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Boening, K.
International Group On Research Reactors (Germany)2003
International Group On Research Reactors (Germany)2003
AbstractAbstract
[en] Papers presented at this Meting were divided into following sessions: safety, licensing and decommissioning of research and test reactors; new reactor facilities and upgrades of the existing research reactors; optimisation of operation and Utilisation; secondary neutron sources; neutron scattering techniques available at existing reactor facilities
Primary Subject
Source
2003; 346 p; IGORR 9: 9. meeting of the International Group On Research Reactors; Sydney (Australia); 24-28 Mar 2003; Refs, figs, tabs
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Report
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Conference
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INIS IssueINIS Issue
Petry, Winfried, E-mail: wpetry@frm2.tum.de
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
AbstractAbstract
[en] The construction of the new German high flux neutron source FRM-II is finished and FRM-II is waiting for its licence to start nuclear operation. With the beginning of the routine operation 22 instruments will be in action, including 5 irradiation facilities and 17 beam tube instruments, most of them use neutron scattering techniques. Additional instruments are under construction. Some of these instruments are unique, others are expected to be the best of their kind, all instruments are based on innovative techniques. (author)
Primary Subject
Source
Boening, K. (comp.) (Technische Univ. Muenchen (Germany)); International Group On Research Reactors (Germany); 346 p; 2003; [8 p.]; IGORR 9: 9. meeting of the International Group On Research Reactors; Sydney (Australia); 24-28 Mar 2003; refs, 3 figs, 4 tabs
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Report
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Conference
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Cabrillat, J.C.; Maegey, M.; Bourguignon, D.; Miachon, G.; Forestier, F.; Coulon, J.P.; Faury, M.
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
AbstractAbstract
[en] The CABRI reactor operated by CEA at the CADARACHE Nuclear Center in France provided the condition for safety studies on nuclear fuel. Initially designed to support investigations on Fast Reactor fuel, large modifications are underway to provide representative conditions for studies on Light Water Fuel types. A general overview of these modifications, the related safety review and supporting studies are described in the paper. (author)
Primary Subject
Source
Boening, K. (comp.) (Technische Univ. Muenchen (Germany)); International Group On Research Reactors (Germany); 346 p; 2003; [7 p.]; IGORR 9: 9. meeting of the International Group On Research Reactors; Sydney (Australia); 24-28 Mar 2003; 4 refs, 3 figs, 1 tab
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Report
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Conference
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Gautier-Picard, P.
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
AbstractAbstract
[en] CILAS company is the world's leading supplier of complete neutron guides systems. The neutron optics with multilayer coatings produced by CILAS have become an international standard for neutron beam transportation in the modern research institutes. During the last 30 years, CILAS designed, produced and installed more than 5000 meters of guides in many European, American and Asian countries. To reinforce its leadership and presence in neutron research, CILAS acquired the company Grenoble Modular Instruments (GMI), a leading company in high precision mechanics, engineering and manufacturing of spectrometers and scientific equipment for neutron and synchrotron research. (author)
Primary Subject
Secondary Subject
Source
Boening, K. (comp.) (Technische Univ. Muenchen (Germany)); International Group On Research Reactors (Germany); 346 p; 2003; [7 p.]; IGORR 9: 9. meeting of the International Group On Research Reactors; Sydney (Australia); 24-28 Mar 2003; 1 tab
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Report
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Conference
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Willers, A.
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
AbstractAbstract
[en] In 1998, PLG delivered their probabilistic safety assessment of the Australian HIFAR reactor to the Commonwealth government. The study was a 'Level 1+' assessment of the likelihood of reactor core damage together with consideration of the reliability of the containment function. As part of their assessment, PLG made a number of recommendations for improvement in the operation of HIFAR which were adopted by ANSTO. In discussion with the regulator, ARPANSA, ANSTO agreed to update the results of the PSA and extend it to the estimate of risks to offsite persons. This paper considers the actions carried out as a result of their recommendations, the subsequent changes to core damage frequency and the likelihood of core damage together with failure of the containment. It also details the results of the simple Level 2/3 study carried out to conservatively estimate the risks to offsite persons. (author)
Primary Subject
Source
Boening, K. (comp.) (Technische Univ. Muenchen (Germany)); International Group On Research Reactors (Germany); 346 p; 2003; [1 p.]; IGORR 9: 9. meeting of the International Group On Research Reactors; Sydney (Australia); 24-28 Mar 2003
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Report
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Conference
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ACCIDENTS, AUSTRALIAN ORGANIZATIONS, CALCULATION METHODS, ENRICHED URANIUM REACTORS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MATERIALS TESTING REACTORS, NATIONAL ORGANIZATIONS, REACTOR ACCIDENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS
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Miller, R.; Abbate, P.M., E-mail: rmx@ansto.gov.au, E-mail: abbapab@invap.com.ar
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
AbstractAbstract
[en] A contract for the design and construction of the Replacement Research Reactor was signed in July 2000 between ANSTO and INVAP from Argentina. Since then the detailed design has been completed, a construction authorization has been obtained, and construction has commenced. The reactor design embodies modern safety thinking together with innovative solutions to ensure a highly safe and reliable plant. Also significant effort has been placed on providing the facility with diverse and ample facilities to maximize its use for irradiating material for radioisotope production as well as providing high neutron fluxes for neutron beam research. The project management organization and planing is commensurate with the complexity of the project and the number of players involved. (author)
