiert, waehrend externe Verbrennungsprozesse zur ausschliesslichen Bereitstellung von Prozesswaerme und elektrischer Energie sektoruebergreifend in einem separaten Kapitel behandelt werden. Der Bericht schliesst mit einem Ueberblick ueber die zur Verfuegung stehenden sekundaeren Minderungsmassnahmen. Fuer die einzelnen Sektoren werden Beispiele fuer Investitionen und Kosten fuer installierte Minderungstechnologien gegeben, die als einzelfallabhaengig anzusehen sind. Zusaetzlich stellten die Anbieter von Emissionsminderungstechnologien Verfahrensbeschreibungen ihrer Produkte einschliesslich Referenzen zur Verfuegung, die im Bericht enthalten sind. (orig.)

Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment. Danish summary[Denmark]; Dekommissionering af Risoes nukleare anlaeg - vurdering af opgaver og omkostninger. Dansk sammenfatning

Energy Technology Data Exchange (ETDEWEB)

Lauridsen, Kurt

2001-02-01

The report gives a brief description of relevant aspects of the decommissioning of all nuclear facilities at Risoe National Laboratory, including the necessary operations to be performed and the associated costs. Together with a more detailed report, written in English, this report is the result of a project initiated by Risoe in the summer of 2000. The English report has undergone an international review, the results of which are summarised in the present report. (au)

American alliances and nuclear non-proliferation. The end of nuclear weapon activities of US allies; Amerikanische Allianzen und nukleare Nichtverbreitung. Die Beendigung von Kernwaffenaktivitaeten bei Verbuendeten der USA

Energy Technology Data Exchange (ETDEWEB)

Schneider, Jonas

2016-07-01

Jonas Schneider tackles a question that is of great interest both to scholars of nuclear proliferation and to practitioners of nonproliferation diplomacy: Why do some political leaders of U.S. allies agree to abandon their nation's nuclear weapons activities, while others - who are often members of the same allied government and sometimes even of the same political party - steadfastly reject such a course reversal? Our existing stock of theories does not fare well in accounting for this important variation in leaders' attitudes. To solve this puzzle, Schneider develops an innovative theory that draws on the individual status conceptions of allied political leaders. Subsequently, the author undertakes to test his theory using four thoroughly researched case studies, and he derives important lessons for international nonproliferation diplomacy toward the Middle East and Northeast Asia.

The public organization of feelings and the nuclear threat. On the political psychology of war and peace. Oeffentliche Gefuehlsorganisation und nukleare Bedrohung. Zur politischen Psychologie von Krieg und Frieden

Energy Technology Data Exchange (ETDEWEB)

Koenig, H.

1987-07-01

Lasting control of the new world-threatening potential for destruction is only possible if the passionate, instinctive nature of man is reflected on the social and individual level. The instincts and instinctive desires which are suppressed in every human social process emerge in (mostly subconscious) fantasies of total power, which the state makes use of: it does not prevent the injustice fed by instinctive desires but monopolizes it. (orig.).

Behaviour of neutron moderator materials at high temperatures in CASTOR registered -casks: qualification and assessment

International Nuclear Information System (INIS)

Krietsch, T.; Wolff, D.; Knopp, U.; Brocke, H.D.

2004-01-01

The Federal Institute for Materials Research and Testing (BAM) is the responsible German authority for the assessment of mechanical and thermal designs of transport and storage casks for radioactive materials. BAM checks up the proofs of the applicants in their safety reports and assesses the conformity to the Regulations for the Safe Transport of Radioactive Material. One applicant is the Gesellschaft fuer Nuklear-Behaelter mbH (GNB) with a new generation of transport and storage casks of CASTOR registered -design. GNB typically uses ultra high molecular weight Polyethylene (UHMW-PE) for the moderation of free neutrons. Rods made of UHMW-PE are positioned in axial bore holes in the wall of the cask and plates of UHMW-PE are in free spaces between primary and secondary lid and between the bottom of the cask and an outer plate (Figure 1). Because of the heat generated by the radioactive inventory and because of a strained spring at the bottom of every bore hole, UHMW-PE is subjected to permanent thermal and mechanical loads as well as loads from gamma and neutron radiation. UHMW-PE has been used under routine- and normal conditions of transport for maximum temperatures up to 130 C. For new generations of CASTOR registered -design maximum temperatures will be increased up to 160 C. That means a permanent use of UHMW-PE at temperatures within and above the melting region of the crystallites. In this paper, some results of special investigations for the proofs of usability of UHMW-PE at temperatures up to 160 C under real conditions of transport and storage in CASTOR registered -casks are given. For that, investigations on temperature dependent expansion behaviour under laboratory conditions as well as in large scale experiments, especially in the case of multiple heating and cooling, were done. Besides, geometrical creep strength for long-term loading by temperatures and pressures with regard to the chemical and physical stability properties of UHMW-PE above the

