• Title/Summary/Keyword: Fission

Search Result 700, Processing Time 0.024 seconds

Calculation of the fission products for neutron-induced fission of 235U

  • Changqi Liu;Kai Tao;Liming Huang;Dejun E;Xiaohou Bai;Zhanwen Ma
    • Nuclear Engineering and Technology
    • /
    • v.56 no.5
    • /
    • pp.1895-1901
    • /
    • 2024
  • The fission model, G4ParaFissionModel, was enhanced in this study, mainly focusing on refining the energy dependence of the peak-to-valley ratio in the mass distribution and the energy dependence of the average total kinetic energy (TKE). The enhanced model was employed to investigate the characteristics of fission products from 235U(n, f) reaction. The calculated results, including fission yield, TKE distribution, prompt fission neutron and gamma spectra, were compared with both evaluated and experimental data. The comparison shows that these physical observables related nuclear data, which are of importance for developments of the nuclear power and physics, can be reasonably well reproduced.

Fission counter array for pulse-mode measurements of high-flux and high-energy neutrons

  • Pilsoo Lee
    • Nuclear Engineering and Technology
    • /
    • v.56 no.9
    • /
    • pp.3553-3557
    • /
    • 2024
  • This manuscript describes a neutron counting system based on cylindrical fission counters that can monitor neutron activity for high-energy neutron flux above 10 MeV under electrically noisy environments with intense gamma rays. Miniature fission counters with depleted uranium as sensitive material and modular electronics were built for digital signal processing and high-countrate operation. The counters are 9.5 mm in diameter and 71.1 mm in active length. The author presents the results of Monte Carlo simulations of the fission-counter response for selected neutron sources and energies based on ENDF7.1, JENDL-5, and TENDL-2021 nuclear data libraries from 1 meV to 200 MeV. For a white neutron beam (Ē = 16.36 MeV) that irradiates the front face of a counter, the intrinsic efficiency is evaluated to be (2.24 ± 0.02) × 10-5 counts/n, while the efficiency of the counter in the array appears to increase by at most 6.7%.

The Change of Mitochondrial Fusion and Fission in human Skeletal Muscle with Aging

  • Cho, Hyung-Jun;Park, Soo-Yeon
    • Biomedical Science Letters
    • /
    • v.18 no.2
    • /
    • pp.112-122
    • /
    • 2012
  • A gradual change of molecules that are related in fission and fusion is occurred during aging process. Although aging effects on mitochondrial fusion and fission are investigated, it is still unclear that the extent of the change in mitochondria fusion and fission periodically. In this study we investigated the changes of mitochondrial proteins involved in fusion (Mfn2, Opa1) and fission (Drp1, Fis1) in the human gracilis muscle ranging from 10 to 50 years of age (n=40). The gracilis muscle showed a significant increase in muscle apoptotic changes in the age of 50s compared with 10s by using in situ terminal deoxynucleotidyl transferase-mediated dUTP nick end-labeling (TUNEL). The expression levels of Drp1 and Fis1 (P<0.01, P<0.05) mRNA were significantly elevated and the Mfn2 and Opa1 (P<0.01, P<0.05) levels were decreased from older individuals. The ratio of fission and fusion was altered and the level of increment of fission gene was greater than fusion gene decrement in the age of 50s. These findings suggest that changes of mitochondrial fusion and fission proteins related with aging might contribute to aged muscle apoptosis.

Acceleration method of fission source convergence based on RMC code

  • Pan, Qingquan;Wang, Kan
    • Nuclear Engineering and Technology
    • /
    • v.52 no.7
    • /
    • pp.1347-1354
    • /
    • 2020
  • To improve the efficiency of MC criticality calculation, an acceleration method of fission source convergence which gives an improved initial fission source is proposed. In this method, the MC global homogenization is carried out to obtain the macroscopic cross section of each material mesh, and then the nonlinear iterative solution of the SP3 equations is used to determine the fission source distribution. The calculated fission source is very close to the real fission source, which describes its space and energy distribution. This method is an automatic computation process and is tested by the C5G7 benchmark, the results show that this acceleration method is helpful to reduce the inactive cycles and overall running time.

A Study on Amplification and Deformation of Long-Period Waves (해양장파의 증폭과 변형에 대한 연구)

  • Bae, Jae-Seok;Shin, Choong-Hun;Cho, Young-Joon;Yoon, Sung-Bum
    • Proceedings of the Korea Water Resources Association Conference
    • /
    • 2011.05a
    • /
    • pp.45-49
    • /
    • 2011
  • 본 연구에서는 일본 전력중앙연구소에서 수행된 wave fission 수리모형실험 자료를 토대로 일차원 FUNWAVE 수치모형을 이용하여 wave fission 현상을 재현하는 수치모의를 수행하였다. FUNWAVE 수치모형은 Boussinesq 방정식을 지배방정식으로 사용하고 있으며 파의 분산효과와 비선형 효과를 고려할 수 있는 수치모형이다. 따라서 wave fission의 주된 발생원인인 분산효과와 비선형효과에 대한 고려를 통해 수치모의 결과는 수리모형실험의 관측치와 상당히 잘 일치함을 확인할 수 있었다. 또한, 본 연구에서는 추가적으로 해수의 흐름이 존재하는 경우를 가정하고 수로 내 일정한 유량의 흐름을 추가하여 wave fission 일차원 수치모의를 수행하였다. 수치모의 결과 파의 진행방향과 반대방향으로 흐름이 존재하는 경우 wave fission으로 인한 수면변위의 크기가 상대적으로 증가함을 확인할 수 있었으며 반대로 파의 진행방향과 동일한 방향으로 흐름이 존재하는 경우 wave fission으로 인한 수면변위의 크기가 상대적으로 감소함을 확인할 수 있었다.

  • PDF

Numerical studies on the important fission products for estimating the source term during a severe accident

  • Lee, Yoonhee;Cho, Yong Jin;Lim, Kukhee
    • Nuclear Engineering and Technology
    • /
    • v.54 no.7
    • /
    • pp.2690-2701
    • /
    • 2022
  • In this paper, we select important fission products for the estimation of the source term during a severe accident of a PWR. The selection is based on the numerical results obtained from depletion calculations for the typical PWR fuel via the in-house code named DEGETION (Depletion, Generation, and Transmutation of Isotopes on Nuclear Application), release fractions of the fission products derived from NUREG-1465, and effective dose conversion coefficients from ICRP 119. Then, for the selected fission products, we obtain the adjoint solutions of the Bateman equations for radioactive decay in order to determine the importance of precursors producing the aforementioned fission products via radioactive decay, which would provide insights into the assumption used in MACCS 2 for a level 3 PSA analysis in which up to six precursors are considered in the calculations of radioactive decays for the fission product after release from the reactor.

Effects of Gap Resistance and Failure Location on prompt Fission Gas Release from a Cladding Breach

  • Tak, Nam-Il;Chun, Moon-Hyun;Ahn, Hee-Jin;Park, Jong-Kil;Rhee, In-Hyoung
    • Proceedings of the Korean Nuclear Society Conference
    • /
    • 1997.05a
    • /
    • pp.184-189
    • /
    • 1997
  • A prompt fission gas release model incorporating the resistance to gas flow in the gap was developed and the effects of gap resistance and failure location on prompt fission gas release from the cladding breach were assessed. The process of prompt fission gas release from the plenum and gap into the coolant was modeled in accordance with three major phenomena: (1) transient gas flow in the gap, (2) the growth of the fission gas bubble while it is still attached to the breach, and (3) the detachment of the fission gas bubble from the breach and mixing with the coolant. The cumulative mass release fraction by the present model was calculated for the case of Young-Gwang 3 & 4 nuclear fuel rod as a typical example. The results showed that the release behavior of prompt fission gas with time was different from the frictionless model which has frequently been used in a simplified approach, and that the location of cladding failure was another key factor for the prompt fission gas release process due to the resistance in the gap.

  • PDF

Semi-empirical model to determine pre- and post-neutron fission product yields and neutron multiplicity

  • Jounghwa Lee;Young-Ouk Lee;Tae-Sun Park;Peter Schillebeeckx;Seung-Woo Hong
    • Journal of the Korean Physical Society
    • /
    • v.80
    • /
    • pp.953-963
    • /
    • 2022
  • Post-neutron emission fission product mass distributions are calculated by using pre-neutron emission fission product yields (FPYs) and neutron multiplicity. A semi-empirical model is used to calculate the pre-neutron FPY, first. Then the neutron multiplicity for each fission fragment mass is used to convert the pre-neutron FPY to the post-neutron FPY. In doing so, assumptions are made for the probability for a pre-emission fission fragment with a mass number A* to decay to a post-emission fragment with a mass number A. The resulting post-neutron FPYs are compared with the data available. The systems where the experimental data of not only the pre- and post-neutron FPY but also neutron multiplicity are available are the thermal neutron-induced fission of 233U, 235U and 239Pu. Thus, we applied the model calculations to these systems and compared the calculation results with those from the GEF and the data from the ENDF and the EXFOR libraries. Both the pre- and post-neutron fission product mass distributions calculated by using the semi-empirical model and the neutron multiplicity reproduce the overall features of the experimental data.

A CLASSIFICATION OF UNIQUELY DIFFERENT TYPES OF NUCLEAR FISSION GAS BEHAVIOR

  • HOFMAN GERARD L.;KIM YEON SOO
    • Nuclear Engineering and Technology
    • /
    • v.37 no.4
    • /
    • pp.299-308
    • /
    • 2005
  • The behavior of fission gas in all major types of nuclear fuel has been reviewed with an emphasis on more recently discovered aspects. It is proposed that the behavior of fission gas can be classified in a number of characteristic types that occur at a high or low operating temperature, and/or at high or low fissile burnup. The crystal structure and microstructure of the various fuels are the determinant factors in the proposed classification scheme. Three types of behavior, characterized by anisotropic $\alpha$-U, high temperature metallic $\gamma$-U, and cubic ceramics, are well-known and have been extensively studied in the literature. Less widely known are two equally typical low temperature kinds: one associated with fission induced grain refinement and the other with fission induced amorphization. Grain refinement is seen in crystalline fuel irradiated to high burnup at low temperatures, whereas breakaway swelling is observed in amorphous fuel containing sufficient excess free-volume. Amorphous fuel, however, shows stable swelling if insufficient excess free-volume is available during irradiation.

The coordinated regulation of mitochondrial structure and function by Drp1 for mitochondrial quality surveillance

  • Cho, Hyo Min;Sun, Woong
    • BMB Reports
    • /
    • v.52 no.2
    • /
    • pp.109-110
    • /
    • 2019
  • Mitochondrial morphology is known to be continuously changing via fusion and fission, but it is unclear what the biological importance of this energy-consuming process is and how it develops. Several data have suggested that mitochondrial fission executed by Drp1 is necessary to select out a damaged spot from the interconnected mitochondrial network, but the precise mechanism for the recognition and isolation of a damaged sub-mitochondrial region during mitochondrial fission is yet unclear. Recently, Cho et al. found that the mitochondrial membrane potential (MMP) is transiently reduced by the physical interaction of Drp1 and mitochondrial Zinc transporter, Zip1, at the fission site prior to the typical mitochondrial division, and we found that this event is essential for a mitochondrial quality surveillance. In this review, Cho et al. discuss the role of a mitochondrial fission in the mitochondrial quality surveillance system.