[en] No abstract available. Paper not delivered in time

No abstract available

[en] This book gives an introduction into materials science especially for students. It is structured as follows: metallography; iron and steel; nonferrous metals; plastics; and materials testing. (MM)

[en] The Juelich Nuclear Research Centre (KFA) has been involved in development and irradiation testing of fuel and structural materials for high-temperature reactors (HTR) for 25 years. During this time several HTR reactor concepts have been designed and developed employing a variety of fuel element concepts with various fuel operating conditions. Coated particles and fuel element matrix components, as well as the integral fuel elements, have undergone extensive irradiation testing in various material testing reactors (MTR). Since 1962, about 150 irradiation experiments have been performed in the reactors R2-Studsvik, BR2-Mol, HFR-Petten, Siloe-Grenoble and FRJ2-Juelich. Rapid feedback of the results from irradiation testing as an essential part of successful fuel element and material development requires above all short irradiation time and therefore high thermal neutron flux. The tests are carried out in instrumented capsules purged with He/Ne gas simulating HTR nominal and extreme operating conditions, including power and temperature transients. The irradiation temperature can be varied by changing the neutron flux and by changing the purge gas composition and is measured by thermocouples in the specimen or in the surrounding structure. The fission gases produced during irradiation are swept out and analysed for their activity. The amount of the fission gases and the composition indicate the fuel quality. Isothermal irradiations and experiments for the determination of neutron-induced creep have been carried out for graphite as structural material for core and fuel elements. Specimen dimensions and physical properties were measured out-of-pile between the irradiation cycles. The tests were carried out at temperatures between 400 and 1200 deg. C up to a fast neutron fluence of 2x10²⁶m^-2, the typical lifetime conditions of the graphite side reflector in pebble bed cores. (author). 4 refs, 9 figs

No abstract available

[en] The current status of reactor irradiation experiments is presented in tables summarizing the experimental objectives, conditions, and schedule. Currently, the program has one irradiation experiment in reactor and five experiments in the design or construction stages. Postirradiation examination and testing is in progress on ten experiments

[en] As an intense 14-MeV neutron source, a steady-state subignited tokamak plasma is proposed, where a 60-MW neutral beam is injected to sustain a subignited plasma and to drive a plasma current for steady-state operation. Plasma and device parameters are self-consistently designed, taking into account physical (confinement characteristics, beta limit, current drive efficiency, and so on) and engineering (maximum magnetic field strength, blanket/shield thickness, and others) constraints. The result of a comparison between plasmas with A = 2.8 and A = 4 indicates that a large aspect-ratio device is preferable as a neutron source. A surface-averaged 14-MeV neutron flux of ∼ 0.6 MW/m² is achievable with R = 4 to 5 m, A = 4, and B_max= 10 T and is not so sensitive to the major radius. When the maximum magnetic field strength of toroidal field coils is raised to 13 T, a neutron flux more than 1 MW/m² is available with a device with R = 4 m. If the plasma performance is advanced and plasmas with an L-mode enhancement factor f_L of ∼3 and a Troyon coefficient in beta limit g of ∼5 are attainable, a neutron flux of ∼ 1.6 MW/m² is achievable even with a device with R=4 m and B_max = 10 T. These devices seem to be very attractive not only as a neutron source but also as a supplementary device of an ignition-oriented International Thermonuclear Experimental Reactor (ITER) device. 16 refs., 7 figs., 1 tab

[en] Three BNCT facilities were designed in this work: an epithermal facility for a 22 Mwatts-MPR research reactor, and two removable facilities for a 10 Mwatts-MTR type reactor, for thermal and epithermal therapy. Dosimetric and thermal aspects were considered for the design. A characterization of the materials which are usually used to obtain the required neutron spectrum had been done previously. This characterization consisted in a study of the neutrons and photons behavior, and also the behavior of its adjuncts, throw the mentioned materials. Facilities composed by a filter-attenuation section, followed by a collimator-section were designed for both reactors. The filter-section consists in a material block to tune the spectrum, and the collimator-section is a 1m long tube for the MRP, and a 50 cm long cone for the MTR. In the 22 MW reactor, it was obtained a facility of an epithermal neutron intensity of 6.9X10⁸ n/cm² seg, with a treatment time of 1 hour and a dose due to fast neutrons and photons lower than 20 cGy and 1.2 Gy, respectively. For the 10MW reactor, it was designed an epithermal facility which has an epithermal neutron intensity of 1.9X10⁹ n/cm² seg, a treatment time of 22 minutes, and a 25 cGy dose due to fast neutrons and 1.25Gy due to photons. The thermal facility designed for this reactor, has a thermal neutron intensity if 5.4X10⁹n/cm² seg, an irradiation time of 10 minutes, and an absorbed dose lower than 0.5 mGy due to fast neutrons and epithermal neutrons, and lower than 0.4Gy due to photons. (author)

[en] A brief review of physical and production research conducted in Western Europe, USA, Russia and Japan in classical tokamaks with aspect ratio A 2.5-4 and plasma elongated cross section and divertor configuration is provided. It is pointed out that construction of the KTM tokamak in Republic of Kazakhstan in the framework of international cooperation is aimed, above all, at complex solution of materials technology problems.The KTM tokamak basic specifications and performance attributes are given, the main problems within the program of research using the KTM tokamak in thermonuclear materials technology being considered

[en] The article presents information about irradiation basis for radiation material science at the IR-8 reactor. It is shown that the results of neutron-physical, thermophysical and strength calculations allowed justifying the possibility of testing structural materials in IR-8 reactor at given parameters