Primary Subject
Source
Boening, K. (comp.) (Technische Univ. Muenchen (Germany)); International Group On Research Reactors (Germany); 346 p; 2003; [8 p.]; IGORR 9: 9. meeting of the International Group On Research Reactors; Sydney (Australia); 24-28 Mar 2003; 2 figs, 2 tabs
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Report
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Conference
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Bitelli, U. d'Utra; Santos, A. dos; Jerez, R.; Diniz, R.; Fanaro, L.C.C.B.; Abe, A.Y.; Moreira, J.M.L.; Fer, N.; Giada, M.R.; Fuga, R., E-mail: ubitelli@ipen.br
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
AbstractAbstract
[en] This paper aims to show the experimental utilization of the IPEN/MB-01 nuclear reactor during the last fourteen years. The IPEN/MB-01 is a zero-power critical assembly specially designed to measure integral and differential reactor physics parameters to validate calculational methodologies and related nuclear data libraries. Experiments involving determination of spectral indices, critical mass, relative abundance of delayed neutrons, the inversion point of the isothermal reactivity coefficient and burnable poison are considered the most important experiments. Current experiments at IPEN/MB-01 reactor are also commented. (author)
Primary Subject
Source
Boening, K. (comp.) (Technische Univ. Muenchen (Germany)); International Group On Research Reactors (Germany); 346 p; 2003; [9 p.]; IGORR 9: 9. meeting of the International Group On Research Reactors; Sydney (Australia); 24-28 Mar 2003; 12 refs, 8 figs, 6 tabs
Record Type
Report
Literature Type
Conference; Numerical Data
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Country of publication
BARYONS, CROSS SECTIONS, DATA, ELEMENTARY PARTICLES, EXPERIMENTAL REACTORS, FERMIONS, FISSION NEUTRONS, HADRONS, INFORMATION, MASS, MATERIALS, NEUTRON ABSORBERS, NEUTRONS, NUCLEAR POISONS, NUCLEONS, NUMERICAL DATA, PHYSICS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, ZERO POWER REACTORS
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AbstractAbstract
[en] A way to increase the cold neutron flux is to cool moderator from where cold neutrons are extracted. Although various kinds of cooling system are considered, the closed thermo-siphon cooling system is adopted in many institutes. The notable feature of this system is to be able to keep the liquid level stable in the moderator cell against thermal disturbances, by using self-regulation, which allows a stable supply of cold neutrons. The main part of the closed thermo-siphon consists of a condenser, a moderator transfer tube and moderator cell, which is called the hydrogen cold system. When an extra heat load is applied to the hydrogen cold system having no flow resistance in a moderator transfer tube, the system pressure rises by evaporation of liquid hydrogen. Then the boiling point of hydrogen rises. The liquefaction capacity of the condenser is increasing with a rise of temperature, because a refrigerating power of the helium refrigerator increases linearly with temperature rise of the system. Therefore, the effect of thermal heat load increase is compensated and cancelled out. The closed thermo-siphon has this feature generally, when the moderator transfer tube is designed to be no flow resistance. The report reviews the concept of self-regulation, and how to design and construct the cold neutron source with self-regulation. (author)
Primary Subject
Source
Boening, K. (comp.) (Technische Univ. Muenchen (Germany)); International Group On Research Reactors (Germany); 346 p; 2003; [7 p.]; IGORR 9: 9. meeting of the International Group On Research Reactors; Sydney (Australia); 24-28 Mar 2003; 11 refs, 6 figs
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Report
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Conference
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Reference NumberReference Number
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Kim, Heonil; Han, Gee Yang, E-mail: hkim@kaeri.re.kr
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
AbstractAbstract
[en] HANARO is an open-tank-in-pool type research reactor. Out of the returning PCS (Primary Cooling System) flow, about 10% flow is directed to the bottom of the reactor pool (90% flow to the core). The flow inside the reactor pool due to this bypass flow is analyzed by a commercial computational fluid dynamics code, CFX-4. The change of the flow pattern inside the reactor pool is also studied including hot water layer (HWL) in the case where hotter bypass flow than the pool is dumped. (author)
Primary Subject
Source
Boening, K. (comp.) (Technische Univ. Muenchen (Germany)); International Group On Research Reactors (Germany); 346 p; 2003; [8 p.]; IGORR 9: 9. meeting of the International Group On Research Reactors; Sydney (Australia); 24-28 Mar 2003; 8 figs
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
COMPUTER CODES, COOLING SYSTEMS, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MATERIALS TESTING REACTORS, MECHANICS, POOL TYPE REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TEST FACILITIES, TEST REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Konoplev, Kir, E-mail: kir@pnpi.spb.ru
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors2003
AbstractAbstract
[en] The construction work at the 100 MW researches reactor PIK in year 2002 was in progress. The main activity was concentrated on mechanical, ventilation and electrical equipment. Some systems and subsystems are under adjustment. Hydraulic driving gear for beam shutters are finished in installation, rinsing, and adjusting. Regulating rods test assembling was done. On the critical assembly the first reactor fueling was tested to evaluate the starting neutron source intensity and a sufficiency of existing control and instrument board. Mainline of the PIK facility design and neutron parameters are presented. (author)
Primary Subject
Source
Boening, K. (comp.) (Technische Univ. Muenchen (Germany)); International Group On Research Reactors (Germany); 346 p; 2003; [8 p.]; IGORR 9: 9. meeting of the International Group On Research Reactors; Sydney (Australia); 24-28 Mar 2003; 4 refs, 7 figs, 2 tabs
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
CONTROL ELEMENTS, CONTROL SYSTEMS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EQUIPMENT, FUELS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, MATERIALS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, THERMAL REACTORS
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