Filters
Results 1 - 10 of 123637
Results 1 - 10 of 123637.
Search took: 0.067 seconds
Sort by: date | relevance |
AbstractAbstract
[en] The International Working Group on Water Reactor Fuel Performance and Technology (IWGFPT) recommended holding a Technical Committee Meeting on Water Channel Reactor Fuel including into this category fuels and pressure tubes/fuel channels for Atucha-I and II, BWR, CANDU, FUGEN and RBMK reactors. The IWGFPT considered that even if the characteristics of Atucha, CANDUs, BWRs, FUGEN and RBMKs differ considerably, there are also common features. These features include materials aspects, as well as core, fuel assembly and fuel rod design, and some safety issues. There is also some similarity in fuel power history and operating conditions (Atucha-I and II, FUGEN and RBMK). Experts from 11 countries participated at the meeting and presented papers on technology, performance, safety and design, and materials aspects of fuels and pressure tubes/fuel channels for the above types of water channel reactors
Primary Subject
Secondary Subject
Source
Jan 1998; 217 p; Technical committee meeting on water channel reactor fuels and fuel channels: Design, performance, research and development; Vienna (Austria); 16-19 Dec 1996; ISSN 1011-4289;
; Refs, figs, tabs.

Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ABSTRACTS, COOPERATION, DOCUMENT TYPES, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, GRAPHITE MODERATED REACTORS, HEAVY WATER MODERATED REACTORS, INTERNATIONAL ORGANIZATIONS, MATERIALS, POWER REACTORS, PRESSURE TUBE REACTORS, REACTOR CHANNELS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Grounes, M.; Graeslund, C.; Lysell, G.; Lassing, A.; Unger, T.; Carlsson, M.
Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting
Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting
AbstractAbstract
[en] The different types of BWR fuel R and D programs at Studsvik are discussed. The R2 test reactor, its facilities for irradiation experiments and post-irradiation examinations are described. Reviews are given of some of STUDSVIK's earlier international fuel R and D programs, of STUDSVIK's defect fuel degradation experiments and of the following new upcoming international fuel R and D projects: the DEFEX II, ULTRA-RAMP, SUPER-RAMP III/10 x 10, STEED, Post-DO/DNB and TRANS-RAMP III Projects. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 217 p; ISSN 1011-4289;
; Jan 1998; p. 101-130; Technical committee meeting on water channel reactor fuels and fuel channels: Design, performance, research and development; Vienna (Austria); 16-19 Dec 1996; 49 refs, 12 figs, 2 tabs.

Record Type
Report
Literature Type
Conference
Report Number
Country of publication
COOPERATION, DEVELOPED COUNTRIES, ENRICHED URANIUM REACTORS, EUROPE, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, POOL TYPE REACTORS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SCANDINAVIA, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, WESTERN EUROPE
Publication YearPublication Year
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Khmelevsky, M.; Malakhova, E.; Popov, V.; Troyanov, V.
Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting
Water channel reactor fuels and fuel channels: Design, performance, research and development. Proceedings of a technical committee meeting
AbstractAbstract
[en] The thermal-mechanical pellet and cladding interaction (TM PCI) in RBMK fuel rods leads to cladding deformation under transient operation conditions. This phenomena is practically confirmed by the full scale in-pile experiments and by the operation experience. The significant fuel rod elongation after long-term irradiation under RMBK operation conditions is observed. What are the reasons and mechanism of this phenomenon? Based on the fuel rods behavior during operation, the calculation model of TM PCI and computer code OXPA have been developed by the authors team. It is under Russian regulatory body licensing now. The main ideas and technique of the OXPA code are presented in paper. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 217 p; ISSN 1011-4289;
; Jan 1998; p. 167-177; Technical committee meeting on water channel reactor fuels and fuel channels: Design, performance, research and development; Vienna (Austria); 16-19 Dec 1996; 5 refs, 11 figs, 1 tab.

Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In this paper the current situation of energy consumption in China is provided. Coal-burn as a dominant sector of energy consumption causes heavy burden on transportation and serious environmental pollution. The roles of nuclear energy in the future energy supply are discussed. The situation of nuclear development, especially heating reactor is introduced. (author)
Primary Subject
Secondary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 362 p; ISSN 1011-4289;
; Feb 1998; p. 29-35; Advisory group meetings on introduction of small and medium reactors in developing countries; Rabat (Morocco); 23-27 Oct 1995; 3 refs, 4 figs, 4 tabs.

Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Hart, R.S.
Introduction of small and medium reactors in developing countries. Proceedings of two advisory group meetings
Introduction of small and medium reactors in developing countries. Proceedings of two advisory group meetings
AbstractAbstract
[en] The many and diverse technologies necessary for the design, construction licensing and operation of a nuclear power plant can be efficiently assimilated by a recipient country through an effective technology transfer program supported by the firm long term commitment of both the recipient country organizations and the supplier. AECL's experience with nuclear related technology transfer spans four decades and includes the construction and operation of CANDU plants in five countries and four continents. A sixth country will be added to this list with the start of construction of two CANDU 6 plants in China in early 1997. This background provides the basis for addressing the key factors in the successful transfer of nuclear technology, providing insights into the lessons learned and introducing a framework for success. This paper provides an overview of AECL experience relative to the important factors influencing technology transfer, and reviews specific country experiences. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 362 p; ISSN 1011-4289;
; Feb 1998; p. 117-126; Advisory group meetings on introduction of small and medium reactors in developing countries; Rabat (Morocco); 23-27 Oct 1995

Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Ciocci, F.; Doria, A.; Fascetti, M.; Gallerano, G.P.; Giannessi, L.; Giovenale, E.; Messina, G.; Picardi, L.; Renieri, A.; Ronci, G.; Ronsivalle, C.; Vignati, A.
ENEA, Centro Ricerche Casaccia, Rome (Italy). Dipt. Innovazione
ENEA, Centro Ricerche Casaccia, Rome (Italy). Dipt. Innovazione
AbstractAbstract
[en] The design characteristics of a compact Free Electron Laser (FEL) operating in the far infrared spectral range between 200 and 600 μm are presented in this report. The device can be employed in a fundamental physics experiment to be performed in collaboration with INFN-Trieste and the Paul Sherrer Institute- Villigen. Spectroscopic measurements in the above spectral region will allow one to determine the energy difference between the levels 3D-3P in the μP system with great accuracy
[it]
In questo rapporto vengono presentate le caratteristiche di progetto di un Laser ad Elettroni Liberi (FEL) compatto operante nel lontano infrarosso a lunghezze d'onda comprese tra 200 e 600 μm. Tale laser potra' essere impiegato in un esperimento di fisica fondamentale su idrogeno muonico in collaborazione con INFN-Trieste ed il Paul Sherrer Institute-Villigen. Le misure spettroscopiche nella regione spettrale del lontano infrarosso consentiranno di determinare con grande accuratezza la differenza di energia dei livelli 3D-3P nel sistema μP. Attraverso la misura di questa transizione sara' possibile effettuare un test delle correzioni di Meccanica Quantistica (QED) alle energie di legame, migliorando di un ordine di grandezza l'accuratezza della misura della polarizzazione del vuotoOriginal Title
Stato del progetto FEL per l'esperimeto MUH
Primary Subject
Source
Jan 1999; 93 p; ISSN 1120-558X; 

