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[en] Irradiation testing of U-Mo based fuels is the central component of the Reduced Enrichment for Research and Test Reactors (RERTR) program fuel qualification plan. Several RERTR tests have recently been completed or are planned for irradiation in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory in Idaho Falls, ID. Four mini-plate experiments in various stages of completion are described in detail, including the irradiation test design, objectives, and irradiation conditions. Observations made during and after the in-reactor RERTR-7A experiment breach are summarized. The irradiation experiment design and planned irradiation conditions for full-size plate test are described. Progress toward element testing will be reviewed
[en] Interpretation of the post irradiation data of U-Mo/Al dispersion fuel mini plates irradiated in the Advanced Test Reactor to a maximum U-235 burn up of 80% are presented. The analyses addresses fuel swelling and porosity formation as these fuel performance issues relate to fuel fabrication and irradiation parameters. Specifically, mechanisms involved in the formation of porosity observed in the U-Mo/Al interaction phase are discussed and, means of mitigating or eliminating this irradiation phenomenon are offered
[en] In the past years two publications offered the initial points for the assessment of the proliferation resistance of the MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) facility. The first document applied the TOPS methodology (Technological Opportunities to Increase the Resistance of Global Civilian Nuclear Power Systems) both to the MYRRHA facility and to the BR2 reactor, the material testing reactor operating at SCK.CEN. The second paper provided an initial study according to the PR and PP methodology. This article presents an overview of the PR and PP methodology to MYRRHA. Thanks to the deeper level of detail of the design a complete study with this methodology has been performed, to identify the challenges to the system and how the system can respond to them. The misuse threat has been analyzed both for MYRRHA and for the BR2, by applying the PR and PP methodology to both facilities. The comparison carried out with the TOPS methodology considered the diversion threat; therefore this article extends the comparison focusing on the misuse threat. The PR and PP methodology was also used to investigate possible design variations for MYRRHA and make some suggestions to the MYRRHA design team by applying the Safeguards-by-Design concept.
[en] After 50 year long feedback experience on nuclear reactor operations it is legitimate to wonder whether experimental facilities used to support nuclear power programs are still necessary. The various participants of this conference said yes for mainly 4 reasons: -) to validate the extension of the service life of a reactor without putting at risk its high safety standard, -) to give the reactor more flexibility to cope with the power demand, -) to confront the results given by computerized simulations with experimental data, and -) to qualify the nuclear systems of tomorrow. (A.C.)
[en] A key component of the Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) effort is to enhance instrumentation techniques available to users conducting irradiation tests in this unique facility. In particular, development of sensors capable of providing 'real-time' measurements of key irradiation parameters is emphasized because of their potential to offer increased fidelity data and reduced post-test examination costs. This paper describes the strategy for identifying new instrumentation needed for ATR irradiations and the program underway to develop and evaluate new sensors to address these needs. Accomplishments from this program are illustrated by describing several new sensors now available to users of the ATR NSUF. In addition, progress is reported on current research efforts to provide users improved in-pile instrumentation.
[en] The objective of the Reduced Enrichment for Research and Test Reactor program is to enable the conversion of test reactors using fuel containing high-enriched uranium to fuel that employs low-enriched uranium. This paper describes the development of this low-enriched fuel, including fabrication, characterization, and testing of the fuel.
[en] The European Commission agreed to a project to investigate the future European needs in Material Test Reactor (MTR) services. The project was carried out with the contribution of specialists in nuclear reactor materials and irradiation services for industrial, medical and basic research applications. The main conclusions are outlined in this paper. There will be a need for MTR experimental capabilities as long as nuclear power remains an appreciable contributor to the mix of energy production sources. Existing European MTRs have been very effective in providing valuable services both in Europe and worldwide. However, these reactors are ageing and measures should be taken for when the existing European MTRs will cease operation. While it is difficult to provide firm timetables, a new European MTR should be in place in about a decade from now. (author)
[en] The IAEA Nuclear Research Reactor Data Base (RRDB) includes information on 278 (+6 not fully verified) operating research reactors ranging in power from zero to several hundred MW thermal. From these 278 operating research reactors, 200 reactors have a power level below 5 MW, the remaining 78 reactors range from 5 MW up to several 100 MW. The major reactor types with common design are: Siemens Unterrichtsreaktor, Argonaut reactor, Slowpoke reactor, the Miniature neutron source reactor, TRIGA reactors, material testing reactors and High flux reactors. All of them are briefly described and an overview of their possible utilization in physics, chemistry, medicine, academic biology, research, training purposes and industrial application is discussed. Advantages and disadvantages of these low power research reactors are presented. Refs. 15 (nevyjel)