Download or read book Irradiation Testing in Fast Reactors in the United Kingdom written by and published by . This book was released on 1970 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: The criteria established for the successful use of DFR for irradiation purposes and the advantages of using a fast reactor are discussed. Examples are drawn from the PFR program for testing fuel, cladding, pins and assemblies, and from tests in support of thermal systems under development. Lack of instrumentation in the experimental rigs results in particular importance being placed on post-irradiation examination and on interpretation of the data. One advantage of DFR is that experiments may be examined non-destructively and returned to the reactor for further irradiation. An indication is given of the proposed use of PFR for experimental purposes, of how this will differ from the current use of DFR, and of its capabilities. (UK).

Download or read book FAST REACTOR IRRADIATION TESTING PROCEEDINGS OF THE INTERNATIONAL CONFERENCE UNITED KINGDOM ATOMIC ENERGY AUTHORITY written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation Testing Vehicles for Fast Reactors from Open Test Assemblies to Closed Loops written by and published by . This book was released on 2016 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt: A review of irradiation testing vehicle approaches and designs that have been incorporated into past Sodium-Cooled Fast Reactors (SFRs) or envisioned for incorporation has been carried out. The objective is to understand the essential features of the approaches and designs so that they can inform test vehicle designs for a future U.S. Fast Test Reactor. Fast test reactor designs examined include EBR-II, FFTF, JOYO, BOR-60, PHÉNIX, JHR, and MBIR. Previous designers exhibited great ingenuity in overcoming design and operational challenges especially when the original reactor plant's mission changed to an irradiation testing mission as in the EBRII reactor plant. The various irradiation testing vehicles can be categorized as: Uninstrumented open assemblies that fit into core locations; Instrumented open test assemblies that fit into special core locations; Self-contained closed loops; and External closed loops. A special emphasis is devoted to closed loops as they are regarded as a very desirable feature of a future U.S. Fast Test Reactor. Closed loops are an important technology for irradiation of fuels and materials in separate controlled environments. The impact of closed loops on the design of fast reactors is also discussed in this report.

Download or read book Enrico Fermi Reactor Use for Irradiation Testing written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1966 with total page 926 pages. Available in PDF, EPUB and Kindle. Book excerpt: Reviews status of AEC projects.

Download or read book IRRADIATION TESTING NEEDS AND FACILITIES FOR FAST REACTOR FUEL AND MATERIAL DEVELOPMENT written by and published by . This book was released on 1966 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fast reactor irradiation testing written by and published by . This book was released on 1969 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation Experimentation in Fast Reactors written by and published by . This book was released on 1973 with total page 522 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation Technology written by Peter von der Hardt and published by Springer. This book was released on 2011-11-11 with total page 802 pages. Available in PDF, EPUB and Kindle. Book excerpt: The International Topical Meeting on Irradiation Technology took place two the Neutron and its Applications (Cambridge, weeks after the Conference on th U. K.) marking the 50 anniversary of the discovery of the neutron. The application of neutrons from research reactors for materials testing requires a large variety of irradiation devices (vehicles) and their out-of-pile control and recording equipment. The in-pile sections are sophisticated in design and assem bly, expensive, and consumable. There have been only a few international con ferences on irradiation testing, the last one being limited to fast breeder reactor work (Jackson, Wyoming, September 1973). In 1982, however, two conferences picked up similar topics -the ANS Conference on Fast, Thermal, and Fusion Reactor Experiments (Salt Lake City, Utah, April 1982), -the Grenoble meeting (these proceedings). Overlapping has been avoided by putting the accent of the U.S. conference on fast reactor work, and on thermal reactor experiments at Grenoble. Put to gether, both conferences ligned up more than 130 papers in this very specialised field, demonstrating a high level of technological development as opposed to a decreasing number of large materials testing reactors available. The editors wish to acknowledge the flawless organisation of the meeting by CEN de Grenoble and the personal commitment of CEN staff to its success. Special thanks go to F. Merchie andJ.F. Veyrat of the Service des Piles. P. von der Hardt H. R6ttger XIII P. von der Hardt and H. Rottger (eds.), Irradiation Technology, xiii.

