• Title/Summary/Keyword: Fission

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The Fission Yeast Gene Encoding Monothiol Glutaredoxin 5 Is Regulated by Nitrosative and Osmotic Stresses

  • Kim, Hong-Gyum;Park, Eun-Hee;Lim, Chang-Jin
    • Molecules and Cells
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    • v.20 no.1
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    • pp.43-50
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    • 2005
  • Glutaredoxin (Grx) is a small, heat-stable redox protein acting as a multi-functional glutathione (GSH)-dependent disulfide oxidoreductase. We have cloned the monothiol Grx5 gene from the genomic DNA of the fission yeast Schizosaccharomyces pombe. It has 1,904 bp, with one intron, and encodes a putative protein of 146 amino acids with a molecular mass of 16.5 kDa. Recombinant Grx5 produced functional Grx in S. pombe cells. NO-generating sodium nitroprusside (SNP, 1.0 and 2.0 mM) and potassium chloride (KCl, 0.2 and 0.5 M) increased the synthesis of ${\beta}$-galactosidase from a Grx5-lacZ fusion gene, and transcription of Grx5 was also enhanced by SNP and KCl. Synthesis of ${\beta}$-galactosidase from the Grx5-lacZ fusion was lower in Pap1-negative TP108-3C cells than in wild type KP1 cells, and when Pap1 was overproduced in KP1 cells, the level of ${\beta}$-galactosidase increased. We also found that Pap1 is involved in the induction of Grx5 by SNP and KCl. S. pombe Grx5 may play a crucial role in responses to nitrosative and osmotic stresses.

DISCUSSION ABOUT HBS TRANSFORMATION IN HIGH BURN-UP FUELS

  • Baron, Daniel;Kinoshita, Motoyasu;Thevenin, Philippe;Largenton, Rodrigue
    • Nuclear Engineering and Technology
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    • v.41 no.2
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    • pp.199-214
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    • 2009
  • High burn-up transformation process in low temperature nuclear fuel oxides material was observed in the early sixties in LWR $UO_2$ fuels, but not studied in depth. Increasing progressively the fuel discharge burn-up in PWR power plants, this material transformation was again observed in 1985 and identified as an important process to be accounted for in the fuel simulations due to its expected consequence on fuel heat transfer and therefore on the fission gas release. Fission gas release was one of the major concerns in PWR fuels, mainly during transient or accidents events. The behaviour of such a material in case of rod failure was also an important aspect to analyse. Therefore several national and international programs were launched during the last 25 years to understand the mechanisms leading to the high burn-up structure formation and to evaluate the physical properties of the final material. A large observations database has been acquired, using the more sophisticated techniques available in hot cells. This large database is discussed in this paper, providing basis to build an engineering-model, which is based on phenomenological description data and information accumulated. In addition this paper has the ambition to construct the best logical model to understand restructuring.

Validation of nuclide depletion capabilities in Monte Carlo code MCS

  • Ebiwonjumi, Bamidele;Lee, Hyunsuk;Kim, Wonkyeong;Lee, Deokjung
    • Nuclear Engineering and Technology
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    • v.52 no.9
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    • pp.1907-1916
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    • 2020
  • In this work, the depletion capability implemented in Monte Carlo code MCS is investigated to predict the isotopic compositions of spent nuclear fuel (SNF). By comparison of MCS calculation results to post irradiation examination (PIE) data obtained from one pressurized water reactor (PWR), the validation of this capability is conducted. The depletion analysis is performed with the ENDF/B-VII.1 library and a fuel assembly model. The transmutation equation is solved by the Chebyshev Rational Approximation Method (CRAM) with a depletion chain of 3820 isotopes. 18 actinides and 19 fission products are analyzed in 14 SNF samples. The effect of statistical uncertainties on the calculated number densities is discussed. On average, most of the actinides and fission products analyzed are predicted within ±6% of the experiment. MCS depletion results are also compared to other depletion codes based on publicly reported information in literature. The code-to-code analysis shows comparable accuracy. Overall, it is demonstrated that the depletion capability in MCS can be reliably applied in the prediction of SNF isotopic inventory.

