• Title/Summary/Keyword: FSR&E

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17 beta-Estradiol Increases Peak of $\textrm{Ca}^{2+}$ Current in Mouse Early Embryo (에스트로겐이 생쥐 초기배의 $\textrm{Ca}^{2+}$ 전류에 미치는 영향)

  • 강다원;신용원;김은심;홍성근;한재희
    • Journal of Embryo Transfer
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    • v.16 no.2
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    • pp.79-89
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    • 2001
  • Steroid hormones control the expression of many cellular regulators, and a role thor estrogen in mouse oocytes has been well documented. The preovulatory $E_2$increment is generally accepted as the endocrine process regulating induction of in vivo oocyte maturation To address whether the activity of the T-type $Ca^{2+}$ channel is altered by 17 beta-estradiol ( $E_2$), we examined the actions of $E_2$on the calcium channel of mouse oocytes and early embryos. Oocrtes were collected from the oviduct of mice treated with pregnant mare's serum gonadotropin (PMSG) and human choronic gonadotropin (hCG). Whole cell voltage clamp technique and confocal microscopy were used to examine that $E_2$increase intracellular $Ca^{2+}$ concentration ([C $a^{2+}$]$_{i}$ ) via voltage dependent $Ca^{2+}$ channel (VDC) and estrogen receptor (FSR), and $E_2$concentration by the use of radioimmunoassay (RIA) were examined in mouse. The results obtained were as follows: The peak of $Ca^{2+}$ current induced by $E_2$increased 122% to 1.50$\pm$0.03 nA from 1.23$\pm$0.21 nA (n=15) in the presence of 5 mM extracellular $Ca^{2+}$ concentration ([C $a^{2+}$]$_{o}$ ). The increased $Ca^{2+}$ current was temporally associated with $Ca^{2+}$ transients. The intracellular $Ca^{2+}$ level increased 207%~30 s following the addition of 1${\mu}{\textrm}{m}$ $E_2$(relative fluorescence intensity: 836.4$\pm$131.2 for control, n=10, 1736.4$\pm$192.0 in the presence of $E_2$, n=10). $E_2$increased amplitude of $Ca^{2+}$ current and [C $a^{2+}$]$_{i}$ . $E_2$-induced $Ca^{2+}$ current and $E_2$concentration in blood were showed difference on the stage of embryo. These results suggest that $E_2$modulate $Ca^{2+}$ channel to increase $Ca^{2+}$ influx.$Ca^{2+}$ influx.

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Effect of Treatment and Samples of Human Follicular Fluid on Development In Vitro of Mouse Embryos (사람 난포액의 처리 방법과 Sample이 생쥐 수정란의 체외 발달율에 미치는 영향)

  • Jeon, Byeong-Gyun;Choi, Yeon-Hee;Jo, Eun-Jung;Song, Gun-Ho;Kwak, Dae-Oh;Moon, Jin-Soo;Kim, Kwang-Chul
    • Clinical and Experimental Reproductive Medicine
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    • v.27 no.4
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    • pp.359-366
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    • 2000
  • The present studt was performed to investigate the effect of treatment and samples of human follicular fluid (hFF) on the development in vitro of mouse embryos. The two cell stage embryos collected at 40 h post-hCG injection were cultured in the modified human tubal fluid (m-RTF) containing 15% synthetic serum substitute (SSS) or human tubal fluid (hFF) for up to 3 days at $37^{\circ}C$ in 5% $CO_2$ incubator. Also the composition of hormone, total protein and protein pattern of hFF samples were analyzed. The developmental rate of mouse embryos developed to blastocyst were not significant difference in the m-RTF containing 15% hFF filtered with 0.22 or 0.8 ${\mu}m$ syringe filter, however, the embryos cultured in the m-RTF containing inactivated hFF were significantly (p<0.05) developed at the high rate to blastocyst than those containing fresh hFF and SSS. The in vitro developmental rate to blastocyst and hatched blastocyst in the m-RTF containing 15% hFF sample A (90.5 and 85.4%, respectively) and SSS (79.4 and 75.3, respectively) were significantly (p<0.05) increased, compared with hFF sample B (64.2 and 54.1 %, respectively). The hFF sample A tended to be higher concentration of LH, FSR, total protein and the ratio of progesterone/$E_2$ and lower concentration of $E_2$ and progesterone than the hFF sample B, but there were no differences in the protein pattern between the two hFF samples. The results of these study suggest that the addition of hFF to the culture medium enhances the development in vitro to blastocyst and hatched blastocyst, but the in vitro developmental rate of mouse embryos is different between hFF samples.

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Analysis of the CREOLE experiment on the reactivity temperature coefficient of the UO2 light water moderated lattices using Monte Carlo transport calculations and ENDF/B-VII.1 nuclear data library

  • El Ouahdani, S.;Erradi, L.;Boukhal, H.;Chakir, E.;El Bardouni, T.;Boulaich, Y.;Ahmed, A.
    • Nuclear Engineering and Technology
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    • v.52 no.6
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    • pp.1120-1130
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    • 2020
  • The CREOLE experiment performed In the EOLE critical facility located In the Nuclear Center of CADARACHE - CEA have allowed us to get interesting and complete experimental information on the temperature effects in the light water reactor lattices. To analyze these experiments with accuracy an elaborate calculation scheme using the Monte Carlo method implemented in the MCNP6.1 code and the ENDF/B-VII.1 cross section library has been developed. We have used the ENDF/B-VII.1 data provided with the MCNP6.1.1 version in ACE format and the Makxsf utility to handle the data in the specific temperatures not available in the MCNP6.1.1 original library. The main purpose of this analysis is the qualification of the ENDF/B-VII.1 nuclear data for the prediction of the Reactivity Temperature Coefficient while ensuring the ability of the MCNP6.1 system to model such a complex experiment as CREOLE. We have analyzed the case of UO2 lattice with 1166 ppm of boron in ordinary water moderator in specified temperatures. A detailed comparison of the calculated effective multiplication factors with the reference ones [1] in room temperature presented in this work shows a good agreement demonstrating the validation of our 3D calculation model. The discrepancies between calculations and the differential measurements of the Reactivity Temperature Coefficient for the analyzed configuration are relatively small: the maximum discrepancy doesn't exceed 1,1 pcm/℃. In addition to the analysis of direct differential measurements of the reactivity temperature coefficient performed in the poisoned UO2 lattice configuration, we have also analyzed integral measurements in UO2 clean lattice configuration using equivalency of the integral temperature reactivity worth with the driver core fuel reactivity worth and soluble boron reactivity worth. In this case both of the ENDF/B-VII.1 and JENDL.4 libraries were used in our analysis and the obtained results are very similar.