우울장애 환자에서 자살 시도와 트립토판 수산화 효소(Tryptophan Hydroxylase) A218C 유전자 다형성과의 관련성

심세훈,황보영,권영준,정희연,이분희,김용구 대한신경정신의학회 2008 신경정신의학 Vol.47 No.2

Objectives : Several lines of evidence suggest the serotonergic dysfunction involved in the biological susceptibility of suicide. Tryptophan hydroxylase (TPH), the rate-limiting enzyme in the biosynthesis of serotonin, Plays a vital role in serotonin metabolism. In a case-control study, we investigated whether the TPH gene was a susceptible factor for suicidal behavior in depressive patients. Methods : The subjects were 218 depressed patients who attempted suicide and visited emergency rooms in multi-medical centers. One hundred thirty hospitalized non-suicidal depressed patients and the 161 normal controls were matched with the suicidal group. Individuals in all 3 groups were evaluated independently by a Structured Clinical Interview for the purpose of establishing a DSM-IV criteria diagnosis (SCID). The severity of depressive symptoms was evaluated using Hamilton depression rating scale (HDRS). Results : There was no significant difference in genotype distributions and allele frequencies of TPH intron 7 A218C polymorphisms among 3 groups. Furthermore, no significant difference in genotype counts and allele frequencies of the polymorphisms was found among lethal suicidal depressed patients, non-suicidal depressed patients and the normal controls. Conclusion : This study suggests that the A218C polymorphism of the TPH gene is unlikely to have a major effect on the susceptibility of suicidal behaviors in depressive patients.

항정신병약물을 처음으로 사용하는 초발 정신증 환자에서 나타나는 체중 및 대사성 지표의 변화 : 후향적 연구

김우진,심주철,공보금,강제욱,문정준,김정은,김민걸,박민경,김성진,김현정,정도운 대한생물치료정신의학회 2011 생물치료정신의학 Vol.17 No.2

Objectives:This study was to identify weight & metabolic changes in first-episode psychotic patients with antipsychotics use and investigate the differences of weight & metabolic changes between first-episode psychotic patients and controls with antipsychotics use. Method:In this retrospective study, twenty eight first-episode psychotic patients and twenty eight controls with schizophrenia, schizoaffective or bipolar disorder defined by DSM-IV criteria were included. Information about demographic and clinical characteristics of the subjects was gathered from the medical records. Also body weight, sBP, dBP, fasting glucose, lipid profile and WBC count were evaluated before and after antipsychotics use. Rogistic regression was conducted to assess factors associated with weight gain. Results:First-episode psychotic patients showed more weight and BMI changes than controls after antipsychotics use, and these changes continue over 12 months. On the other hand, there were no significant factors associated with weight gain. Conclusion:The results of present study suggest that antispychotics is one of the major causes inducing weight gain of psychotic patients and antipsychotics-induced weight gain is more vulnerable to drug-naive first-episode psychotic patients.

Experiment for a Collection Method of Phosphorylation Products From Molten Salt

Joon-Bo Shim,Ju Ho Lee,Sang-Woon Kwon,Chang Hwa Lee 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.2

Based on the results of a review for various precipitation methods phosphorylation (phosphate precipitation) of metal chlorides considered as a proper treatment method for recovering of the fission products in a molten salt. In previous precipitation tests, the powder of lithium phosphate (Li3PO4) added into LiCl-KCl molten salt containing metal chlorides as a precipitation agent. The reaction of metal chlorides containing actinides and rare earths to recover with lithium phosphate in a molten salt known as solid-liquid reaction. The powder of lithium phosphate disperse in a molten salt by stirring thoroughly in order to enhance the precipitation reaction. As a result, metal phosphates as the reaction products precipitate on the bottom of the vessel and cutting at the lower part of the salt ingot considered as one of the recovery method of the precipitates. Recently, the vacuum distillation of upper part of the salt proposed as another recovering method. Cutting method of precipitate at the lower part of the salt ingot would be difficult to handle the increased size of the salt ingot produced from the practical scale equipment. In this presentation, a new method for collecting the precipitates of phosphorylation reaction into a small vessel is introduced with test results in a molten salt containing uranium and rare earths such as Nd, Ce, and La. As the first step of a series of test lithium phosphate ingot was prepared by melting the powder at a temperature 1,300°C, and the ingot put into LiCl-KCl molten salt at 500°C for more than three hours to examine the shape of ingot to be deformed or not. The phosphorylation experiments using lithium phosphate ingots carried out to collect the metal phosphate precipitates and the test result of this new method was feasible.

