[en] Actinides are attracting keen interests in research fields of solid state physics and are expected to reveal interesting electromagnetic properties. However, most of actinide isotopes are very hazardous α radioactively. Also, they perform the experimental works for actinides physics and chemistry. In this paper, we will describe the facility developed in Tohoku university for the handling actinide elements and will show some preliminary results obtained on the study of electromagnetic properties

[en] The three hot cell facilities exist in the Department of Hot Laboratories (DHL), as follows: RFEF......Reactor Fuel Examination Facility RHL......Research Hot Laboratory WASTEF....Waste Safety Testing Facility The present paper mainly describes current status on the activities and the topics at these facilities, and also introduces the other presentations from the department in this seminar

[en] This proceedings contains articles of the 2nd KAERI-JAERI Joint Seminar on the PIE Technology. It was held on Sep. 20-22, 1995 in Taejon, Korea. This proceedings is comprised of 4 sessions. The main topic titles of session are as follows: current status and future program on PIE, operating experiences of PIE facility, PIE techniques and evaluation of PIE data. (Yi, J. H.)

[en] The Reactor Fuel Examination Facility (RFEF) has developed a Pellet Thermal Diffusivity measuring apparatus (PTD) with biological shielding, which is based on the laser flash method and used for an irradiated fuel pellet. The authors examined the characteristics and the function of the apparatus by using unirradiated metal, ceramics and irradiated UO₂ specimens. And also, the measurements of thermal constant for high burnup fuels and TMI 2 debris specimens were carried out, and the important data were obtained

[en] Curium doped SYNROC containing 1.61 wt.% of the curium source was prepared for an alpha acceleration test using the calci ner and the hot press in the hot cell, which were newly installed in the hot cell. The SYNROC slurry was calcined at 750 .deg. C for 2 h with very little powder carryover. Four SYNROC blocks with almost equal densities (4.302 to 4.308 g·cm^-3) were fabricated by hot pressing at 1200 .deg. C and 29 MPa for 2 hours. Volume swelling due to accumulation of alpha decays caused a gradual decrease in density. The increment of density after an equivalent age of 5000 years was -1%

[en] The air oxidation of Zry and the effects of adsorbates on the oxidation are found by the intermittent measurements of the weight gain of specimens. LiOH and NaCl are the adsorbates tested in this paper. NaCl enhances the oxidation, where nonuniform stresses on the surface and Cl ions are the cause of the enhancement. LiOH also enhances the oxidation, where initial porous oxide seem to the reason

[en] The re fabrication technique for irradiated Light Water Reactor (LWR) fuel was developed to prepare the re irradiation fuel segment with instruments. This report also describes typical PIE (Post Irradiation Examination) results on the behavior of fission gas release and metallography for the fuel specimen after RIA (Reactivity Initiated Accident) experiment in the NSRR (Nuclear Safety Research Reactor)

[en] Miniaturization of specimens are mandatory for the study of effects of heavy neutron irradiations, due to the spatial limitation in controlled irradiation rigs and due to the high radioactivity of specimens. Automated instruments for mechanical tests with the miniature specimens have been developed. Mechanical properties, such as tensile properties, toughness, have been evaluated with specimen heavily irradiated in JMTR, JOYO, EBR II, and FFTF/MOTA. The specimens are mainly structural candidate materials for fusion reactors. The paper will describe details of the instruments and present mechanical behaviors of heavily irradiated materials

[en] PIE program is discussed by utilizing both post irradiation examination facility(PIEF) and irradiated material examination facility of Korea Atomic Energy Research Institute(KAERI). The presentation does not cover the program beyond 2001

[en] To identify the distribution of actinide elements in irradiated cladding materials with different burn up, samples were dissolved in 6 M nitric acid, aqua regia and hydrofluoric acid sequentially. Gross alpha activity measurement, alpha spectrometry and mass spectrometry were applied to analyze the distribution of actinide elements in an oxidized and a non oxidized specimens. According to the results of gross alpha activity, average alpha activity was about 30μCi per gram of irradiated cladding tube and alpha activity is increased as the increase of burnup