• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.2
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• pp.87-96
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• 2004

Studies were conducted to select the candidate buffer material for a high-level waste (HLW) repository in Korea. This paper presents the hydraulic properties, the swelling properties, the thermal properties, and the mechanical properties as well as the radionuclide release-retarding capacity of Kyungju bentonite as part of those studies. Experimental results showed that the hydraulic conductivities of the compacted bentonite were very low and less than $10^{-11}$m/s. The values decreased with increasing the dry density of the compacted bentonite. The swelling pressures were in the range of 0.66 MPa to 14.4 ㎫ and they increased with increasing the dry density. The thermal conductivities were in the range of 0.80 ㎉/m $h^{\circ}C$ to 1.52 ㎉/m $h^{\circ}C$. The unconfined compressive strength, Young's modulus and Poison's ratio showed the range of 0.55 ㎫ to 8.83 ㎫, 59 ㎫ to 1275 ㎫, and 0.05 to 0.20, respectively, when the dry densities of the compacted bentonite were 1.4 Ms/㎥ to 1.8 Mg/㎥. The diffusion coefficients in the compacted bentonite were measured under an oxidizing condition. The values were $1.7{\times}10^{-10}$m^2$/s to 3.4{\times}10^{-10}$m^2$/s for electrically neutral tritium (H-3), 8.6{\times}10^{-14}$m^2$/s to 1.3{\times}10^{-12}$m^2$/s for cations (Cs, Sr, Ni), 1.2{\times}10^{-11}$m^2$/s to 9.5{\times}10^{-11}$m^2$/s for anions (I, Tc), and 3.0{\times}10^{-14} $m^2$/s to 1.8{\times}10^{-13}$m^2$/s $for actinides (U, Am), when tile dry densities were in the range of 1.2 Mg/㎥ to 1.8 Mg/㎥. The obtained results will be used in assessing the barrier properties of Kyungju bentonite as a buffer material of a repository in Korea.n Korea.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.3
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• pp.189-197
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• 2012

Geochemical composition of fracture filling minerals and groundwater was investigated to characterize geochemical characteristics of groundwater system at the KURT site. Minerals such as calcite, illite, laumontite, chlorite, epidote, montmorillonite, and kaolinite, as well as I/S mixed layer minerals were detected in the minerals extracted from the fracture surfaces of the core samples. The groundwater from the DB-1, YS-1 and YS-4 boreholes showed alkaline conditions with pH of higher than 8. The electrical conductivity (EC) values of the groundwater samples were around $200{\mu}S/cm$, except for the YS-1 borehole. Dissolved oxygen was almost zero in the DB-1 borehole indicating highly reduced conditions. The Cl- concentration was estimated around 5 mg/L and showed homogeneous distribution along depths at the KURT site. It might indicate the mixing between shallow groundwater and deep groundwater. The shallow groundwater from boreholes showed $Ca-HCO_3$ type, whereas deep groundwater below 300 m from the surface indicated $Na-HCO_3$ type. The isotopic values observed in the groundwater ranged from -10.4 to -8.2‰ for ${\delta}^{18}O$ and from -71.3 to -55.0‰for ${\delta}D$. In addition, the isotope-depleted water contained higher fluoride concentration. The oxygen and hydrogen isotopic values of deep groundwater were more depleted compared to the shallow groundwater. The results from age dating analysis using $^{14}C$ indicated relatively younger (2000~6000yr old) groundwater compared to other european granitic groundwaters such as Stripa (Sweden).

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.1
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• pp.45-53
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• 2012

The metal chloride wastes from a pyrochemical process to recover uranium and transuranic elements has been considered as a problematic waste difficult to apply to a conventional solidification method due to the high volatility and low compatibility with silicate glass. In this study, a dechlorination approach to treat LiCl-KCl waste for final disposal was adapted. In this study, a $SiO_2-Al_2O_3-P_2O_5$ (SAP) inorganic composite as a dechlorination agent was prepared by a conventional sol-gel process. By using a series of SAPs, the dechlorination behavior and consolidation of reaction products were investigated. Different from LiCl waste, the dechlorination reaction occurred mainly at two temperature ranges. The thermogravimetric test indicated that the first reaction range was about $400^{\circ}C$ for LiCl and the second was about $700^{\circ}C$ for KCl. The SAP 1071 (Si/Al/P=1/0.75/1 in molar) was found to be the most favorable SAP as a dechlorination agent under given conditions. The consolidation test revealed that the bulk shape and the densification of consolidated forms depended on the SAP/Salt ratios. The leaching test by PCT-A method was performed to evaluate the durability of consolidated forms. This study provided the basic information on the dechlorination approach. Based on the experimental results, the dechlorination method using a $SiO_2-Al_2O_3-P_2O_5$ (SAP) could be considered as one of alternatives for the immobilization of waste salt.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.1
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• pp.27-36
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• 2012

Metal chloride waste is generated as a main waste streams in a series of electrolytic processes of a pyrochemical process. Different from carbonate or nitrate salt, metal chloride is not decomposed into oxide and chlorine but it is just vaporized. Also, it has low compatibility with conventional silicate glasses. Our research group adapted the dechlorination approach for the immobilization of waste salt. In this study, the composition of SAP ($SiO_2-Al_2O_3-P_2O_5$) was adjusted to enhance the reactivity and to simplify the solidification process as a subsequent research. The addition of $Fe_2O_3$ into the basic SAP decreased the SAP/Salt ratio in weight from 3 for SAP 1071 to 2.25 for M-SAP( Fe=0.1). The experimental results indicated that the addition of $Fe_2O_3$ increased the reactivity of M-SAP with LiCl-KCl but the reactivity gradually decreased above Fe=0.1. Also, introducing $B_2O_3$ into M-SAP requires no glass binder for the consolidation of reaction products. U-SAP ($SiO_2-Al_2O_3-Fe_2O_3-P_2O_5-B_2O_3$) could effectively dechlorinate the LiCl-KCl waste and its reaction product could be consolidated as a monolithic form without a glass binder. The leaching test result indicated that U-SAP 1071 was more durable than other SAPs wasteform. By using U-SAP, 1 g of waste salt could generated 3~4 g of wasteform for final disposal. The final volume would be about 3~4 times lower than the glass-bonded sodalite. From these results, it could be concluded that the dechlorination approach using U-SAP would be one of prospective methods to manage the volatile waste salt.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.3
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• pp.281-290
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• 2018

In order to understand the long-term behavior of radionuclides in granite environments, geochemical behavior characteristics of uranium in granitic host rock of KURT (KAERI Underground Research Tunnel) were investigated by dissolution experiment with different reaction time and solutions. In the dissolution experiment, significantly increased dissolution levels of uranium from granite powder samples were identified during the reaction time of 0~10 days for reaction solutions ($UD-CO_3$ and UD-Bg) containing a large amount of $CO_3{^{2-}}$. On the other hand, significantly increased dissolution levels of uranium were also identified for reaction solutions containing Na and Ca after 60 days. Dissolution of uranium continuously increased in reaction solutions of $UD-CO_3$ ($44.61{\mu}g{\cdot}L^{-1}$), UD-Bg ($41.01{\mu}g{\cdot}L^{-1}$), UD-Na ($26.87{\mu}g{\cdot}L^{-1}$), UD-Ca ($20.26{\mu}g{\cdot}L^{-1}$), UD-CaSi ($17.03{\mu}g{\cdot}L^{-1}$), and UD-Si ($10.47{\mu}g{\cdot}L^{-1}$) in the experimental period of ~270 days. However, after day 270, dissolution of uranium showed a decreasing tendency. This is thought to have occurred because existing uranium in granite samples reached the limit of dissolution by interaction with reaction solutions. Concentrations of dissolved uranium and points of maximum concentration value were found to differ depending on the $CO_3{^{2-}}$ presence in the mixed reaction solution and on the geochemical type of the water. It is estimated that differences in the reaction rate between the granite sample and the reaction solution are due to the influence of dissolved ions in the reaction solution.

• Analytical Science and Technology
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• v.28 no.5
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• pp.331-340
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• 2015

Mutations in Fused in Sarcoma (FUS) have been identified in patients with amyotrophic lateral sclerosis (ALS) or Frontotemporal Dementia (FTD). Pathological FUS is mis-localized to cytosol and forms aggregates associated with stress granules (SG), while FUS is normally localized to nucleus. However, it is largely unknown how pathological FUS forms SG-aggregates and which domains are responsible for this process. In this study, we examined cellular localization and aggregation of ALS-linked FUS missense mutants (P525L, R521C, R521H, R521G), analyzed the domains responsible for cytosolic FUS aggregation in HEK293T cells, and confirmed this in cultured mouse neurons. To do this, we firstly generated missense mutants of FUS and then examined their cellular localization. We found that P525L was mostly mis-localized to cytosol and formed FUS-positive SG aggregates while R521C, R521H, or R521G was localized to both nucleus and cytosol. To further characterize the domains required for aggregate formation of cytosolic FUS, we generated different domain-deletion mutants using FUS-∆17 which has a deletion of nuclear localization signal. Interestingly, cytosolic FUS without SYGQ and RGG1 domain or cytosolic FUS without RGG2-ZnF-RGG3 domain did not form FUS-positive SG aggregates, while cytosolic FUS without RRM domain generated more aggregates compared to FUS-∆17. Taken together, these data suggest that SYGQ-RGG1 or RGG2-ZnF-RGG3 domain contributes to formation of cytosolic aggregate, while RRM domain might interfere with FUS aggregation. Therefore, our studies will provide important insight for understanding cellular pathogenesis of neurodegeneration associated with FUS aggregate as well as finding therapeutic targets for ALS or FTD.

• Women's Health Nursing
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• v.5 no.3
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• pp.389-409
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• 1999