Download or read book Status of Fast Reactor Research and Technology Development written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: "Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.

Download or read book Assessment of Available Fast Neutron Irradiation Facilities and the Validation of PLATE 2 0 to Support the Conceptual Design of a Gas Test Loop in the Advanced Test Reactor written by William Frances Skerjanc and published by . This book was released on 2005 with total page 244 pages. Available in PDF, EPUB and Kindle. Book excerpt: Current research and development programs being conducted in the United States for advanced fuels and materials to support the Advanced Fuel Cycle Initiative (AFCI), Generation-IV reactors (GEN-IV), and space nuclear programs require an irradiation testing facility capable of simulating anticipated operating environments. The lack of domestic irradiation facilities to meet these programmatic goals has led to a proposed Gas Test Loop (GTL) for fuel and material irradiation to be installed in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The GTL will utilize highly enriched U2́3Si2́2 fuel plates to increase the fast neutron flux density to simulate actual fast reactor conditions. The INL has chosen the computer code PLATE 2.0 (Plate Lifetime Accurate Thermal Evaluation, version 2.0) to model the steady-state thermal properties of the fuel plates. The INL requires all new computer software used in modeling applications to undergo qualification before it can be used for safety analysis. The qualification plan specified by the INL requires a user's manual be developed for PLATE 2.0 along with verification and validation (V & V) of the output results against benchmark data. This thesis presents a study of foreign and domestic fast neutron irradiation facilities, a description of PLATE 2.0 and its user's manual, and the results from the V & V of PLATE 2.0 for U2́3Si2́2 fuel plates.

Download or read book Handbook of Materials Testing Reactors and Associated Hot Laboratories in the European Community written by Peter von der Hardt and published by Springer. This book was released on 1981 with total page 168 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Advanced Test Reactor Irradiation Capabilities Available as a National Scientific User Facility written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR) is one of the world's premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. The ATR is a very versatile facility with a wide variety of experimental test capabilities for providing the environment needed in an irradiation experiment. These capabilities include simple capsule experiments, instrumented and/or temperature-controlled experiments, and pressurized water loop experiment facilities. Monitoring systems have also been utilized to monitor different parameters such as fission gases for fuel experiments, to measure specimen performance during irradiation. ATR's control system provides a stable axial flux profile throughout each reactor operating cycle, and allows the thermal and fast neutron fluxes to be controlled separately in different sections of the core. The ATR irradiation positions vary in diameter from 16 mm to 127 mm over an active core height of 1.2 m. This paper discusses the different irradiation capabilities with examples of different experiments and the cost/benefit issues related to each capability. The recent designation of ATR as a national scientific user facility will make the ATR much more accessible at very low to no cost for research by universities and possibly commercial entities.

Download or read book Control of Tritium at the Fast Flux Test Facility written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Fast Flux Test Facility (FFTF) is located on the Hanford Site near Richland, Washington, and is operated by the Westinghouse Hanford Company for the US Department of Energy (DOE). The facility features a 400 MW(t) three-loop sodium-cooled, mixed-oxide-fueled reactor that was designed for irradiation testing of fuels and materials to support the commercial development of liquid metal fast reactors. The mission has subsequently been expanded to include a passive safety test program, irradiation of fusion and space reactor materials, and isotope production. The FFTF has been in operation for about 7 yr, which includes over 1600 d of full power operation of the fast test reactor (FTR). Radiological operating experience at the FFTF has been excellent. Collective dose equivalents received by operating personnel have been very low (5 person-rem/yr average). No major contamination problems have been encountered in operating and maintaining the plant, and release of radioactivity to the environment has been well below acceptable limits (Bunch and Prevo 1987). Skin contamination events have averaged less than two per year. There have been no internal depositions. This paper discusses the generation, transport and distribution, and radiological aspects of tritium control at the FFTF. 3 refs., 1 fig., 2 tabs.