National choices in a European perspective. Proceedings of the European Forum 2003

International Nuclear Information System (INIS)

Sido, Bruno; Lamoureux, Francois; ); Herzog, Philippe; ); Barre, Bertrand; Bataille, Christian; Colombani, Pascal; Gonzalez Gomez, Jose Luis; Lescoeur, DBruno; Perez, Serge; Weh, Rudolf; Westerlind, Magnus; Houssin, Didier; Nagashima, Hideo; Pavlopoulos, Panagiotis; Linkohr, Rolf; ); Allemeersch, Antoine; Beveridge, George; Bonnemains, Jacky; Fritschi, Markus; Piguet, Jack-Pierre; Rigny, Paul; Streydio, Jean-Marie; Tallec, Michele; Vasa, Ivo; Pancher, Bertrand

2003-01-01

In 2003, the 'Entretiens europeens' engaged a dialogue between stakeholders of various socio-professional backgrounds from several countries and with the European Commission, in order to compare the selected options of management of radioactive waste and materials and to emphasize the best experiments, which could inspire an innovating European policy in the world. This document is the proceedings of this first European Forum on this topic. Content: 1 - Introduction by Bruno Sido, senator and chairman of the County Council of Haute-Marne; 2 - talk by Francois Lamoureux, General Director of DG TREN, European Commission. 3 - Debate with the audience. 4 - First round table chaired by Philippe Herzog, Member of the European Parliament and President of Confrontations Europe: Is a European directive feasible? Within what time frame? What flexibility is required? What democratic process is needed? With the contributions from: Bertrand Barre, Manager in charge of Scientific Communications (AREVA), Christian Bataille, Member of the French Parliament, author of the 'Bataille Law', Pascal Colombani, Administrator, British Energy (nuclear power producer in UK), Jose Luis Gonzalez Gomez, ENRESA (Spain), Bruno Lescoeur, Director of the Energy sector, EDF, Serge Perez, Trade Unionist, Member of the National Bureau, FNME CGT (France), Rudolf Weh, Head of Department Spent Fuel and Waste Management Services/Interim Storage, GNS Gesellschaft fuer Nuklear-Service mbH (Germany), Magnus Westerlind, Manager Nuclear Security, SKI (Sweden). 5 - Hearing Didier Houssin, Director, Raw Materials and Hydrocarbons, DGEMP. 6 - Interventions of Hideo Nagashima, Executive Director, NUMO (Japan) and of Panagiotis Pavlopoulos, Research Director CERN, Geneva. 7 - Second round table chaired by Rolf Linkohr, Member of the European Parliament and chairman of European Energy Foundation: 'The scientific and social importance of the various options for the management of nuclear waste' With the contributions

Method and apparatus for nuclear logging making use of lithium detectors and equipment for gamma ray stripping; Fremgangsmaate og apparat til nuklear logging med bruk av litiummontasjer og anordning for gammastraalestripping

Energy Technology Data Exchange (ETDEWEB)

Perry, C.A.; Daigle, G.A.; Bruck, W.D. [and others

1998-05-11

The patent deals with a borehole logging tool where a pair of spaced-apart lithium detectors is lowered into a borehole traversing a sursurface formation. The formation is irradiated with bursts of neutrons, and the neutrons returning to the borehole are detected by thermal neutron detectors. The dieaway gamma ray spectra provide information on the formation porosity. A MWD system includes a programmable gain amplifier and gamma ray stripping means. 30 figs.