Consideration on the Conversion Characteristic of Uranium Ions to Metal in the LiCl-KCl Salt With the Aid of Yttrium Metal

Joon-Bo Shim,Dal-Sung Yoon,Sung-Jai Lee 한국방사성폐기물학회 2019 한국방사성폐기물학회 학술논문요약집 Vol.2019 No.10

Effect of Sat Stirring on Phosphorylation of Uranium and Rare Earths in Molten Salt

Joon-Bo Shim,Hansoo Lee,Chang Hwa Lee 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.2

Under the circumstance of energy transition policy of the previous government in which nuclear energy portion will be gradually reduced, some R&D study looking for alternatives other than Pyro- SFR recycling could be very valuable and timely suitable. New alternative study started to evaluate the possibility of it if there are some advantages in terms of waste burden in case that the spent fuel are appropriately treated and disposed of in a disposal site, instead of recycling of spent nuclear fuels (SNF). The alternative study separate the fission products (minor actinides and rare earths) from SNF in a molten salt medium. The molten salt coming from the alternative study is radioactive and heat generating because it contains the fission products chlorides. It is necessary to collect the fission products from the waste molten salt for minimization of the high-level waste volume and to generate a final waste form containing the fission products compatible to the disposal site. Based on the results of a review for various precipitation methods, phosphorylation (phosphate precipitation) of metal chlorides selected as a proper treatment method for recovering of the fission products in a molten salt. Phosphate precipitation has the potential for removing most of fission product elements from a molten salt arising from the treatment of spent nuclear fuel. The performance of phosphate precipitation method evaluated using a salt mixture with the actinide and rare earth chlorides. The molten salt containing uranium as surrogate of the actinides and three rare earths (Nd, Ce, La) chloride was used for testing a phosphate precipitation method at experimental condition (temperature 500°C, salt stirring 200~300 rpm, and 1~1.2 eq. of phosphorylation agent). A cyclic voltammetry (CV) method monitored in-situ phosphate precipitation progress for determining the precipitation rate and conversion ratio evaluated. The phosphorylation reaction increased greatly at a salt stirring 300 rpm.

Collection of Uranium Metal From the Salt Mixture Using Yttrium Metal

Joon-Bo Shim,Dal-Sung Yoon,Si-Hyung Kim,Sung-Jai Lee 한국방사성폐기물학회 2019 한국방사성폐기물학회 학술논문요약집 Vol.2019 No.05

Segregation of the Precipitates and Salt Ingot From Tapered Crucible for Recovery of the Metal Phosphate Precipitates

Joon-Bo Shim,Sang-Woon Kwon,Chang Hwa Lee 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.2

In KAERI’s previous phosphate precipitation tests, the dispersed powder of lithium phosphate (Li3PO4) as a precipitation agent reacted with various metal chlorides in a simulated LiCl-KCl molten salt. The reaction of metal chlorides composed of actinides such as uranium and three rare earths (Nd, Ce and La) with lithium phosphate is a solid-liquid reaction. A phosphorylation reaction rate is very fast and the metal phosphates as a reaction product precipitated on the bottom of the molten salt crucible. One of the recovery methods of the metal phosphate precipitates is segregation the lower part (precipitates) of the salt ingot using the various cutting tools. Recently, a new phosphorylation experiment using lithium phosphate ingots carried out in order to collect the metal phosphate precipitates into a small recovering vessel, and the test result of this new method was feasible. However, the reaction rate of test using lithium phosphate ingot is extremely slower than that of test using lithium phosphate powder. In this study, the precipitation reactor design (a tapered crucible with polished inner surface) used for phosphorylation reaction showed that the salt ingot with metal phosphate precipitates could be detached from a tapered stainless steel crucible. We propose that the recovery of precipitates from a salt ingot is possible by introducing a dividing plate structure into a molten salt and by positioning it at the interface between salt and precipitated metal phosphate.

Concept of the Precipitation Reactor Design for Reduction of Molten Salt Amount Transferred to the Distillation Unit

Joon-Bo Shim,Eunsoo Lee,Sang-Woon Kwon,Chang Hwa Lee 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.1

A phosphorylation (phosphate precipitation) technology of metal chlorides is considering as a proper treatment method for recovering the fission products in a spent molten salt. In KAERI’s previous precipitation tests, the powder of lithium phosphate (Li3PO4) as a precipitation agent reacted with metal chlorides in a simulated LiCl-KCl molten salt. The reaction of metal chlorides containing actinides such as uranium and rare earths with lithium phosphate in a molten salt was known as solidliquid reaction. In order to increase the precipitation reaction rate the powder of lithium phosphate dispersed by stirring thoroughly in a molten salt. As one of the recovery methods of the metal phosphates precipitated on the bottom of the molten salt vessel cutting method at the lower part of the salt ingot is considered. On the other hand, a vacuum distillation method of all the molten salt containing the metal phosphates precipitates was proposed as another recovering method. In recent study, a new method for collecting the phosphorylation reaction products into a small recovering vessel was investigated resulting in some test data by using the lithium phosphate ingot in a molten salt containing uranium and three rare earth elements (Nd, Ce, and La). The phosphorylation experiments using lithium phosphate ingots carried out to collect the metal phosphate precipitates and the test result of this new method was feasible. However, the reaction rate of test using lithium phosphate ingot is very slower than that of test using lithium phosphate powder. In this presentation, the precipitation reactor design used for phosphorylation reaction shows that the amount of molten salt transferred to the distillation unit will reduce by collecting all of the metal phosphates that will be generated using lithium phosphate powder into a small recovering vessel.

Phosphate Precipitation of Uranium and Rare Earth Chlorides in Molten Salt

Joon-Bo Shim,Sang-Woon Kwon,Hansoo Lee,Chang Hwa Lee 한국방사성폐기물학회 2021 한국방사성폐기물학회 학술논문요약집 Vol.2021 No.11

Segregation Method of the Recovered Actinide Metal Mixture From a Molten Salt Medium in the Back-end Fuel Cycles System

Joon-Bo Shim,Sangkwon Lee,Chang Hwa Lee,Jae Soo Ryu 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.1

When the recycling technology of spent nuclear fuels (SNF) for future nuclear reactor systems and the treatment technology of SNF for disposing of in a disposal site use a molten salt such as LiCl-KCl eutectic as a processing medium one of the essential unit processes is a distillation process that remove the salt component mixed with fission products recovered. Especially, in case of Pyro-SFR recycling system the recovered nuclear fuel materials such as U, TRU and some of rare earths come from main three processes (electro-refining, electro-winning, and drawdown processes) for recycling of SNF. These recovered fuel materials contain large portion of molten salt or liquid cadmium which requires removal of them by distillation. In spent nuclear fuels discharged from PWR the portion of composing element is as follows. Uranium is about 95%, other actinides such as transuranic elements (TRU; Np, Pu, Am, Cm) is about 1%, the rare earths (lanthanides) is about 1%, and the other elements is about 3%. For example, americium (Am) in the recovered fuel materials has a problem that the reported loss of Am inevitably occurs during the vacuum salt distillation operation. A new segregation method of AMM (actinide metal mixture)–salt system is based on the difference in melting point of the actinide elements. It is possible to apply this segregation method to recovering other actinides from AMM with accompanied salt because of relatively large amount and lower melting point of a specific element in other actinides avoiding vacuum salt distillation. This new segregation method successfully tested using a surrogate element such as aluminum due to its similar melting point with a specific element. The segregation principle is solid-liquid separation, thus the solidified actinides mixture ingot can take out of a molten salt medium.