포항분지에 대한 석유지질학적 연구

  • 김기현;김재호;김상석;박동배;이용일
    • 한국석유지질학회:학술대회논문집
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    • spring
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    • pp.48-55
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    • 1998
  • The Pohang Basin is located in Pohang City and adjacent coastal areas in the southeastern Korea. It has a sequence of 900 meters of Neogene marine sediments (Yeonil Group) while offshore basins in the East Sea, e.g., the Ulleng basin, is over 10 Km in thickness. An understanding of the marine Yeonil Group in the Pohang Basin may provide insights into the hydrocarbon potential of the offshore East Sea regions. Heulandite, smectite, dolomite, kaolinite and opal-CT are commonly found as diagenetic minerals in the Yeonil Group. Among these minerals, heulandite occurs as a main cement only in sandstones consisting of volcanic matrix, Smectite composition and diagenetic mineral facies such as heulandite and opal-CT may reflect that the Yeonil Group has undergone shallow burial, temperatures below about 60 degrees. This suggest that sandstones have experiened weak diagenetic alteration. In order to reconstruct the thermal history of the basin, apatite fission-track analysis was carried out. Aapparent apatite fission-track ages (AFTAs) exhibit a broader range of ages from 238 Ma to 27 Ma with mean track lengths in the range of $15.24\pm8.0$ micrometers, indicating that these samples had undergone significant predepositional thermal alteration. The Triassic to Cretaceous AFTAs seem In represent the timing of cooling of their sedimentary sources. Late Cretaceous mean AFTA $(79.0\pm8.0 Ma)$ on the Neogene Yeonil Group indicates that the Yeonil Group had not been buried deeper than 2km since its deposition. The organic matters of. the Pohang Basin remain in the immature stage of thermal evolution because burial depth and temperature were not sufficient enough for maturation even in the deep section of the basin.

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FISSION PRODUCT RELEASE ASSESSMENT FOR A LARGE BREAK LOCA IN CANDU REACTOR LOADED WITH CANFLEX-NU FUEL BUNDLES

  • Oh, Dirk-Joo;Ohn, Myeong-Yong;Lee, Kang-Moon;Suk, Ho-Chun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.484-488
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    • 1997
  • Fission product release (FPR) assessment for 100% reactor outlet header (ROH) break in CANDU reactor loaded with CANFLEX-NU fuel bundles has been performed. The predicted results are compared with those for the reactor loaded with standard 37-element bundles. The fuel failure thresholds for the CANFLEX and standard bundle elements are very similar. All the sheaths at the corresponding fuel failure thresholds for the CANFLEX and standard bundles fail due to the significant cracks in the surface oxide, except those for the CANFLEX inner element at burnups of 220 to 240 MW.h/kg(U), which fail due to the excessive diametral strain. The fuel failure analysis predicts that the number of failed fuel elements for the CANFLEX bundle case is none, while that for the standard bundle case is 1827. The total (gap plus bound) I-131 releases for the CANFLEX and standard bundles are none and 5889 TBq, respectively The significant reduction of the number of failed fuel elements and FPR for the CABFKEX fuel bundle is attributed to the lower linear power of the CANFLEX fuel bundle compared with the standard fuel bundle.

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The Cooling Characteristics for Circular Irradiation Hole under Suppressing Jet Flow at Guide Tube in HANARO (안내관 제트유동 억제시의 하나로 원형 조사공의 냉각특성)

  • Wu S. I.;Park P. C.
    • 한국전산유체공학회:학술대회논문집
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    • 2004.03a
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    • pp.208-213
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    • 2004
  • The HANARO, multi-purpose research reactor, 30 MWth open-tank-in- pool type, is under normal operation since it reached the initial critical in February 1995. The HANARO is planning to produce a fission moly-99 of radio isotopes, a mother nuclide of Tc-99m, a medical isotope and is under developing a target handling tool for loading and unloading it in a circular flow tube (OR-5). A guide tube is extended from the reactor core to the top of the reactor chimney for easily un/loading a target under the reactor normal operation. But active coolant through the core can be quickly raised up to the top of the chimney through the guide tube by jet flow. This paper is described an analytical analysis to calculate the hole size of a orifice inserted in the circular irradiation hole and to study the flow characteristics through the guide tube under reactor normal operation and loading the target. As results, the results show that the hole size of orifice was 31 mm of the inner diameter to suppress the guide tube jet flow and the coolant safely cooled the target of fission moly after inserting the orifice to the flow tube.