Download or read book Testing and Research Capabilities at the Sandia Fast Pulsed Reactor Facility written by and published by . This book was released on 1993 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: A wide variety of space-based system components have been qualified for use through neutron irradiation testing performed at the Sandia Pulsed Reactor (SPR) Facility. The SPR Facility is the operating location for two fast burst reactors, SPR II and SPR III, which have been used to induce neutron and gamma damage in electronic components and other materials for customers in the Department of Energy, Department of Defense, NASA, and the private sector. In addition to the pulse mode of operation, during which peak fluxes of up to lel9 n/cm2-s are achieved, the steady state mode allows for the long term irradiation of components and systems in a fast neutron environment at a flux of up to 5e11 n/cm2-s. The SPR reactors are operated in a 9.2 meter diameter exposure cell, or Kiva, suitable for the irradiation of large test articles external to the reactors. Currently, a new upgraded version of SPR Ill (SPR IIIM) is in fabrication; a unique feature of SPR IIIM is its 19 cm (usable diameter) central irradiation cavity, the largest of any US fast burst reactor. An improved cooling system permits continuous operation at power levels in excess of 20 kW{sub t}. The SPR Facility is also the operating site for a critical assembly which was used to characterize prototypic fuels in arrays appropriate for the Space Nuclear Thermal Propulsion Program. Work continues on use of the facility to design, build, and operate critical assemblies for a diverse customer base.

Download or read book The Advanced Test Reactor Irradiation Facilities and Capabilities written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR) is one of the world's premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. The ATR is a very versatile facility with a wide variety of experimental test capabilities for providing the environment needed in an irradiation experiment. These different capabilities include passive sealed capsule experiments, instrumented and/or temperature-controlled experiments, and pressurized water loop experiment facilities. The ATR has enhanced capabilities in experiment monitoring and control systems for instrumented and/or temperature controlled experiments. The control systems utilize feedback from thermocouples in the experiment to provide a custom blended flowing inert gas mixture to control the temperature in the experiments. Monitoring systems have also been utilized on the exhaust gas lines from the experiment to monitor different parameters, such as fission gases for fuel experiments, during irradiation. ATR's unique control system provides axial flux profiles in the experiments, unperturbed by axially positioned control components, throughout each reactor operating cycle and over the duration of test programs requiring many years of irradiation. The ATR irradiation positions vary in diameter from 1.6 cm (0.625 inches) to 12.7 cm (5.0 inches) over an active core length of 122 cm (48.0 inches). Thermal and fast neutron fluxes can be adjusted radially across the core depending on the needs of individual test programs. This paper will discuss the different irradiation capabilities available and the cost/benefit issues related to each capability. Examples of different experiments will also be discussed to demonstrate the use of the capabilities and facilities at ATR for performing irradiation experiments.

Download or read book Characterization of Nuclear Transmutations in Materials Irradiated Test Facilities written by and published by . This book was released on 1994 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: This study presents a comparison of nuclear transmutation rates for candidate fusion first wall/blanket structural materials in available, fission test reactors with those produced in a typical fusion spectrum. The materials analyzed in this study include a vanadium alloy (V-4Cr-4Ti), a reduced activation martensitic steel (Fe-9Cr-2WVTa), a high conductivity copper alloy (Cu-Cr-Zr), and the SiC compound. The fission irradiation facilities considered include the EBR-II fast reactor, and two high flux mixed spectrum reactors, HFIR (High Flux Irradiation Reactor) and SM-3 (Russian reactor). The transmutation and dpa rates that occur in these test reactors are compared with the calculated transmutation and dpa rates characteristic of a D-T fusion first wall spectrum. In general, past work has shown that the displacement damage produced in these fission reactors can be correlated to displacement damage in a fusion spectrum; however, the generation of helium and hydrogen through threshold reactions [(n, x, [alpha]) and (n, xp)] are much higher in a fusion spectrum. As shown in this study, the compositional changes for several candidate structural materials exposed to a fast fission reactor spectrum are very low, similar to those for a characteristic fusion spectrum. However, the relatively high thermalized spectrum of a mixed spectrum reactor produces transmutation rates quite different from the ones predicted for a fusion reactor, resulting in substantial differences in the final composition of several candidate alloys after relatively short irradiation time.

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 1146 pages. Available in PDF, EPUB and Kindle. Book excerpt: