• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• 제2권1호
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• pp.69-75
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• 2004

DORT and ORIGEN2 code were used for calculation of neutron flux and inventory in reactor pressure vessel(RPV) of Kori unit-1, To calculate neutron flux using DORT code, the reactor was divided into 94 mesh from the center of core to RPV and from 0 to 45 degree along the azimuth. The cross-sections of main nuclides were recalculated using neutron flux in the RPV region. The results showed that 95% of the total activity in RPV came from the nuclides of $^{55}$ Fe, $^{60}$ Co, $^{59}$ Ni and $^{63}$ Ni. And the total activity with cooling of more than 50 years after decommissioning was no more than 0.2% of at the time of shutdown. Considering the weight of RPV is 210 tons, the initial total activity of RPV reached 5.25${\times}$10$^{6}$ GBq. To verify results of ORIGEN2 calculation, comparison between calculated and measured value at RPV of Kori unit-1 was peformed. The comparison results showed a good agreement.

• KSBB Journal
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• 제9권5호
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• pp.475-482
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• 1994

To find out the optimum conditions for the cell growth and the synthesis of PHB in A. eutrophus, the effects of culture conditions and extracellular by-products were investigated. Glucose and$>(NH_4)_2HP0_4$were optimum carbon and nitrogen sources, respectively for cell growth of A. eutrophus. PHB accumulation was stimulated by deficiency of nutrients such as $>NH_4^{3-}, P0_4^{3-}, and Mg^{2+}$ in the medium. $>NH_4^+$, deficiency was the most suitable for PHB accumulation and PHB accumulation ratio was reached 42% of dry cell weight. The specific growth rate was increased 1.5 times by addition yeast extract in the medium, and proteins and vitamins are supposed a main factor of that effect. The extracellular products such as ethanol and butanediol were excreted under anaerobic conditions. And ethanol was found to decrease the specific growth rate.

• Journal of Radiation Protection and Research
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• 제35권1호
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• pp.12-20
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• 2010

In a primary system at nuclear power plants (NPPs), various radionuclides including fission products and corrosion products are generated due to the complex water conditions. Particularly, $^3H,\;^{14}C,\;^{58}Co,\;^{60}Co,\;^{137}Cs,\;and^{131}I$ are important radionuclides in respect of dose assessment for radiation workers and management of radioactive effluents. In this paper, the dominant contributors of radiation exposure for radiation workers and the member of public adjacent to NPPs were reviewed and the process of dose assessment attributable to those contributors were introduced. Furthermore, the analysis for some examples of radiation exposure to radiation workers and the public during the NPP operation was carried out. This analysis included the notable precedents of internal radiation exposure and contamination of demineralized water occurred in Korean NPPs. Particularly, the potential issue about the dose assessment of tritium and carbon-14 was also reviewed in this paper.

• Nuclear Engineering and Technology
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• 제5권3호
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• pp.202-213
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• 1973

In a continuation of the 1st series of these studies, a separation of the components in organic phases obtained from Szilard Chalmer reactions of aromatic chloro derivatives was attempted to clarify the conditions of isolating the main component. Though it was unable to isolate all constituents of organic phases, the main component was well isolated by means of a simple distillation or a thin layer chromatography. It was identified that the main component was a recombined product of the recoiled $^{38}$ Cl atom with the original sample. In cases of solid samples the main component amounted about 80-60% of the radio activity of the organic phase, whereas the main component from liquid samples gave less than 70% of the radio activity of the organic phase. A prolonged irradiation could increase the yield of a main component, but it was, in case of a radiation senintive compound, decreased as the irradiation is extended. The number of aide produets separated from an organic phase of a liquid sample was greater than that of a solid sample, and hence the main component of a solid sample was isolated easier. The overall fields of the labelled main products of 22 kinds of compounds were listed and a procedure of the separation of the main component by a thin layer chromatograply was proposed and evaluated. The feasibility of the present procedure for labelling purpose was also reviewed with respects to the chemical structure of a compound.

• Journal of the Korean Institute of Gas
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• 제2권3호
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• pp.60-69
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• 1998

Methane, the major constituent of natural gas, had been converted to higher hydrocarbons by microwave and radio-frequency plasma in vacuum condition. Methane had been activated to plasma by suppling high energy then converted to ethane, ethylene, acetylene. The direct conversion process of methane had produced few by-products and demanded low-energy. The plasma sources were microwave and radio-frequency. Two types of reactor had been used to activate methane. One is common single tubular-type reactor and the other is series coil-type reactor which used for the first time in this study. To produce more C2 products, methane had been converted by a plasma and catalyst. The results of this study could be used to study mechanism of plasma reaction of methane, design the plant-scale reactor.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• 제17권1호
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• pp.121-126
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• 2019

The radionuclide inventory prediction of a nuclear power plant can help establish decommissioning plan by providing information of radiation environment. Accumulated radionuclides in reactors and related facilities after reactor shutdown can be divided into neutron activated materials and contaminated materials. Among the neutron activated radionuclides, $^{36}Cl$ and $^{41}Ca$ are important from the viewpoint of disposal because of its long half-life and physiochemical characteristics. In this research, we calculated the radionuclides of $^{36}Cl$ and $^{41}Ca$ in bioshielding concrete by estimating the neutron flux and cross section using the MCNPX. And we evaluated the inventories of $^{36}Cl$ and $^{41}Ca$ using the activation calculation code ORIGEN2.

• Journal of the Korean Chemical Society
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• 제37권2호
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• pp.228-236
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• 1993

The effect of ferric ion on the reaction of CH_3$MgI with benzylbromide was investigated by determining the product ratio between cross-coupling product, ethylbenzene (A) and homocoupling product, bibenzyl (B) in the presence of ferric ion. When CH_3$MgI prepared with pure magnesium was used, the ratio of A to B was 22 to 78 and with reagent grade magnesium, the ratio became 33 to 67 indicating that metallic impurities in magnesium affect the reaction mechanism to lead less homocoupling product, B. The ratio changes became significant when ferric chloride was added in the reaction mixture in catalytic amounts and the ratio of A to B reached to 80 to 20 at maximum. The reaction in the presence of ferric ion seems to follow mainly an ionic mechanism which involves iron-benzyl bromide ${\pi}$-complex formation. The complex formation is expected to be able to enhance ionic attack of CH_3$MgI on benzyl carbon to give more A.

• Journal of Radiation Protection and Research
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• 제9권1호
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• pp.33-42
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• 1984

A great variety of nuclear gamma rays emitted from fission and activation products of spent nuclear fuel contains much information that can be elicited without affecting the integrity of the fuel elements. But the extraction of such information from the complex spectrum is difficult and requires computer codes. In the present work, a versatile code 'CAERI' was developed which locates peaks and calculates their areas for X-rays as well as gamma rays using elegant features of some widely used programs for gamma-ray peak fitting. 'CAERI' coded in FORTRAN used infinite series approximation more accurate than other workers various, simple, piecewise series approximations for evaluations of the Voigt function which represents the X-ray peak with non-negligible natural line width. 'CAERI' can handle even a complex multiplet consisting of peaks from X-rays and gamma rays in arbitrary mixture, which one often encounters in the isotopic analysis of heavy elements such as U and Pu. The results of the fitting performed on the test spectra of $^{177m}\;Lu\;{\gamma}-ray\;and\;^{235}U\;K_{\alpha}$X-ray show good agreement with those by previous workers.