Deuterium/hydrogen isotope exchange on beryllium and beryllium nitride; Deuterium/Wasserstoff-Isotopenaustausch an Beryllium und Berylliumnitrid

Energy Technology Data Exchange (ETDEWEB)

Dollase, Petra; Eichler, Michael; Koeppen, Martin; Dittmar, Timo; Linsmeier, Christian [Forschungszentrum Juelich GmbH, Institut fuer Energie- und Klimaforschung - Plasmaphysik (Germany)

2016-07-01

untersuchen den Isotopenaustausch von Deuterium und Protium, um nicht mit radioaktivem Tritium arbeiten zu muessen. Der Ionenbeschuss wird dabei mit einer Ionenquelle simuliert. Mit Spannungen bis maximal 5 kV werden Deuterium- und protische Wasserstoffionen in polykristallines Be bzw. Be{sub 3}N{sub 2} implantiert. Die Proben werden dann in-situ mit Roentgenphotoelektronenspektroskopie (XPS) und thermischer Desorptionsspektroskopie (TDS) analysiert. Anschliessend werden unter den gleichen Bedingungen hergestellte Proben ex-situ mittels nuklearer Reaktionsanalyse (NRA) charakterisiert.

The crisis bears the chance. The nuclear conflict with Iran and the impact on the nuclear non-proliferation regime; In der Krise liegt die Chance. Der Atomkonflikt mit Iran und seine Auswirkungen auf das nukleare Nichtverbreitungsregime

Energy Technology Data Exchange (ETDEWEB)

Meier, Oliver

2014-10-15

The contribution on the nuclear conflict with Iran and the impact on the nuclear non-proliferation regime covers the following topics: Iran and the verification of non-nuclear -weapon states, the system of nuclear safeguards, the application of new verification instruments, verification of possible military research and development activities, the limitation of proliferation relevant activities, delivery guarantees as mean for non-proliferation, Iran and the handling of contract violations, graded reactions, political issues, problems of harmonization, capacity and process deficiencies, before the ninth non-proliferation verification conference, approaches for strengthening the non-proliferation regime, recommendation to the German politics.

Examination of imaging detectors for combined radiography procedures in the ACCIS joint project. Automatic cargo container inspection system. Final report; Untersuchung von bildgebenden Detektoren fuer kombinierte Radiographieverfahren im Verbundprojekt ACCIS. Automatisches Cargo-Container Inspektionssystem. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Dangendorf, Volker

2014-06-09

erfordert im Verdachtsfalle aufwendige Nachuntersuchungen. Auf der anderen Seite ist auch der Bildkontrast bei schweren Elementen mit Roentgenmethoden nur gering was z.B. die Identifikation durch von nukleares Schmuggelgut (SNM) wie Pu und.U, die ggf auch noch in einem Behaelter aus Blei zur Tarnung und gemischt mit Waren aus anderen schweren Metallen transportiert werden, sehr schwierig macht. Im Rahmen des ACCIS Verbundprojektes wurde ein neuartiges Inspektionssystem fuer Luftfracht auf der Basis von Neutronen- und Gammastrahlung erforscht. Das Teilprojekt der PTB umfasste innerhalb dieses Rahmens folgende Aufgabenbereiche: 1. Erforschung und Aufbau von Labormustern der bildgebenden Strahlungsdetektoren; 2. Aufbau eines Messplatzes zur Evaluation der Durchleuchtungsmethode an der Beschleunigeranlage der PTB, 3. Mitarbeit bei der Entwicklung eines Konzeptes fuer eine gepulste Strahlungsquelle, insbesondere Aufbau- und Untersuchung des strahlerzeugenden Targets, 4. Ermittlung der strahlenschutzrechtlich relevanten physikalischen und dosimetrischen Kenngroessen, 5. Untersuchung der Bedingungen fuer die Anwendung, Anforderung an einsatzfaehige Anlage, Endnutzerkontakte; 6. Koordination der deutschen Partner, insbesondere Organisation der Projektmeetings der deutschen und der israelischen Partner.

