[en] Conceptual design on the IPS, instrumentation and 1/4' Tubing, test fuel supports, test fuel inspection station and inner assembly O-ring replacement was suggested for their improvement. There is a need Jacking bolt on the Top flange for the inner assembly disassemble from the outer assembly and the replacement about the top flange O-ring to metal gasket to secure pressure boundary. Mechanical sealing was suggested instead of brazing. Instrumentation and tubing route should be modified for the reduction of bending and protection from unexpected occasion. Concept on the test fuel inspection station under the consideration of canal dimension. Top flange Bolt handling tool, O-ring replacement platform and O-ring replacement tool was designed for the O-ring replacement at the inner assembly

No abstract available

[en] Specimen irradiation of fissile or non-fissile materials, carried out under circumstances becoming more and more severe and in reactor of increasing flux bas led to an evolution of irradiation rigs. A survey of the problems arising from irradiating under these various circumstances leads to conclude that it is possible to devise one capsule type suitable to every particular case, and that in a wide temperature range. Consequently, once the various irradiation-parameters known, a general method of calculation can be followed so as to determine the various sizes of the parts constituting the capsule. These theoretical calculations might sometimes be corrected through benefits gained from previous irradiations. Similarly, practical experimentation might allow to foresee more handy assembling of the capsule, specimen loading-and unloading being easier at the same time. (author)

[en] In-Pile Loop Safety analysis in integrated with the multipurpose reactor in the case of In-Pile Loop leakage at the core position has been conducted which intended to evaluate the failure of fuel element. By considering design of In-Pile Loop and the highest possibility position of of leakage, the failure of fuel element is emphasized on mechanical aspect. The thermal hydraulic aspect is not taken into account due to the condition that when the leakage occurred the reactor has been in shut down condition. It is determined that the spray attacks the top position of fuel element, and to be calculated the force, of spray that produces 1 cm deflection on the single fuel element. Using that four (4) fuel elements is calculated because in the real condition 4 fuel elements will undergo deflection of 43.8 kg is obtained that producing 1 cm deflection and the force of 1228 kg that causes failure on the bottom of fuel element as shear force is also obtained. Whatever the force, high or low, the damage of fuel element occurred at the bottom part or at the position of grid plate. Therefore there is no damage on the fuel part (uranium meat) and the releasing of radioactive material from fuel plate is not happened

[en] A test facility for research on BWR core statics and dynamics was designed and built in Delft. The loop, DESIRE, consists of a BWR fuel assembly, a riser, condenser and a downcorner section. Freon-12 is used as a coolant. Presently, research on this facility is focused on investigations of the physical aspects of natural-circulation cooling and reactor kinetic stability. To this end, an artificial feedback from in-core void fraction to heating power is being established. The void fraction is determined on a sub-channel level by measuring the transmission of a collimated gamma beam

[en] Compared with steel tubular heat exchanger under same design parameters, plate heat exchanger has high heat transfer coefficient, low cost, compact structure and others outstanding advantages. It is applied to test loop in reactor

[en] Fuel Test Loop (FTL) is designed at the operation condition of power reactor such as high temperature, high pressure and neutron flux etc. As the design of the FTL has been completed, purchasing and manufacturing hardware are underway at present. Installation of the facility is going to do during reactor shutdown period in 2006. This paper describes the preparation of measurement and as-built measurement about in pool structure

[en] In order to carry out the investigations on the short-life Hg isotopes produced by the intermediate energy heavy ion reactions with a natural Pb thick target, on-line molten lead target gas thermochromatography separation apparatus with a rabbit system has been designed. The apparatus could operate automatically for target irradiation by using this apparatus, release and separation as well as collection of Hg-product could be quick performed. The sample of collection is transferred to the low background measuring station without breaking the main vacuum. It can be easily adapted to nuclide of about 20 s or less half-life. Detailed design and constructional features of the apparatus are described

[en] Base on the planning to increase of the working capability of the rabbit system facility, using the design of mentioned portable bridge on material access has been done. Using the designed installation, the transportation of the middle and high active samples from the isotop cell to the scanning room will be easy to be done. The design has been done by using the maximum actual load, and also the chosen steel shape dimension compliance with ASTM standard. The installation required 2 pieces of W 6 x 12 steel beam by 111.82 inches in length, 4 pieces W 6 x 12 steel beam by 47.25'' in length and a piece of steel plate by 111.82'' x 47.25'' x 0.394''. This paper concluded that this design is feasible to be fabricated

[en] Union nut is like a nut functioning to fasten join of two pipe pieces on capsule carrier handling tool of Power Ramp Test Facility (PRTF). For tightening or loosening union nut is needed special equipment which appropriate size in diameter of union nut. Design of union nut spanner on irradiation facility of PRTF is aimed as a reference for a process of spanner fabrication. Design was carried out by spanner shape determination, calculating and technical drawing. From discussion results it can be concluded that spanner design that present in technical drawings can be used as a reference for the spanner fabrication. (author)