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Growth-Dependent Variations in Antioxidant and Redox Enzyme Activities of Schizosaccharomyces pombe

  • Cho, Young-Wook;Park, Eun-Hee;Ahn, Ki-Sup;Kim, Dae-Myung;Lim, Chang-Jin
    • BMB Reports
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    • v.34 no.3
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    • pp.278-283
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    • 2001
  • Antioxidant and redox enzyme activities are known to be involved in the cellular responses to various stresses. Their variations were observed according to the growth cycle of the fission yeast Schizosaccharomyces pombe. Peroxidase activity appeared to be notably higher in the early exponential phase than in the mid-exponential and stationary phases. However, catalase activity showed a variation pattern resembling the growth curve. Glutathione S-transferase activity was higher in the early exponential and late stationary phases. Activities of the two redox enzymes, thioredoxin and thioltransferase (glutaredoxin), were high in the stationary phase. However, their activities appeared to increase from the early exponential to mid-exponential phase. Total glutathione content had a varying pattern similar to that of thioredoxin and thioltransferase. However, its content in the early exponential phase was high. These results propose that antioxidant and redox enzymes tested are also involved in the mechanism of cell growth.

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Functional Characterization of the Madlp, a Spindle Checkpoint Protein in Fission Yeast

  • Kim, In-Gyu;Rhee, Dong-Keun;Lee, Hee-Cheul;Lee, Joo;Kim, Hyong-Bai
    • Journal of Microbiology and Biotechnology
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    • v.15 no.4
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    • pp.694-700
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    • 2005
  • Defects in the mitotic spindle or in the attachment of chromosomes to the spindle are believed to release an activated form of spindle checkpoint complex that inhibits APC-dependent ubiquitination and subsequently arrests the cell cycle at metaphase. When the spindle assembly is disrupted, the fission yeast mitotic arrest deficient (mad) mutants fail to arrest and rapidly lose viability. To enhance our understanding of the molecular mechanisms for the pathway of checkpoint function, the functional characterizations of Mad 1 p from Schizosaccharomyces pombe involved in this process have been carried out. Yeast two-hybrid and various deletion analyses of S. pombe Mad1 p reveal that the C terminus of Mad1p is critical for the binding of Mad2p and maintenance of Mad 1 p-Mad2p interaction. In addition, it was found. that the Mad1p region (residues 206-356) is essential for Mad1p-other checkpoint components. Mad1p truncating this region is sufficient to bind Mad2p but abolishes the checkpoint function, indicating that the checkpoint function is necessary for interaction of Mad 1 p-other checkpoint components. The possible functions of S. pombe Mad1p at the cell cycle checkpoint are discussed.

A Development of Digital Control System for FWPT In Nuclear Power Plant (원전 급수펌프 구동용 터빈 제어시스템 개발)

  • Choi, In-Kyu;Jeong, Chang-Ki;Kim, Byoung-Chul;Kim, Jong-An;Woo, Joo-Hee
    • Proceedings of the KIEE Conference
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    • 2006.07d
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    • pp.1885-1886
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    • 2006
  • The thermal energy from nuclear fission is transferred to the steam generator which is a kind of a large heat exchanger. After the feedwater is injected into the steam generator and absorbs the thermal energy, it is converted into the steam. This steam goes into the turbine. The balance between the generated energy and the consumed energy is required for the nuclear power plant to be stable. For the purpose of which, the feed water, a parameter for energy transfer, should be controlled in stability. Usually, the nuclear power plants are operated in base load in the view of power system for the stability of fission system. Therefore, though there will be almost no unbalance, there can be some instability from unbalance in case of startup/shutdown or disturbance. In this case, the controllability of feedwater pump is very important for the quick recover of stability.

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