Development of an indoor air quality checklist for risk assessment of indoor air pollutants by semiquantitative score in nonindustrial workplaces

Directory of Open Access Journals (Sweden)

Syazwan AI

2012-04-01

Full Text Available AI Syazwan1, B Mohd Rafee1, Juahir Hafizan2, AZF Azman1, AM Nizar3, Z Izwyn4, AA Muhaimin5, MA Syafiq Yunos6, AR Anita1, J Muhamad Hanafiah1, MS Shaharuddin1, A Mohd Ibthisham7, Mohd Hasmadi Ismail8, MN Mohamad Azhar1, HS Azizan1, I Zulfadhli9, J Othman101Department of Community Health, Faculty of Medicine and Health Sciences, Universiti Putra Malaysia, Selangor, Malaysia; 2Department of Environmental Science, Faculty of Environmental Studies, Universiti Putra Malaysia, Selangor, Malaysia; 3Pharmacology Unit, Department of Human Anatomy, Faculty of Medicine and Health Sciences, Universiti Putra Malaysia, Selangor, Malaysia; 4Department of Therapy and Rehabilitation, Faculty of Health Science and Biomedical Engineering, Universiti Teknologi Malaysia, Johor, Malaysia; 5Department of Environmental Management, Faculty of Environmental Studies, Universiti Putra Malaysia, Selangor, Malaysia; 6Plant Assessment Technology (PAT, Industrial Technology Division (BTI, Malaysian Nuclear Agency (Nuklear Malaysia, Bangi, Kajang, Malaysia; 7Department of Mechanical Engineering, Faculty of Mechanical Engineering, Universiti Teknologi Malaysia, UTM Skudai, Johor, Malaysia; 8Department of Forest Production, Faculty of Forestry, Universiti Putra Malaysia, Selangor, Malaysia; 9Faculty of Built Environment and Architect, Universiti Teknologi Malaysia, Skudai, Johor, Malaysia; 10Department of Counsellor Education and Counselling Psychology (DCECP, Faculty of Educational Studies, Universiti Putra Malaysia, Selangor, MalaysiaBackground: To meet the current diversified health needs in workplaces, especially in nonindustrial workplaces in developing countries, an indoor air quality (IAQ component of a participatory occupational safety and health survey should be included.Objectives: The purpose of this study was to evaluate and suggest a multidisciplinary, integrated IAQ checklist for evaluating the health risk of building occupants. This IAQ checklist proposed to support

Dictionary of the energy-producing industry. Nuclear and non-nuclear energy sources. Vol. 2. Fachwoerterbuch zur Energiewirtschaft. Nukleare und nichtnukleare Energietraeger. - Dictionnaire technique de l'economie energetique. Sources d'energie nucleaire et autre que nucleaire. Bd. 2. Allemand-Francais/Francais-Allemand

Energy Technology Data Exchange (ETDEWEB)

Mannhardt, K H

1981-01-01

This technical dictionary, compiled in everyday practice, gives an outline of the terminology and phraseology of a modern field of engineering. Users should have some basic knowledge of the French language and also of engineering as well as access to standard-language dictionaries. Core subjects of the dictionary are nuclear power, reactor engineering, fusion technology, solar energy, wind energy, tidal energy, radiation protection, nuclear safety, coal gasification and coal liquefaction, cooperative agreements and managerial problems.

Convention on nuclear safety report by the government of the Federal Republic of Germany for the second extraordinary meeting in August 2012; Uebereinkommen ueber nukleare Sicherheit. Bericht der Regierung der Bundesrepublik Deutschland fuer die Zweite ausserordentliche Tagung im August 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-25

The nuclear consequences of the earthquake disaster in Japan represent a profound change for the peaceful use of nuclear power, also in Germany. In the light of these events, the German Federal Government, together with the Prime Ministers of the Laender in which NPPs are operated had reviewed the safety of all German NPPs by the German Reactor Safety Commission in close collaboration with the competent nuclear regulatory authorities of the Laender and, through an Ethics Commission on ''Secure Energy Supply'', also started a dialogue among the German society on the risks involved in the use of nuclear power and on the possibility of an accelerated transition to the age of renewable energies. Taking into account the results of the Reactor Safety Commission and the Ethics Commission on ''Secure Energy Supply'' as well as the absolute priority of nuclear safety, the Federal Government decided to terminate the use of nuclear power at the earliest possible date. The amendments in the Atomic Energy Act that went into force in August 2011 induce the progressive abandonment of electricity generation by NPPs in Germany by the end of 2022 at the latest. Germany took an active part in the assessment of the robustness of the NPPs in Europe (EU stress test) under the leadership of the European Nuclear Safety Regulators Group (ENSREG). The results of these reviews show that the German plants partly have considerable safety margins and that additional precautionary measures have been taken in order to prevent (preventive measures) or limit (mitigative measures) the effects of the beyond-design-basis events considered in the reviews. Based on the results of the plant-specific reviews, the RSK has derived first recommendations for further examinations. Some plant-specific improvement measures are already in implementation or planned. The results of the EU stress test will be taken into account in future RSK recommendations. On behalf of the BMU, the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) prepared an Information Notice on the conclusions drawn from the Fukushima accident for German NPPs. The recommendations also include measures for a further improvement of the control of beyonddesign- basis events. The recommendations essentially concern the electrical energy supply, residual-heat removal, and accident management procedures. As regards emergency preparedness measures, the Federal Environment Ministry has initiated a working group of the Commission on Radiological Protection (in Germany abbreviated as SSK) that carries out a review of the German regulations for emergency preparedness on the basis of the experience feedback from the Fukushima accident. Corresponding changes and measures will be defined once the results are available.

Runtime extension and nuclear safety. On the legal and technological context of the 11th and 12th amendment of the Atomic Energy Act; Laufzeitverlaengerung und nukleare Sicherheit. Zum rechtlichen und technischen Zusammenhang von 11. und 12. AtG Novelle

Energy Technology Data Exchange (ETDEWEB)

Renneberg, Wolfgang [Renneberg Consult UG, Alfter (Germany)

2011-04-15

The 11th and 12 Amendment of the Atomic Energy Act with which on the one hand the runtime is extended and on the other hand the safety requirements have been renormalized, formally are independent legislative projects. Concerning to the contents, the 12th Amendment appears as an essential element for securing the extension of operation periods. At the same time it constitutes censorship in the safety assessment of nuclear power plants which is equivalent to a modification in the existing security philosophy. The relationships allowing this interpretation go beyond purely legal issues. Therefore the contribution under consideration reports on the legal, safety related and safety political genesis of the actual legal situation following the contributions of Rossnagel/Hentschel and Ziehm.

Dictionary of the energy-producing industry. Nuclear and non-nuclear energy sources. Vol. 3. Fachwoerterbuch zur Energiewirtschaft. Nukleare und nichtnukleare Energietraeger. - Diccionario tecnico de terminos de la industria de energia. Recursos energeticos nucleares y no nucleares. Bd. 3. Aleman-Espanol/Espanol-Aleman

Energy Technology Data Exchange (ETDEWEB)

Mannhardt, K H

1981-01-01

This technical dictionary, compiled in everyday practice, gives an outline of the terminology and phraseology of a modern field of engineering. Users should have some basic knowledge of the Spanish language and also of engineering as well as access to standard-language dictionaries. Core subjects of the dictionary are nuclear power, reactor engineering, fusion technology, solar energy, wind energy, tidal energy, radiation protection, nuclear safety, coal gasification and coal liquefaction, cooperative agreements and managerial problems.

Convention on Nuclear Safety - CNS. Report by the government of the Federal Republic of Germany for the seventh review conference in March/April 2017; Uebereinkommen ueber nukleare Sicherheit. Bericht der Regierung der Bundesrepublik Deutschland fuer die Siebte Ueberpruefungstagung im Maerz/April 2017

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-06-22

The CNS (Convention on Nuclear Safety) report by the government of the Federal Republic of Germany for the seventh review conference in March/April 2017 covers the following topics: Summary of the most important results since the sixth review conference: existing nuclear facilities, frame for legislation and execution, licensing system, regulatory authority, governmental organizations, responsibility of the licensee, priority of safety, financing and personnel, human factors, quality assurance, safety assessment, radiation protection, emergency preparedness, site selection for nuclear facilities, design and construction, operation.

Convention on Nuclear Safety - CNS. Report by the government of the Federal Republic of Germany for the sixth review conference in March/April 2014; Uebereinkommen ueber nukleare Sicherheit. Bericht der Regierung der Bundesrepublik Deutschland fuer die Sechste Ueberpruefungstagung im Maerz/April 2014

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-01

The report by the government of the Federal Republic of Germany for the sixth review conference (Convention on Nuclear Safety - CNS) in March/April 2014 covers the following issues: reappraisal of nuclear energy in the Federal Republic of Germany; measures as consequence of the reactor accident in the nuclear power plant Fukushima; safety regulations; execution of the IRRS follow-up mission in Germany; safety management and technical qualification of the occupational personnel; safety surveillance; radiation protection, overview on important safety topics; events and incidents larger INES 0. Assessment of the existing nuclear facilities; progress and changes since 2011; future activities.

Nuclear proliferation in the Near East. What is the reaction of the regional neighbors on Iran's nuclear program? An analysis based on the proliferation debate; Nukleare Proliferation im Nahen Osten. Wie reagieren die regionalen Nachbarn auf Irans Nuklearprogramm? Eine Analyse anhand der Proliferationsdebatte

Energy Technology Data Exchange (ETDEWEB)

Erny, Matthias [Zuericher Hochschule fuer Angewandte Wissenschaften (ZHAW), Winterthur (Switzerland)

2012-07-01

The booklet on the reactions of the neighbor states on Iran's nuclear program covers the following topics: Iran's position in the Near East: historical aspects, Iran's nuclear program. The nuclear proliferation and the theory debate: the role of nuclear weapons in the international policy, proliferation optimism, proliferation pessimism. Analysis of the players and theory criticism: nuclear states (Israel, Pakistan), emerging nuclear states (Saudi Arab, Egypt, Turkey, Syria), states without nuclear weapons (Iraq, Jordan, GCC states); analysis, theory criticism.

Nuclear safety assessment of nuclear power plants and nuclear risk in Eastern Europe and other regions. Scientific-technical cooperation with nuclear regulatory authorities and technical support organizations (TSOs); Einschaetzung der nuklearen Sicherheit von Kernkraftwerken sowie nuklearer Risiken in Osteuropa und anderen Regionen. Wissenschaftlich-technische Zusammenarbeit mit atomrechtlichen Behoerden und deren Sachverstaendigenorganisationen (TSO)

Energy Technology Data Exchange (ETDEWEB)

Wolff, Holger

2014-09-15

The BMUB/BfS project 3611I01512 formed the frame of the GRS for the scientifictechnical cooperation with Technical Support Organisations and Nuclear Regulatory Authorities in the field of nuclear safety of NPPs and for the evaluation of nuclear risks in Eastern Europe and other regions for the period from September 2011 till June 2014. In the present final report main results of the project are described. The project comprised the following technical topics: - Record status of NPP modernisation programs, Monitoring and evaluation of modernisation programs; - Design basis and severe accident analyses for NPP with PWR (WWER-440, WWER-1000); - Cooperation with INSC partner countries on DBA, BDBA and severe accident analyses for WWER plants of generation 3+ and on building NRA and safety evaluation capacities; - Decommissioning of nuclear facilities and disposal of radioactive waste; - Evaluation of new reactor concepts and their safety design; Panels at regulatory level. The work results are preceded by a summary on the activities related to the project management and to the planning of the bilateral work.

Germany without renewables? Electricity costs and security of supply without the supply of renewable energy in 2011-2013. Discussion paper; Deutschland ohne Erneuerbare Energien? Stromkosten und Versorgungssicherheit ohne die Einspeisung Erneuerbarer Energien in den Jahren 2011-2013. Diskussionspapier

Energy Technology Data Exchange (ETDEWEB)

Dillig, Marius; Karl, Juergen

2014-12-15

Reservekraftwerke fuer Systemdienstleistungen (''Regelreserve'') und moegliche zusaetzliche Stromimporte nicht beruecksichtigt. Ein stabiler Netzbetrieb war in diesen Situationen allerdings nur durch die Einspeisung Erneuerbarer Energien sicher gewaehrleistet. Durch den massiven Ausbau Erneuerbarer Energien reduzierten sich also fuer die Letztverbraucher nicht nur die Gesamtkosten des Strombezugs. Erneuerbare Energien erhoehen vor dem Hintergrund reduzierter konventioneller und nuklearer Kraftwerkskapazitaeten auch wesentlich die Versorgungssicherheit am bundesdeutschen Strommarkt.

