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AbstractAbstract
[en] HFR Petten has been operated in 1980 in fulfilment of the 1980/83 JRC Programme Decision. Both reactor operation and utilization data have been met within a few percent of the goals set out in the annual working schedule, in support of a large variety of research programmes. Major improvements to experimental facilities have been introduced during the year and future modernization has been prepared
Primary Subject
Source
1981; 26 p
Record Type
Report
Literature Type
Progress Report
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AbstractAbstract
[en] In this 1981 report, the first chapter introduces the Establishment's activities during the year, followed by brief accounts of the three major programmes assigned to Petten. The scientific work is then described in Chapters II and IV with selected topics being presented in Chapters III and V. The remainder of the report contains charts and tables concerned with staff and budgetary matters and finally a list of technical publications and contributions to conferences made during the year. The year has seen heavy demands being made on the facilities, both the High Flux Reactor and Materials Research installations being fully occupied for most of the time, important results being obtained in both these fields
Primary Subject
Source
1981; 52 p
Record Type
Report
Literature Type
Progress Report
Report Number
Country of publication
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The high flux materials testing reactor has been operated in 1982 within a few percent of the pre-set schedule, attaining 73% overall availability. Its utilization reached another record figure in 20 years: 81% without, 92% with, the low enrichment test elements irradiated during the year
Primary Subject
Source
1983; 29 p; ISBN 92-825-3588-6; 

Record Type
Report
Literature Type
Progress Report
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Country of publication
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INIS IssueINIS Issue
AbstractAbstract
[en] This report reviews work performed in 1982 at the Petten Establishment of the Joint Research Centre in connection with the 1980-83 multiannual programme. It has been prepared with the general reader in mind and discusses some of the highlights of the scientific activities. The report ends with a brief resume of the Establishment's staff and budget and a list of scientific publications made during the year
Original Title
Petten Establishment
Primary Subject
Source
1982; 54 p; ISBN 92-825-3970-9; 

Record Type
Report
Literature Type
Progress Report
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Country of publication
Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Published in summary form only.
Record Type
Journal Article
Journal
Transactions of the American Nuclear Society. Supplement; v. 32(1); p. 56
Country of publication
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Luzginova, N.; Blagoeva, D.; Hegeman, H.; Van der Laan, J.
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France)2011
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France)2011
AbstractAbstract
[en] The text of publication follows: The High Flux Reactor (HFR) in Petten is a powerful multi-purpose research and materials testing reactor operating for about 280 Full Power Days per year. In combination with hot cells facilities, HFR provides irradiation and post-irradiation examination services requested by nuclear energy research and development programs, as well as by industry and research organizations. Using a variety of the custom developed irradiation devices and a large experience in executing irradiation experiments, the HFR is suitable for fuel, materials and components testing for different reactor types. Irradiation experiments carried out at the HFR are mainly focused on the understanding of the irradiation effects on materials; and providing databases for irradiation behavior of materials to feed into safety cases. The irradiation experiments and materials testing at the HFR include the following issues. First, materials irradiation to support the nuclear plant life extensions, for instance, characterization of the reactor pressure vessel stainless steel claddings to insure structural integrity of the vessel, as well as irradiation of the weld material coupons to neutron fluence levels that are representative for Light Water Reactors (LWR) internals applications. Secondly, development and qualification of the structural materials for next generation nuclear fission reactors as well as thermo-nuclear fusion machines. The main areas of interest are in both conventional stainless steel and advanced reduced activation steels and special alloys such as Ni-base alloys. For instance safety-relevant aspects of High Temperature Reactors (HTR) such as the integrity of fuel and structural materials with increasing neutron fluence at typical HTR operating conditions has been recently assessed. Thirdly, support of the fuel safety through several fuel irradiation experiments including testing of pre-irradiated LWR fuel rods containing UO2 or MOX fuel. Fourthly, conduction of the unique surveillance program for the HFR reactor vessel focused on measurements of the materials property degradation in advance of the 'hot' spot vessel areas. (authors)
Primary Subject
Source
2011; 1 p; Fontevraud 7 - Contribution of materials investigations to improve the safety and performance of LWRs; Avignon (France); 26-30 Sep 2010; Available in abstract form only, full text entered in this record
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
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Thijssen, P.J.M.
Netherlands Energy Research Foundation (ECN), Petten (Netherlands)1994
Netherlands Energy Research Foundation (ECN), Petten (Netherlands)1994
AbstractAbstract
[en] The concept of an 'HFR standard core' is frequently used in discussions concerning the characteristics of the HFR core. It turns out more than once that the concept is not very well defined. This report is written to define it properly. (orig.)
Primary Subject
Source
Jun 1994; 17 p
Record Type
Report
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Country of publication
Reference NumberReference Number
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AbstractAbstract
[en] The Institut Max von Laue-Paul Langevin (ILL) was founded by France and the Federal Republic of Germany in 1967. The aim was to build and operate a high flux research reactor devoted to neutron beam research. This was one of the first practical steps towards international collaboration in fields of basic research where neutrons could contribute. The paper illustrates the development of the ILL and its achievements in neutron research. A short description of the reactor, the technical installations and the instruments, some of which are unique, is given. Besides the technical aspects the organization of the scientific utilization of neutron fields and beams is described. The ILL is basically a user institute open to all interested research groups at universities and other research institutions in the participating countries. (author). 3 refs, 8 figs, 2 tabs
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Proceedings series; 629 p; ISBN 92-0-050688-7;
; 1988; p. 3-12; IAEA; Vienna (Austria); International symposium on the utilization of multipurpose research reactors and related international co-operation; Grenoble (France); 19-23 Oct 1987; IAEA-SM--300/100

Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
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Kroeckel, H.
Commission of the European Communities, Brussels (Belgium)1971
Commission of the European Communities, Brussels (Belgium)1971
AbstractAbstract
No abstract available
Primary Subject
Source
1971; 36; Microfiche only.
Record Type
Report
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Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
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Ahlf, J.; Gevers, A.
Commission of the European Communities, Luxembourg (Luxembourg)1989
Commission of the European Communities, Luxembourg (Luxembourg)1989
AbstractAbstract
[en] In 1989 the operation of the High Flux Reactor Petten was carried out as planned. The availability was more than 100% of scheduled operating time. The average occupation of the reactor by experimental devices was 72% of the practical occupation limit. The reactor was utilized for research programmes in support of nuclear fission reactors and thermonuclear fusion, for fundamental research with neutrons and for radioisotope production. General activities in support of running irradiation programmes progressed in the normal way. Development activities addressed upgrading of irradiation devices, neutron radiography and neutron capture therapy
Primary Subject
Secondary Subject
Source
1989; 100 p
Record Type
Report
Literature Type
Progress Report
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Country of publication
Reference NumberReference Number
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INIS IssueINIS Issue
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