[en] The purpose of this project is to survey the national infrastructure of the radionuclide analysis for radioactive waste, and to identify the improvement issues of the national infrastructure. This study has carried out the followings: ● Analysis of measures to prevent the recurrence of the radionuclide analysis errors - Survey the measurement plans and implementation status of the radionuclide analysis errors ● Current status of the radioactive waste disposal and of the radionuclide analysis for radioactive waste - Survey the current status of KORAD for the radioactive disposal and for radioactive waste characterization ● Current status of the national infrastructure for radioactive waste characterization - Survey the infrastructures of research institutes, public institutions, university institutions and private research companies for the radionuclide analysis ● Improvement plan of the national infrastructure for radioactive waste characterization - Improvement plan of the national infrastructure for the radionuclide analysis - Current status of the test certification system and third party inspection in the field of radionuclide analysis

[en] A simultaneous technology of radioactivity and dose rate was developed based on the ICRU method. The field verification of dose rate spectroscopy (DRS) was performed to assess the radioactivity and dose rate. Finally, the method of depth profile was determined from the ICRU and DRS method. The assessment method of radioactivity in the ground using an ERM based on a NaI(Tl) and LaBr3(Ce) detectors was developed and applied to the monitoring of natural radionuclides. The multipurpose system for environmental radiation survey was developed based on a LaBr3(Ce) detector. In addition, An environmental radiation survey system based on the large-volume NaI(Tl) was developed and applied to the site characterization. The assessment method of dose rate for detected gamma nuclides was developed in the mobile survey using a backpack, carborne, and drone survey. The underwater gamma-ray spectrometer was developed to assess radioactivity in the sediment. The ground-based and mobile gamma-ray spectroscopy was applied to the contaminated area around the Fukushima Daiichi nuclear power plant (FDNPP). The implementing arrangement with JAEA was made to make a field verification of the research results. The correction factor and its evaluation was conducted through the comparison of airborne and carborne survey in the same site. In addition, the airborne survey using a unmanned helicopter of JAEA was conducted around the FDNPP. The data lost was minimized from the optimization of data interface and internal memory. The underwater survey system was developed for the purpose of the assessment of radioactivity in the sediment.

[en] A modular automated radionuclide separator for ⁹⁹Tc (MARS Tc-99) has been developed for the rapid and reproducible separation of technetium in groundwater samples. The control software of MARS Tc-99 was developed in the LabView programming language. An automated radiochemical method for separating ⁹⁹Tc was developed and validated by the purification of ^99mTc tracer solution eluted from a commercial ⁹⁹Mo/^99mTc generator. The chemical recovery and analytical time for this radiochemical method were found to be 96±2% and 81 min, respectively. - Highlights: • Design and performance of an automated radionuclide separator for ⁹⁹Tc are presented. • A control software developed in the LabView is given in detail. • An automated radiochemical method for separating ⁹⁹Tc is presented. • The automated separator is validated by the purification of ^99mTc tracer solution

[en] Surveys of radioactive contamination were performed for imported foodstuffs in 2003. The following samples among imported foodstuffs were selected from markets and Korea Food and Drug Administration(KFDA); the imported samples from country associated with the Chernobyl nuclear accident, the samples produced around the nuclear power plants or nuclear tests, the foodstuffs reported as radioacitive contamination materials in foreign country. After pretreatments such as drying and homogenization, samples were analyzed. The ¹³⁷Cs radionuclide was only measured among the regulation radionuclides(¹³⁷Cs, ¹³⁴Cs, ¹³¹I) of food code. All foodstuffs except Inonotus Obliquus(Chaga mushooms) are less than 17.0 Bq/kg or below the Minimum Detectable Activity (MDA). The activity concentrations of Chaga mushrooms from Russia ranged up to 131.25 Bq/kg which is almost 35% of the maximum permitted level of food code. The fraction of imported foodstuffs having meaningful radioactivity is small, however, the radioactive contamination survey of imported foodstuffs is still needed

[en] According to the Nuclear Safety Act, the part operating the nuclear facility have to characterize its radioactive waste, for example ³H, ¹⁴C, ⁵⁵Fe, ⁹⁰Sr, ⁹⁹Tc, ¹²⁹I, gamma isotopes and gross alpha. The fast and reliable analytical technique is a big issue in the characterization of radioactive waste, because the waste handling cost depends on its analytical results. The sequential determination of several radionuclides from one sample could be the economic alternative in processing wastes. Except the volatile radionuclides, such as ³H and ¹⁴C and gamma emitters, alpha and beta emitters should be chemically separated from the sample. This study presented the sequential separation of ⁹⁰Sr and ⁹⁹Tc from soil and concrete sample based on extraction chromatography. We collected soil and concrete samples produced from decommissioning of research reactor in Seoul. We analyzed the level of ⁹⁰Sr and ⁹⁹Tc in soil and concrete samples. The acid digestion was employed for the pretreatment and TEVA resin/Sr resin was used for chemical separation. The recovery of each radionuclide was estimated by determining stable Sr by ICP-OES and 99mTc by HPGe. ⁹⁹Tc and ⁹⁰Sr were determined by ICP-MS and LSC, respectively. Based on the performance test using the method standard sample, this method shows the reliable result, having from -8 to 2 % of relative error. The level of ⁹⁹Tc and ⁹⁰Sr in real soil and concrete samples were less than MDA.

[en] In order to investigate and evaluate the radiation environment around the nuclear facilities, the radioactivity analysis of 1359 samples and environment radiation real-time measurements at 10 sites were performed. The four times per year off-site dose assessment were performed and the first and second half environment radiation monitoring reports were submitted. Also we participated in the IAEA ALMERA activity and domestic and overseas radioactivity analysis. KAERI safeguards is to implement obligations based on the Agreement and Additional Protocol between ROK and IAEA for the Application of Safeguards, Bilateral Agreements between ROK and USA, Canada, Australia, Japan, and Domestic Nuclear Safety Law. For the IAEA Safeguards, KAERI should submit annual report for extended declaration, DIQs for nuclear facilities, accounting reports on nuclear material and advanced notifications. According to the information, KAERI should be inspected by IAEA and NSSC. Also, KAERI should provide annual reports based on the Bilateral Agreements. HANARO emergency planning zone(EPZ) was reestablished around the radius 1.5km of HANARO reactor because the EPZ base radius was expanded in the related Act. Emergency plan was updated 4 times to reflect the operation experience and request from regulatory body, etc. The training program was developed and applied every year, the exercise scenario was developed and implemented 27 times in 3 years We will comprehensively manage general environmental affairs, fulfill legal obligations, support stable research activities, and purify the environment around the nuclear research complex. Moreover we contribute to the positive image of nuclear energy as well as environmental preservation

[en] A spectrometric determination of the dose rate using a detector is a very useful method to identify the contribution of artificial nuclides. In addition, the individual dose rate for detected gamma nuclides from the radioactive materials as well as the environment can give further information such as the in-situ measurement because of the direct relation between the individual dose rate and the activity of a nuclide. In this study, the calculation method for the individual dose rate for detected gamma nuclides was suggested by introducing the concept of the dose rate spectroscopy and the peak-to-total ratio in the energy spectrum for the dose rate, which means just a form of multiplied counts and the value of a G-factor in the spectrum. In addition, the validity of the suggested method for the individual dose rate was experimentally verified through a comparison of the calculation results on the energy spectra for several conditions of the standard source. - Highlights: • A G-factor for converting count rates into the dose rate was calculated. • The dose rate spectroscopy was introduced by multiplying counts and a G-factor. • The peak-to-total ratio at the dose rate spectroscopy was calculated. • Individual dose rates for detected gamma nuclides were determined at the dose rate spectroscopy

[en] Some consumer goods to promote health such as anion bracelets, necklace and mats contain naturally occurring radioactive material (NORM). Some of them can cause problems because of high radioactivity. In the regulations, there is an annual effective dose limit of 1mSv for products, but the activity concentration limits and radioactivity index for products is not established yet. Although there are few researches for consumer goods containing NORM in foreign countries, in Japan, for the consumer goods. To regulate the NORM in consumer goods, it is necessary to derive activity concentration limits corresponding to the annual limits of 1mSv. In this research, we calculated the activity concentration limits according to the usage quantities of consumer goods. Using these results, it is possible to suggest several radioactivity indexes to apply to a lot of consumer goods

[en] Highlights: • "1"4CO_2 and THO were produced by the combustion of radwaste samples. • The radioactivity of "1"4CO_2 and THO absorbed sorbents were measured by LSC. • The CO_2 absorption in the "1"4C sorbent was analyzed using by FT-IR and a rheometer. • The temperature and viscosity of the CO_2 absorbed "1"4C sorbent was investigated. - Abstract: Radioactivities of "3H and "1"4C in spent radioactive ion exchange resins and spent radioactive lubricant oils released from nuclear power plants, has been determined using a combustion and sorption method (combustion method). The liquid scintillation counting (LSC) spectra showed that the interference of other radionuclides has not significantly affected the determination of radioactivities of "3H and "1"4C in the radwaste samples. The chemical structure of "1"4CO_2, which originated from the combustion of radwastes, trapped "1"4C sorbent has been investigated using Fourier transform infrared spectroscopy (FT-IR). FT-IR study showed interesting results that peaks for uncoupled CO_2 and carbonic amide appeared at FT-IR spectra of CO_2 high-absorbed "1"4C sorbents, while the peak for carbamate was only observed at the spectra of CO_2 low-absorbed sorbents. During the CO_2 sorption in "1"4C sorbent, temperature and viscosity of the sorbent increased owing to decrease of enthalpy and increase of apparent molecular weight of the sorbent caused by the bonding formation between sorbent molecules.

[en] The various standard operational procedures (KOLAS, ISO, ASTM) for the determination of gamma emitting radionuclides in foodstuffs were deeply examined and compared to the KFDA standard procedure. Differences are observed in the sample preparation methods, the radioactivity measurement and data report. For the quality control (QC) of the radioactivity analysis of foodstuffs, the QC sample was prepared with Cs-137 spiked rice. The simple and practical method was developed for the self-absorption correction of gamma-ray according to the matrices with the various apparent density of foodstuffs. The foodstuffs were categorized with three classes according to its characteristics (powder, liquid and gel properties) and the sample preparation methods were improved according to its categories. The monitoring procedure to identify the contaminated foodstuffs was developed based on the uncertainty and measurement time