The nuclear detectives. The international atomic energy agency IAEA is supposed to trace countries that produce or disseminate nuclear materials for nuclear weapons. A team from Juelich is supporting the process; Die Nukleardetektive. Die internationale Atomenergie-Organisation IAEO soll Staaten aufspueren, die heimlich nukleares Material fuer Atomwaffen herstellen oder verbreiten. Ein Juelicher Team unterstuetzt sie dabei

Energy Technology Data Exchange (ETDEWEB)

Frick, Frank

2015-07-01

The Juelich Team is part of the International Standing Advisory Group on Safeguard Implementation that is supposed to find violations of the Non-Proliferation Treaty. Using wipe cloth in nuclear facilities it is possible to find uranium or plutonium containing particles. The study of the isotopic composition of uranium particles allows the identification of the uranium enrichment in the facility. In Juelich reference uranium particles with defined isotopic composition are produced for calibration purposes. The Juelich team supporting IAEA is also developing computer programs for the automatic processing of satellite data with respect to nuclear facilities.

Scientific-technical exchange of experiences between Germany and the GUS, the Baltic and MOE states, and central Asia and other regions. Workshop and establishment of a common knowledge base for nuclear safety and security. Final report; Wissenschaftlich-technischer Erfahrungsaustausch Deutschlands mit der GUS, den Baltischen und den MOE-Staaten sowie Laendern Zentralasiens und anderer Regionen. Arbeitstreffen und Schaffung gemeinsamer Wissensbasen fuer nukleare Sicherheit und Sicherung. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Dabrowski, Anna

2017-03-15

The report on the workshop concerning scientific-technical exchange of experiences between Germany and the GUS, the Baltic and MOE states, and central Asia and other regions includes the following issues: Results an d success of know-how transfer from West to East, topical issues for mutual exchange of experience, scope of the project, concept of the realization of mutual exchange of experiences. The emphasis of the workshop covered the following issues: emergency preparedness, international requirements concerning nuclear safety and radiation protection, transport of radioactive wastes and communication in nuclear technology.

Material modifications in lithium niobate and lithium tantalate crystals by ion irradiation; Materialmodifikationen in Lithiumniobat- und Lithiumtantalat-Kristallen durch Ionenbestrahlung

Energy Technology Data Exchange (ETDEWEB)

Raeth, Niels Lennart

2017-02-17

''. An explanation for the different behavior of the refractive index changes after irradiation of LiNbO{sub 3} and LiTaO{sub 3} is provided by the following model: The refractive index changes caused by effects such as volume increase, change in polar polarizabilities, and decrease of spontaneous polarization partially cancel each other out, so that the change of ordinary and extraordinary refractive index in LiNbO{sub 3} just coincidentally the same amount fails. In LiTaO{sub 3}, the compensating fraction is normally insufficient to cause a positive change in the extraordinary refractive index. [German] Die kuenstlich hergestellten Kristalle Lithiumniobat (LiNbO{sub 3}) und das eng verwandte Lithiumtantalat (LiTaO{sub 3}) sind bewaehrte Ausgangsmaterialien zur Herstellung aktiver und passiver Bauelemente, die Licht fuehren, verstaerken, schalten und verarbeiten koennen. Hierfuer ist es oft notwendig, den Brechungsindex des Substrats gezielt beeinflussen zu koennen, was neben anderer Methoden auch durch Bestrahlung der Materialien mit schnellen leichten Ionen moeglich ist. Im Rahmen dieser Arbeit werden Lithiumniobat- und Lithiumtantalat-Kristalle mit Alphateilchen, {sup 3}He-Ionen, Deuteronen und Protonen bei Projektilenergien von bis zu 14 MeV/Nukleon bestrahlt. Energie und Kristalldicke sind dabei so gewaehlt, dass die Projektile die gesamte Probe durchdringen und nicht implantiert werden. Alle fuer die unerwuenschte, durch die Bestrahlung entstehende, nukleare Aktivierung der Kristalle verantwortlichen Isotope sind relativ kurzlebig und insgesamt nimmt die Aktivierung schnell genug ab, um nach einer Lagerfrist von einigen Tagen bis wenigen Wochen den gefahrlosen Umgang mit den bestrahlten Proben zu ermoeglichen. Die in Lithiumniobat und Lithiumtantalat durch die Bestrahlung mit den verschiedenen Projektilen erzeugten Brechungsindexaenderungen werden interferometrisch bestimmt und koennen durch geeignete Wahl der Probengeometrie auch in Abhaengigkeit von der