Relevant bibliographies by topics / Halden Reactor Project

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  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Halden Reactor Project'

Author: Grafiati
Published: 4 June 2021
Last updated: 15 February 2022

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Journal articles on the topic "Halden Reactor Project"

1

Vitanza, Carlo. "Overview of the OECD–Halden reactor project." Nuclear Engineering and Design 207, no. 2 (2001): 207–21. http://dx.doi.org/10.1016/s0029-5493(00)00384-8.

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2

Holmstroem, Conny O., and Mark Green. "Human Factors Research at the OECD Halden Reactor Project into the 21st Century." Proceedings of the Human Factors and Ergonomics Society Annual Meeting 44, no. 22 (2000): 803–6. http://dx.doi.org/10.1177/154193120004402280.

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The OECD Halden Reactor Project is a joint undertaking of national nuclear organisations from 20 countries, who together sponsor a research programme under the auspices of the OECD - Nuclear Energy Agency. One of the Projects important research areas addresses human factors in control room design and operation. The simulator-based Halden Man-Machine Laboratory (HAMMLAB) has, since its establishment in 1983, been the main facility for conducting research in this area. It's objective is to provide knowledge for improving today's control rooms, through the introduction and evaluation of computer-
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Solstad, Steinar, and Rudi Van Nieuwenhove. "Instrument Capabilities and Developments at the Halden Reactor Project." Nuclear Technology 173, no. 1 (2011): 78–85. http://dx.doi.org/10.13182/nt11-a11486.

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4

Endestad, Tor, Conny B. O. Holmstroem, and Frode S. Volden. "Effects of Using a Diagnostic Rule-Based Expert System Developed for the Nuclear Industry." Proceedings of the Human Factors Society Annual Meeting 36, no. 16 (1992): 1200–1204. http://dx.doi.org/10.1177/154193129203601604.

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This experiment, conducted at the OECD Halden Reactor Project, Halden, Norway in the spring 1991, aimed to assess the effect on nuclear power plant operators diagnostic behaviour when using a rule based diagnostic expert system. The rule based expert system used in the experiment is called DISKET (Diagnosis System Using Knowledge Engineering Technique) and was originally developed by the Japan Atomic Energy Research Institute (JAERI). The experiment was performed in the Halden man-machine laboratory using a full scope pressurized water reactor simulator. Operator performance in terms of qualit
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Karlsen, T. M. "Achievements and further plans for the OECD Halden reactor project materials programme." Nuclear Engineering and Design 207, no. 2 (2001): 199–206. http://dx.doi.org/10.1016/s0029-5493(00)00383-6.

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Wiesenack, Wolfgang, and Terje Tverberg. "The OECD Halden reactor project fuels testing programme: methods, selected results and plans." Nuclear Engineering and Design 207, no. 2 (2001): 189–97. http://dx.doi.org/10.1016/s0029-5493(00)00385-x.

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Iwai, T., S. Souzawa, S. Niyata, H. Sakai, and A. Sakakura. "Results of eddy current test for second round robin by Halden reactor project." NDT International 22, no. 3 (1989): 185. http://dx.doi.org/10.1016/0308-9126(89)90141-7.

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Wiesenack, W. "Review of Halden reactor project high burnup fuel data that can be used in safety analyses." Nuclear Engineering and Design 172, no. 1-2 (1997): 83–92. http://dx.doi.org/10.1016/s0029-5493(97)00056-3.

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Kim, Inn Seock, Rolf-Einar Grini, and Svein Nilsen. "Implementation of an integrated on-line process surveillance and diagnostic system at the Halden reactor project: MOAS." Annals of Nuclear Energy 28, no. 10 (2001): 967–82. http://dx.doi.org/10.1016/s0306-4549(00)00101-8.

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10

Holcombe, Scott, Staffan Jacobsson Svärd, and Lars Hallstadius. "A Novel gamma emission tomography instrument for enhanced fuel characterization capabilities within the OECD Halden Reactor Project." Annals of Nuclear Energy 85 (November 2015): 837–45. http://dx.doi.org/10.1016/j.anucene.2015.06.043.

