• Title/Summary/Keyword: Fission fragments

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Nuclear Charge Distribution in Fission Products

  • Baik, Joo-Hyun;Bak, Hae-Ill
    • Nuclear Engineering and Technology
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    • v.11 no.4
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    • pp.295-301
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    • 1979
  • For thermal-neutron-induced fission of $U^{235}$, nuclear charge distribution in the light part of the primary products has been calculated by using several postulates of charge distribution in the fission fragments. By comparing these values with the experimental results, it is revealed that those models are not appropriate for predicting the nuclear charge distribution in the fission fragments. The variation in the most probable charge, $Z_{P}$, of the isobaric distribution for the fission fragments and the charge for a mass given by unchanged charge density, $Z_{UCD}$, is turned out to be small as a function of mass. The parameter, $Z_{P}$ $-Z_{UCD}$, varies from 0.45 to 0.5 in charge units. The nuclear charge dispersion, $\sigma$, shows about 0.5 charge units for the fission fragments. Neutron odd-even effect in fission products could not be revealed clearly without considering the odd-even effect of prompt neutron emission.

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Isotopic Analysis of Decay Heat Contributors From Actinides and Fission Fragments of Spent Nuclear Fuel for Intermediate- and Long-Term Storage Times

  • Amir Mohammad Al-Ramady
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.22 no.1
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    • pp.1-7
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    • 2024
  • In this research, a detailed analysis of the decay heat contributions of both actinides and non-actinides (fission fragments) from spent nuclear fuel (SNF) was made after 50 GWd·tHM-1 burnup of fresh uranium fuel with 4.5% enrichment lasted for 1,350 days. The calculations were made for a long storage period of 300 years divided into four sections 1, 10, 100, and 300 years so that we could study the decay heat and physical disposal ratios of radioactive waste in medium- and long-term storage periods. Fresh fuel burnup calculations were made using the code MCNP, while isotopic content and then decay heat were calculated using the built-in stiff equation solver in the MATLAB code. It is noted that only around 12 isotopes contribute more than 90% of the decay heat at all times. It is also noted that the contribution of actinides persists and is the dominant ether despite decreasing decay heat, while the effect of fission products decreases at a very rapid rate after about 40 years of storage.

Development of Parallel Plate Avalanche Counter for heavy ion collision in radioactive ion beam

  • Wei, Xianglun;Guan, Fenhai;Yang, Herun;Wang, Yijie;Zhang, Junwei;Ma, Peng;Diao, Xinyue;Lu, Chengui;Li, Meng;Guan, Yuanfan;Duan, Limin;Hu, Rongjiang;Zhang, Xiuling;Xiao, Zhigang
    • Nuclear Engineering and Technology
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    • v.52 no.3
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    • pp.575-580
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    • 2020
  • We have developed a position-sensitive Parallel Plate Avalanche Counter (PPAC) to detect the fission fragments and reconstruct the fission reaction plane in the experiment of studying nuclear equation of state (nEOS) by means of heavy ion collision (HIC). This experiment put forward high requirements for the performances of PPAC, such as the time resolution, efficiency and position resolution. According to these requirements we designed the PPAC with an active area of 240 mm × 280 mm working at low gas pressure. The results show that time resolution could be less than 300 ps. Position resolution is consistent with the theoretical calculation about 1.35 mm. Detection efficiency could be approaching 100% gradually with the voltage increasing in different gas pressures. The performances of PPAC have also been verified in beam experiment. Each set of anode wires can be accurately separated in the position spectrum. In the beam experiment, we also got the back-to-back correlation of fission fragments which is one of the direct signals characterizing binary decay.

Radioactive Nuclide Identification of a Fall-Out Sample in Korea (放射能 落塵의 核種檢出의 一例)

  • Kim, Chong-Kuk
    • Journal of the Korean Chemical Society
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    • v.6 no.2
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    • pp.155-157
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    • 1962
  • A tiny dust found at the balcony of the Institute indicated about 8,0000 counts per minute by T.G.C.-2 Geiger-Muller tube (1.8mg/$cm^2$ window-thickness) at the distance of 2cm from the window. The main fission fragments, as identified by the present analysis, are 12.5day Ba-140 and 33.1 day Ce-141. The gamma energies were determined using $2"{\times}2"$ NaI(Tl) scintillation detector connected to RCL-256 channel pulse heigt analyzer. The beta energies were evaluated by Feather plot.

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Calculation of Low-Energy Reactor Neutrino Spectra for Reactor Neutrino Experiments

  • Riyana, Eka Sapta;Suda, Shoya;Ishibashi, Kenji;Matsuura, Hideaki;Katakura, Jun-ichi
    • Journal of Radiation Protection and Research
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    • v.41 no.2
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    • pp.155-159
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    • 2016
  • Background: Nuclear reactors produce a great number of antielectron neutrinos mainly from beta-decay chains of fission products. Such neutrinos have energies mostly in MeV range. We are interested in neutrinos in a region of keV, since they may take part in special weak interactions. We calculate reactor antineutrino spectra especially in the low energy region. In this work we present neutrino spectrum from a typical pressurized water reactor (PWR) reactor core. Materials and Methods: To calculate neutrino spectra, we need information about all generated nuclides that emit neutrinos. They are mainly fission fragments, reaction products and trans-uranium nuclides that undergo negative beta decay. Information in relation to trans-uranium nuclide compositions and its evolution in time (burn-up process) were provided by a reactor code MVP-BURN. We used typical PWR parameter input for MVP-BURN code and assumed the reactor to be operated continuously for 1 year (12 months) in a steady thermal power (3.4 GWth). The PWR has three fuel compositions of 2.0, 3.5 and 4.1 wt% $^{235}U$ contents. For preliminary calculation we adopted a standard burn-up chain model provided by MVP-BURN. The chain model treated 21 heavy nuclides and 50 fission products. The MVB-BURN code utilized JENDL 3.3 as nuclear data library. Results and Discussion: We confirm that the antielectron neutrino flux in the low energy region increases with burn-up of nuclear fuel. The antielectron-neutrino spectrum in low energy region is influenced by beta emitter nuclides with low Q value in beta decay (e.g. $^{241}Pu$) which is influenced by burp-up level: Low energy antielectron-neutrino spectra or emission rates increase when beta emitters with low Q value in beta decay accumulate Conclusion: Our result shows the flux of low energy reactor neutrinos increases with burn-up of nuclear fuel.

Cloning and Expression of Alkaline Phosphatase Gene from Schizosaccharomyces pombe

  • Kang, Sung-Won;Cho, Young-Wook;Park, Eun-Hee;Ahn, Ki-Sup;Lim, Chang-Jin
    • BMB Reports
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    • v.34 no.3
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    • pp.262-267
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    • 2001
  • A cDNA coding alkaline phosphatase (AP) homologue was isolated from a cDNA library of Schizosaccharomyces pombe by colony hybridization. The nucleotide sequence of the cloned cDNA appeared to lack the N-terminal coding region. The genomic DNA encoding alkaline phosphatase homologue was isolated from S. pombe chromosomal DNA using PCR. The amplified DNA fragment was ligated into plasmid pRS315 to generate the recombinant plasmid pSW20. The DNA insert was subcloned as two smaller fragments for nucleotide sequencing. The sequence contains 2,789 by and encodes a protein of 532 amino acids with a molecular mass of 58,666 daltons. The S. pombe cells containing plasmid pSW20 showed much higher AP activity compared with the yeast cells with vector only This indicates that the cloned AP gene apparently encodes AP The predicted amino acid sequence of the S. pombe AP shares homology with those of other known APs.

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