• 한국신재생에너지학회:학술대회논문집
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• 한국신재생에너지학회 2011년도 춘계학술대회 초록집
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• pp.76.2-76.2
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• 2011

석탄으로부터 합성석유를 생산하는 상용기술을 도입하여 건설하고 이와 더불어 원천기술 개발을 위한 국산화 기술 개발을 병행하여 향후 고유가 시대를 대비한 국가 에너지 안보 확립과 국내 기술 개발의 가속화를 추구해야 할 필요성이 대두되고 있다. 본 타당성 조사는 3종류의 석탄(호주 Wyong탄, 인도네시아 NTC탄, 인도네시아 KBB탄)으로부터 가스화에 의하여 합성석유스를 생산하는 공정에 대한 타당성 조사(Feasibility Study, FS)를 Class 5(하한 -50~-20%, 상한 30~100%)의 정확도로 수행하는 것을 내용으로 하고 있다. 플랜트의 규모는 합성석유 기준으로 20,000배럴/일이다. 플랜트의 건설을 위해서 광양제철소 슬래그처리장 내 12만평 부지에 조성 중인 포스코 SNG 생산공장 부지의 일부를 사용하는 것을 기준으로 하였다. 일반적으로 석탄의 종류에 따라서 가스화기의 종류 및 성능이 결정된다. 본 타당성 조사 연구에서 선정된 3종류의 석탄의 조성, 발열량, 회분 함량 등의 특성을 고려하여 각각의 석탄에 적합한 현존하는 상용급 가스화기를 선정하였다. 해당 석탄이 가스화기 종류에 따라 적절한 전처리 과정(건조, 분쇄, 슬러리화)을 거친 후 가스화기에 공급되는 것을 가정하여 석탄의 원소분석 조성, 발열량, 회분함량, 회분조성, 회 용융점 등의 변수에 따라서 각각 해당 가스화기에서 가스화되었을 때의 생성되는 합성가스의 조건을 시뮬레이션을 통하여 얻었다. 가스화기 시뮬레이션 결과를 토대로 합성석유 및 합성천연가스 생산을 위한 공정의 물질수지식 및 에너지수지식이 계산되었으며 이로부터 각 공정에서 발생되는 부생성물과 폐기물에 대한 양이 결정되고 이를 처리하는 방안 등도 제시되었다. 실증시설은 20,000배럴/일 규모의 CTL 및 전기 병산 시설이 적합하다. 더 큰 규모 공장은 투자비가 너무 커서 유가 또는 석탄가 변동에 따라 사업의 수익성이 크게 변하여 위험도가 큰 단점이 있기 때문이다. CTL 공장에 전기 병산이 추천되는 이유는 산소생산공장(APU), 압축 등 석탄전환공장에는 자체적인 전기수요가 막대하여 따로 스팀터빈용 발전소를 운영하므로 이를 효율적으로 대체하고자 하기 때문이다. 즉, 석탄가스화에 의해 기름을 최대한 만들고 미반응가스는 가스터빈 및 스팀터빈의 복합발전에 의해 고효율로 전기를 생산하면 최소의 비용으로 최대한 전기를 생산하여 자체소비 전력을 충당하고 남는 전기는 판매하여 수익률을 높일 수 있다.

• Journal of the Korean Wood Science and Technology
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• 제29권2호
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• pp.126-132
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• 2001

This research is carried out to investigate the formation and preservative effectiveness of inorganic substance, calcium carbonate($CaCO_3$), in wood. The specimens were prepared by the impregnation with saturated solutions of potassium carbonate($K_2CO_3$) into the wood followed by precipitation in saturated solutions of calcium chloride($CaCl_2$) for 24h, 72h and 120h, and then they were leached in instrument flowing with water for 24h. The weight percent gains of $K_2CO_3$ solution impregnated specimens reached approximately a maximum value (108.1%) by 72h precipitation in $CaCl_2$ solutions. Inorganic substances were observed to he produced in the lumina of tracheids of specimens. From these inorganic substances filling in the tracheids, characteristic X-rays of calcium(Ca-$K_{\alpha}$) were detected by energy dispersive X-ray analyzer. Moreover, it was shown from a leaching treatment that these substances could not he leached easily from the specimens. Therefore, they were could he considered to be insoluble calcium carbonates. The weight losses of the prepared specimens were hardly occurred by test fungi attacks. Thus inorganic substances in specimens can be said to have preservative effectiveness.