Record Type
Report
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Full text: A major thrust in recent chemical research has been the development of supramolecular chemistry 1 - broadly the chemistry of large multicomponent molecular assemblies in which the component structural units are held together by either covalent linkages or by a variety of weaker (non-covalent) interactions that include hydrogen bonding, dipole stacking, π-stacking, van der Waals q forces and favourable hydrophobic interactions. Much of the activity in the area has been motivated by the known behaviour of biological molecules (such as enzymes). Thus molecular assemblies are ubiquitous in natural systems but, with a limited number of exceptions, have only recently been the subject of increasing investigation by chemists. A feature of much of this recent work has been its focus on molecular design for achieving complementarity between single molecule hosts and guests. The use of single crystal neutron diffraction coupled with molecular modelling and a range of other techniques to investigate the nature of individual supramolecular systems will be discussed. By way of example, in one such study the supramolecular array formed by co-crystallisation of 1,2- diaminoethane and benzoic acid has been investigated; the system self-assembles into an unusual layered structure composed of two-dimensional hydrogen bonded networks sandwiched between layers of edge-to-face stacked aromatic systems. The number of hydrogen-bond donors and acceptors is balanced in this structure
Source
Australian Institute of Nuclear Science and Engineering, Lucas Heights, NSW (Australia); 89 p; 1998; p. 16; AINSE's 40th anniversary conference; Lucas Heights, NSW (Australia); 2-3 Dec 1998
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Ray, A.S.; Stevens, M.G.; Knight, R.S.; Stevenson, K.; Mapson, C.; Aldridge, L.
AINSE's 40th anniversary conference. Conference handbook
AINSE's 40th anniversary conference. Conference handbook
AbstractAbstract
[en] Full text: Cemented zeolite cured at different temperatures were studied to determine whether or not there significant changes between the retention of caesium or strontium. A 65% pure clinoptilolite zeolite, a 90% pure clinoptilolite zeolite and a synthetic A type zeolite were used in the study. Two different Portland cements were chosen to immobilize the zeolites which were ion exchanged with caesium and strontium prior to immobilisation. The cemented zeolites were cured for 28 days at room temperature, and for 7 days at 70 deg C and 150 deg C. They were then leached in pure water at 25 deg C and 40 deg C for 28 days without replacement of the leachate solutions. Leachate aliquots were collected every 3, 7, 14, 21 and 28 days. Zeolite additions in cements improved the retention of both caesium and strontium the level of retention being dependent on the type of zeolite, the type of cement and the temperature of leaching
Primary Subject
Source
Australian Institute of Nuclear Science and Engineering, Lucas Heights, NSW (Australia); 89 p; 1998; p. 41; AINSE's 40th anniversary conference; Lucas Heights, NSW (Australia); 2-3 Dec 1998
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Smart, R.; Lange, A.; Prince, K.; Gerson, A.
AINSE's 40th anniversary conference. Conference handbook
AINSE's 40th anniversary conference. Conference handbook
AbstractAbstract
[en] We propose a mechanism based on the existing XPS literature data and new secondary ions mass spectroscopy (SIMS) and X-ray absorption fine structure (XAFS) measurements. SIMS measurements demonstrate that the adsorbed Cu is not solely located in sites of low coordination and is spread relatively evenly across the surface of sphalerite particles. XAFS measurements have indicated that the Cu is located in a distorted trigonal planar conformation in both bulk and surface sphalerite sites. The proposed mechanism accounts for the final oxidation states of Cu and S as observed by XPS. In addition the proposed mechanism of activation accounts for the slight shift to a lower oxidation state of bulk Cu as compared to surface adsorbed Cu as observed from the Cu( 1s) binding energies
Source
Australian Institute of Nuclear Science and Engineering, Lucas Heights, NSW (Australia); 89 p; 1998; p. 61; AINSE's 40th anniversary conference; Lucas Heights, NSW (Australia); 2-3 Dec 1998; Extended abstract
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] It is now more than a year since the Federal government announced the decision to replace the HIFAR research reactor. The planned start up date of the replacement reactor is 2005, and HIFAR will continue to operate until that time. It is to be a multipurpose reactor with improved capabilities for neutron beam research and for the production of radioisotopes for pharmaceutical, scientific and industrial use. The neutron beam facilities are intended to cater for Australian scientific needs well into the 21st century. In the first stage of planning, a consultative group was formed, the Beam Facilities Consultative Group (BFCG), to determine the scientific capabilities of the new facility. Then, a beam facilities technical group (BFTG) was formed to prepare the engineering specifications for the tendering process. The group consisted of some members of the BFGC, several scientists and engineers from ANSTO, and scientists from leading neutron scattering centres in Europe, USA and Japan. The BFTG looked in detail at the key components of the facility such as the thermal, cold and hot neutron sources, neutron collimators, neutron beam guides and overall requirements for the neutron guide hall. The report of the BFTG, which was submitted in August, has been incorporated into the specifications for the reactor project. Planning for the initial suite of instruments is now under way. The latest technological advances will be used wherever possible to ensure that world class facilities are constructed. The details of the facility will be presented, highlighting some new technologies which will be used, and indicating the scientific capabilities that are to be developed
Primary Subject
Secondary Subject
Source
Australian Institute of Nuclear Science and Engineering, Lucas Heights, NSW (Australia); 89 p; 1998; p. 63; AINSE's 40th anniversary conference; Lucas Heights, NSW (Australia); 2-3 Dec 1998; Extended abstract
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |