No abstract available

[en] The Kartini reactor reached the first criticality on January 25, 1979. In the first three years, the reactor power is limited up to 50 kW thermal power and on July 1, 1982 has been increased to 100 kW. It has been used as experiments facility by researcher of Atomic Energy National Agency and students of the Universities. Three beam tubes used as experiments facilities, the first, is used as a neutron source for H₂O-Natural Uranium Subcritical Assembly, the second, is developed for neutron radiography facility and the third, is used for gamma radiography facility. The other facilities are rotary rack and two pneumatic transfer systems, one for delayed neutron counting system and the other for the new Neutron Activation Analysis (NAA) facility. The rotary rack used for isotope production for NAA purpose (for long time irradiation), the delayed neutron counting system used for analysis the Uranium contents of the ores and the new NAA is provided for short live elements analysis. In the last three years the Reactor Division has a joint use program with the Nuclear Component and Engineering Center in research reactor instrumentation and control development. (author)

No abstract available

[en] Beginning in 1994, a total of 3 (three) workshops ('The Utilization of Research Reactors-Neutron Scattering') have been held yearly in Jakarta. Back in December 1994, a joint research collaboration on the subject of superionic conductors between PNRI and BATAN was proposed and approved by the steering committee. The two principal scientists were V.S. Calix (PNRI) and AK Jahja (BATAN). The general arrangement was that PNRI is responsible for the sample preparation and the preliminary studies on the samples' physical properties (e.g., x-ray studies, DSC thermal measurements and frequency -dependent resistivity studies), whereas BATAN is responsible for structural studies using HRPD neutron diffraction measurements. For the period of December 1994 - December 1995, the superionic samples were the single phase β'-alumina and the double phase β,β-alumina (K_1+xFe₁₁O₁₇). Neutron diffraction measurements were supposed to be taken at room- and elevated temperatures. For the period of November 1996 - November 1997, new compounds have been proposed, in this case it is the non-stoichiometric Cu-based Rubidium Copper Iodide Chloride compounds, again the distribution of responsibility/workload stays the same as previously agreed to by BATAN and PNRI. The full report and results of this cooperation is presented. Activities covered so far at both laboratories are outlined. Although the high temperature neutron scattering measurements have not been completed, a further cooperation involving the preparation and neutron scattering measurements of materials in thin-film and single crystalline morphology is proposed. (author)

[en] A bilateral scientific cooperation, in the small angle neutron scattering has been agreed upon between CIAE, China and BATAN, Indonesia as well as MINT Malaysia. As stated in the agreed proposal that the objective of this cooperation, in the initial stage (stage-1), was to have a regional intercomparison measurements of SANS instruments in order to determine their characteristic/performance. Therefore, this report is supposed to describe the progress in the SANS instrument development of each country involved during the period of 1996/97 and some activities related to the SANS instrument. Since, up to now, we have not yet received any progresses reported from either China or Malaysia, this report will describe the progress of SANS's activities in BATAN only. (author)

[en] The Philippine Nuclear Research Institute (PNRI) started its activities on radioisotope production more than three decades ago, when the Philippine Research Reactor (PRR-1) started operating at its full rated power of 1 MW. Since then, several radionuclides in different chemical forms, were routinely produced and supplied for use in nuclear medicine, industry, agriculture, research and training, until the conversion of the PRR-1 to a 3 MW TRIGA type reactor. After the criticality test of the upgraded reactor, a leak was discovered in the pool liner. With the repair of the reactor still ongoing, routine radioisotope production activities have been reduced to dispensing of imported bulk ¹³¹I. In the Philippines, radioisotopes are widely used in nuclear medicine, with ¹³¹I and ^99mTc as the major radionuclides of interest. Thus the present radioisotope production program of PNRI is directed to meet this demand. With the technical assistance of the International Atomic Energy Agency (IAEA), PNRI is setting up a new ¹³¹I production facility. The in-cell equipment have been installed and tested using both inactive and active target, obtained from BATAN, Indonesia. In order to meet the need of producing ⁹⁹Mo-^99mTc generators, based on low specific activity reactor-produced ⁹⁹Mo, research and development work on the preparation of ^99mTc gel generators is ongoing. (author)