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Dissertations / Theses on the topic "Halden Reactor Project"

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Kwok, Jordanna. "Ecological Interface Design for Turbine Secondary Systems in a Nuclear Power Plant: Effects on Operator Situation Awareness." Thesis, 2007. http://hdl.handle.net/10012/2987.

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Investigations into past accidents at nuclear power generating facilities such as that of Three Mile Island have identified human factors as one of the foremost critical aspects in plant safety. Errors resulting from limitations in human information processing are of particular concern for human-machine interfaces (HMI) in plant control rooms. This project examines the application of Ecological Interface Design (EID) in HMI information displays and the effects on operator situation awareness (SA) for turbine secondary systems based on the Swedish Forsmark 3 boiling-water reactor nuclear power
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Books on the topic "Halden Reactor Project"

1

Kennedy, W. G. Lessons learned in process control at the Halden Reactor Project. Office of Nuclear Reactor Regulation ; Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

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Kennedy, W. G. Lessons learned in process control at the Halden Reactor Project. Office of Nuclear Reactor Regulation ; Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

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3

Turnbull, J. Anthony. Review of nuclear fuel experimental data: Fuel behaviour data available from IFE-OCDE Halden Project for development and validation of computer codes. Nuclear Energy Agency, Organisation for Economic Co-operation and Development, 1995.

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4

Camm, Frank A. Reaction to DRI critique of unpublished Rand working draft, Projected use, emissions, and banks of potential ozone-depleting substances. Rand, 1986.

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5

Project, OECD Halden Reactor, ed. OECD Halden Reactor Project, 1958-1988. The Project, 1988.

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Book chapters on the topic "Halden Reactor Project"

1

Sivertsen, Terje, and Fridtjov Øwre. "Research on Software Systems Dependability at the OECD Halden Reactor Project." In Progress of Nuclear Safety for Symbiosis and Sustainability. Springer Japan, 2014. http://dx.doi.org/10.1007/978-4-431-54610-8_30.

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2

Hallonsten, Olof, Hjalmar Eriksson, and August Collsiöö. "The role of research infrastructures in innovation systems: The case of Swedish participation in the Halden Reactor Project." In Big Science and Research Infrastructures in Europe. Edward Elgar Publishing, 2020. http://dx.doi.org/10.4337/9781839100017.00014.

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3

Bye, Andreas, Øivind Berg, and Fridtjov Øwre. "Operator support systems for status identification and alarm processing at the OECD Halden Reactor Project— experiences and perspective for future development." In Human Factors in Alarm Design. Taylor & Francis, 1994. http://dx.doi.org/10.1201/9780203481714.ch9.

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Conference papers on the topic "Halden Reactor Project"

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Green, M. "Human machine interaction research at the OECD Halden Reactor Project." In International Conference on People in Control (Human Interfaces in Control Rooms, Cockpits and Command Centres). IEE, 1999. http://dx.doi.org/10.1049/cp:19990215.

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Březina, Martin, Jana Petzová, Ľudovít Kupča, and Michal Kapusňák. "Utilization of SPT Techniques for Evaluation of Changes in the Properties of the VVER-440 Reactor Pressure Vessel Steels After Their Irradiation in the Research and Power Reactors." In ASME 2015 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/pvp2015-45528.

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The paper describes the testing procedures and the basic results of the evaluation of the Small Punch Test (SPT) specimens after their irradiation in the Halden reactor in Norway. The SPT technique was used for estimation of basic mechanical properties as ultimate tensile strength and yield stress of the tested materials as well as the Fracture Appearance Transition Temperature (FATT). The main aim of the work was to compare the SPT results obtained from the surveillance specimen programs implemented in the Slovak power reactors with the SPT results from the specimens irradiated in the researc
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Matsuzawa, Hiroshi. "Prediction of Radiation Embrittlement for Highly Irradiated Reactor Pressure Vessel Steels." In ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-78096.