This study was carried out to identify the differences between nursing needs and levels of satisfaction of postpartum women during the early postpartum period. The goal of this study was to obtain needed to develope the nursing quality for postpartum women. The subjects were 87 postpartum women who had vaginal delivery at 2 general hospital and 2 maternity hospital in the Ulsan City. The period for the data collection was from June 1 to 29, 1999. The data was gathered using an 98 items questionnaire which was a modified version of a questionnaire the developed by Y. J. Chun. Results found are as follows : 1. The general characteristics of the subjects : The majority of subjects were 25-29 yrs. (57.5%), high school and college graduates(96.5%), unemployed(75.9%), middle ranged economics(93.1%), had no religion(43.7%), male baby(52.9%), birth weight 3-3.5Kg(49.4%), wanted pregnancy(96.6%), no abortion history(50.6%), had antenatal care(89.7%), had prenatal education(32.2%), postnatal education(42.5%), intended breast feeding (46.0%), had resonable self confidence about self(20.7%), infant care(36.8%) and nuclear family pattern(82.3%). 2. The level of nursing needs of overall nursing care(3.93) and the levels of satisfaction(3.86) was relatively high. The nursing needs by category of nursing care, the highest need was in the emotional and psychological care(4.09), and the lowest need was in physical need(3.73). The satisfactions by category of nursing care, the highest satisfaction was in emotional and psychological care(4.11) and the lowest satisfaction was in education in self care(3.64). The significant differences between nursing needs and satisfactions were found on education in infant care(p=.005), and education in self care(p=.020). 3. Among items of physical care, 'accurate medication and treatment(4.21)', 'control of postpartum hemorrhage(4.13)', 'pain control and care of episiotomy wound (4.12)' and 'regular observation of postpartum conditions(4.09)' showed high nursing needs. 'Accurate medication and treatment(4.31)', 'regular observation of postpartum condition(4.24)', 'control of postpartum hemorrhage(4.22)' and 'pain control and care of episiotomy wound(4.12)' showed high satisfaction levels. 4. Among items of emotional and psychological care, 'personal treatment(4.32)', kind and faithful care(4.30)', 'detailed explanation on the treatment or nursing care(4.25)', 'adequate draping during the care and treatment(4.23)' and detailed explanation on a doubt(4.13)', showed high nursing needs, 'personal treatment(4.52)', 'kind and faithful care(4.45)', 'detailed explanation on a doubt(4.24)', 'detailed explanation on the treatment or nursing care(4.21)' and 'adequate draping during the care and treatment(4.18)' showed high satisfaction of nursing care. Difference between the level of nursing needs and satisfaction was significant except item of 'early contacts with their baby and breast feeding'. 5. Among items of environmental care, the highest level of need and satisfaction were on the items of 'neat bedding and clothes(4.05, 4.21)' and 'room cleansing or care of room(4.01, 4.28)'. Differences between the level of nursing care and satisfaction were 'room cleansing of care of room'. 6. Among items of educational needs on self care, 'sitz bath method(4.22)', 'high risk symptoms to immediate clinic visits(4.13)', 'the timing of tub bath(4.05)' and 'good secretion of breast milk(4.03)', showed high nursing needs, 'sitz bath method(4.22)' showed high satisfaction of nursing care. Differences between the level of nursing care and satisfaction were 'the timing of hair shampoo', 'the timing of tub bath', ' the method of pad change', 'postpartum exercise', 'good secretion of breast milk', 'maintenance of breast figure', 'contraindicated drugs in postpartum women', 'kegel exercise' and 'breast self examination'. 7. Among items of educational needs on infant care, 'immunization of infants(4.36)', 'symptoms of sickness to immediate clinic visits(4.28)'. 'safety and emergency care(4.28)', 'umbilical care(4.26)', 'feeding times and intervals(4.24)', 'normal growth and development of infant(4.24)' and 'infection control(4.22)', showed high level of nursing care, 'immunization of infants(4.21)', 'feeding times and intervals(4.17)', were high satisfaction items showed significant differences between the level of nursing care and satisfaction. 8. Relationship between nursing needs and levels of satisfaction among postpartum women were as follows : 1) Physical area : There were no significant differences in the level of nursing needs, but satisfaction levels were significantly different among 'working mothers', 'baby's weights', 'baby's sex', 'planning of feeding' and 'routes of receiving postpartum informations'. 2) Emotional and psychological area : The level of nursing needs were significantly different in the area of 'confidence in self care'. Satisfaction levels were significantly different among 'baby's sex', 'baby's weights', 'the confidence of infant care' and 'working mother'. 3) Environment area : There were on significant differences in the level of nursing needs, but satisfaction levels were significantly different among 'maternal age' and 'baby's weights'. 4) Education in self care : The level of nursing needs were significantly different among 'parity history' and 'type of family formation'. Satisfaction levels were significantly different among 'working mother', 'baby's sex', 'antenatal care', 'postpartum education', 'planning of feeding', 'routes of receiving postpartum informations'. 5) Education in infant care area : The level of nursing needs were significantly different among 'parity history'. Satisfaction levels were significantly different among 'baby's sex', 'receiving postpartum education or not' and 'working mother'.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.2
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• pp.117-131
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• 2006

A coupled T-H-M(Thermo-Hydro-Mechanical) analysis was carried out for KENTEX (KAERI Engineering-scale T-H-M Experiment for Engineered Barrier System), which is a facility for validating the coupled T-H-M behavior in the engineered barrier system of the Korean reference HLW(high-level waste) disposal system. The changes of temperature, water saturation, and stress were estimated based on the coupled T-H-M analysis, and the influence of the types of mechanical constitutive material laws was investigated by using elastic model, poroelastic model, and poroelastic-plastic model. The analysis was done using ABAQUS, which is a commercial finite element code for general purposes. From the analysis, it was observed that the temperature in the bentonite increased sharply for a couple of days after heating the heater and then slowly increased to a constant value. The temperatures at all locations were nearly at a steady state after about 37.5 days. In the steady state, the temperature was maintained at $90^{\circ}C$ at the interface between the heater and the bentonite and at about $70^{\circ}C$ at the interface between the bentonite and the confining cylinder. The variation of the water saturation with time in bentonite was almost same independent of the material laws used in the coupled T-H-M processes. By comparing the saturation change of T-H-M and that of H-M(Hydro-Mechanical) processes using elastic and poroelastic material mod31 respectively, it was found that the degree of saturation near the heater from T-H-M calculation was higher than that from the coupled H-M calculation mainly because of the thermal flux, which seemed to speed up the saturation. The stresses in three cases with different material laws were increased with time. By comparing the stress change in H-M calculation using poroelasetic and poroelasetic-plastic model, it was possible to conclude that the influence of saturation on the stress change is higher than the influence of temperature. It is, therefore, recommended to use a material law, which can model the elastic-plastic behavior of buffer, since the coupled T-H-M processes in buffer is affected by the variation of void ratio, thermal expansion, as well as swelling pressure.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.3
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• pp.217-224
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• 2008

In deep geological disposal system, the integrity of a disposal canister having spent fuels is very important factor to assure the safety of the repository system. This disposal canister is one element of the engineered barriers to isolate and to delay the radioactivity release from human beings and the environment for a long time so that the toxicity does not affect the environment. The main requirement in designing the deep geological disposal system is to keep the buffer temperature below 100$^{\circ}C$ by the decay heat from the spent fuels in the canister in order to maintain the integrity of the buffer material. Also, the disposal canister can endure the hydraulic pressure in the depth of 500 m and the swelling pressure of the bentonite as a buffer. In this study, new concept of the disposal canister for the CANDU spent fuels which were considered to be disposed without any treatment was developed and the thermal stability and the structural integrity of the canister were analysed. The result of the thermal analysis showed that the temperature of the buffer was 88.9$^{\circ}C$ when 37 years have passed after emplacement of the canister and the spacings of the disposal tunnel and the deposition holes were 40 m and 3 m, respectively. In the case of structural analysis, the result showed that the safety factors of the normal and the extreme environment were 2.9 and 1.33, respectively. So, these results reveal that the canister meets the thermal and the structural requirements in the deep geological disposal system.

• The Journal of Korean Medicine
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• v.29 no.4
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• pp.205-212
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• 2008

Background and purpose: So far it was reported that acupuncture increased cerebral blood supply and stimulated the functional activity of brain nerve cells. A previous study demonstrated a correlation between LI4-11 electro-acupuncture (EA) and rCBF increase in frontal lobe. However, there remained a need to study further using various controls in acupuncture research. Transcutaneous electrical nerve stimulation (TENS) has been used as a non-invasive control in acupuncture study. This study was to evaluate the effect of LI4-LI11 TENS on regional cerebral blood flow (rCBF) in normal volunteers using single photon emission computed tomography (SPECT) and statistical parametric mapping (SPM). Methods: In the resting state, $^{99m}Tc-ECD$ brain SPECT scans were performed on 10 normal volunteers (9 males, 1 female, mean age 26.6$\pm$0.5 years; age range from 26 to 27 years). On the other day, 7 days after the resting examination, 15 minute TENS were applied at LI 4 and LI 11 on the right side of the subjects. Immediately after LI4-LI11 TENS, the second SPECT images were obtained in the same manner as the resting state. Significant increases and decreases of regional cerebral blood flow after LI4-LI11 TENS were estimated by comparing their SPECT images with those of the resting state using paired t statistics at every voxel, which were analyzed by statistical parametric mapping with a threshold of p = 0.001, uncorrected (extent threshold: k=100 voxels). Results: TENS applied at right LI4-LI11 increased rCBF in the left somatosensory association cortex (Brodmann area 5, 7). However there was no area where LI4-11 TENS decreased rCBF. Conclusion and suggestions: These results demonstrate that right LI4-LI11 TENS increased rCBF only in corresponding somatosensory association cortex, which was different from the previous results using LI4-11 EA. It is suggested that there be a different mechanism between TENS and EA.