[en] The Korea multipurpose research reactor, HANARO(Hi-flux Advanced Neutron Application Reactor) is designed and constructed to obtain high density neutron flux (max. 5x10¹⁴ n/cm²·sec) with relatively low thermal output (30 MW) in order to utilize for various studies such as fuel and material test, radioisotope production, neutron activation analysis, neutron beam experiment, neutron transmutation doping, etc. HANARO has 32 vertical channels (3 in-core, 4 out-core, 25 reflector) and 7 horizontal channels. KAERI has constructed 4 concrete hot cells for production of Co-60, Ir-192, etc. and 6 lead hot cells for production of medical RIs(I-131, Mo-99, etc.). Other 11 lead hot cells will be completed by Feb. 1998 for production of Sm-153, Dy-165, Ho-166, etc. Clean room facilities were installed for production of radiopharmaceuticals. (author)

[en] The paper summarizes the preparation and quality control of ¹⁵³Sm-EDTMP and three ¹⁵³Sm-radiosynovectomy agents. Natural and enriched Sm₂O₃ (98.7% ¹⁵²Sm) irradiated in RSG-GAS 30 MW reactor yielded pure and high specific activity ¹⁵³Sm. Labeling of EDTMP with ¹⁵³Sm was carried out by mixing ¹⁵³SmCl₃ solution of pH 4.0 to an EDTMP solution at room temperature then pH adjustment to 8. The ¹⁵³Sm-EDTMP complex was separated from the free ¹⁵³Sm⁺³ on a Chelex 100 column. Radiochemical purity was determined by thin layer chromatography using Cellulose sheets and pyridine: ethanol: water (1: 2: 4) mixture as solvent. The ¹⁵³Sm-EDTMP has been shown to be stable for two weeks. Three particulate preparations of ¹⁵³Sm used for the irradiation of chronic synovitis have been studied. They are hydroxyapatite particles, human serum albumin microspheres and ferric hydroxide macroaggregates. The ¹⁵³Sm-ferric hydroxide macroaggregates were prepared in a single step by coprecipitation of ¹⁵³Sm in the formation of Fe(OH)₃. Preparation of ¹⁵³Sm-labelled hydroxyapatite particles and ¹⁵³Sm-labelled albumin microspheres were carried out by ¹⁵³Sm labelling of previously prepared particles. Radiolabelling efficiency were greater than 95% for hydroxyapatite particles and macroaggregates and was lower than 20% for albumin microspheres. The particle sizes were inspected using an optical microscope with a haemocytometer and micrometric ocular. (author)

[en] The Dalat Nuclear Research Reactor (DNRR) is a pool type research reactor which was reconstructed in 1982 from the previous 250 kW TRIGA-MARK II reactor. The reactor core, the control and instrumentation system, the primary and secondary cooling systems as well as other associated systems were newly designed and installed. The renovated reactor reached its initial criticality in November 1983 and attained its nominal power of 500 kW in February 1984. Since then DNRR has been operated safely. Retained structures of the former reactor such as the reactor aluminum tank, the graphite reflector, the thermal column, the horizontal beam tubes and the radiation concrete shielding are 35 years old. During the recent years, in-service inspection has been carried out, the reactor control and instrumentation system were renovated due to ageing and obsolescence of its components, reactor general inspection and refurbishment were performed. Efforts are being made to cope with ageing of old reactor components to maintain safe operation of the DNRR. (author)

[en] MINT TRIGA Reactor is a 1-MW swimming pool nuclear reactor commissioned in June 1982. Since then, it has been used for research, isotope production, neutron activation, neutron radiography and manpower training. The total operating time till the end on September 1997 is 16968 hours with cumulative total energy release of 11188 MW-hours. After more than fifteen years of successful operation, some deterioration in components and associated systems has been observed. This paper describes some of the activities carried out to increase the lifetime and to reduce the shutdown time of the reactor. (author)