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There are 53 (fifty-three) nuclear power plants (both PWR and BWR type) are now under operating in Japan, and the oldest plant has been operating more than thirty years. These plants will be operated until sixty years for operation periods, and will be verified the integrity for assessment of nuclear plants for every ten years in Japan. Reactor Pressure Vessels (RPVs) are required to evaluate the reduction of fracture toughness and the increase of the reference temperature in the transition region. As the operating period will be longer, the prediction for these material properties will be mor
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Toman, Gary J., and Paolo F. Fantoni. "Cable Aging Assessment and Condition Monitoring Using Line Resonance Analysis (LIRA)." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48523.

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This paper describes a method for cable system condition monitoring, developed at the IFE Halden Reactor Project, which is based on Frequency Domain Reflectometry. This method resulted in the development of a system called LIRA (LIne Resonance Analysis), which can be used on-line to detect local or global changes in the cable electrical parameters as a consequence of insulation faults or degradation. This paper presents some results achieved in field experiments on signal cables for nuclear installations, in USA and Europe.
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Fantoni, Paolo F. "Condition Monitoring of Electrical Cables Using Line Resonance Analysis (LIRA)." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75833.

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This paper describes a method for cable system condition monitoring, developed initially at the IFE Halden Reactor Project and then further developed at Wirescan AS, which is based on transmission line theory and resonance analysis. This method resulted in the development of a system called LIRA (LIne Resonance Analysis), which can be used on-line to detect local or global changes in the cable electrical parameters as a consequence of insulation faults or degradation. This paper presents the latest results achieved in field experiments on signal and power cables.
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O’Donnell, William J., Amy B. Hull, and Shah Malik. "Historical Context of Elevated Temperature Structural Integrity for Next Generation Plants: Regulatory Safety Issues in Structural Design Criteria of ASME Section III Subsection NH." In ASME 2008 Pressure Vessels and Piping Conference. ASMEDC, 2008. http://dx.doi.org/10.1115/pvp2008-61870.

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In 2006, ASME and DOE signed a cooperative agreement to update and expand appropriate materials, construction and design codes for application in future Generation IV nuclear reactor systems that operate at elevated temperatures. The second task in this ASME/DOE Gen-IV Materials Project was to identify issues relevant to ASME Section III, Subsection NH, and related Code Cases that must be resolved for licensing purposes for VHTGRs (Very High Temperature Gas Reactor concepts such as those of PBMR, Areva, and GA); and to identify the material models, design criteria, and analysis methods that ne
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LaGrange, Jay W., and William F. Smith. "Non Flow-Through (NFT), Advanced Product Water Removal (APWR), Low Temperature PEM Fuel Cell With Reduced Balance of Plant for Air-Independent Applications." In ASME 2016 14th International Conference on Fuel Cell Science, Engineering and Technology collocated with the ASME 2016 Power Conference and the ASME 2016 10th International Conference on Energy Sustainability. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/fuelcell2016-59322.

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Recent developments in applications such as Pulsed Power, Space, High Altitude Long Endurance (HALE) aircraft and underwater vehicles have created interest in the application of air-independent fuel cells. The attraction for such systems has been the potential for high performance, long life and high energy density allowing for extended mission operations and simple recharge. A limitation of such systems, to date, has been the relatively complicated balance of plant required for system operation. This typically requires circulation of one or both reactants to remove product water and distribut
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Reports on the topic "Halden Reactor Project"

1

Kennedy, W. Lessons learned in process control at the Halden Reactor Project. Office of Scientific and Technical Information (OSTI), 1989. http://dx.doi.org/10.2172/5156552.

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2

Wiesenack, W. Review of Halden Reactor Project high burnup fuel data that can be used in safety analyses. Office of Scientific and Technical Information (OSTI), 1996. http://dx.doi.org/10.2172/269710.

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