• Title/Summary/Keyword: waste fuel

Search Result 1,724, Processing Time 0.032 seconds

Mechanical Integrity Evaluation on the Degraded Cladding Tube of Spent Nuclear Fuel Under Axial and Bending Loads During Transportation

  • Lee, Seong-Ki;Lee, Dong-Hyo;Park, Joon-Kyoo;Kim, Jae-Hoon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.19 no.4
    • /
    • pp.491-501
    • /
    • 2021
  • This paper aims to evaluate the mechanical integrity for Spent Nuclear Fuel (SNF) cladding under lateral loads during transportation. The evaluation process requires a conservative consideration of the degradation conditions of SNF cladding, especially the hydride effect, which reduces the ductility of the cladding. The dynamic forces occurring during the drop event are pinch force, axial force and bending moment. Among those forces, axial force and bending moment can induce transverse tearing of cladding. Our assessment of 14 × 14 PWR SNF was performed using finite element analysis considering SNF characteristics. We also considered the probabilistic procedures with a Monte Carlo method and a reliability evaluation. The evaluation results revealed that there was no probability of damage under normal conditions, and that under accident conditions the probability was small for transverse failure mode.

An Experimental Study on the Bed Combustion Phenomena in MSW(Municipal Solid Waste) Incinerator (폐기물 소각로 베드에서의 연소현상 관찰을 위한 실험적 연구)

  • Min, Jee Hyun;Shin, Donghoon;Choi, Sangmin
    • Transactions of the Korean Society of Mechanical Engineers B
    • /
    • v.23 no.2
    • /
    • pp.159-165
    • /
    • 1999
  • Experimental studies have been performed to observe the basic phenomena of waste bed combustion in MSW incinerator. A reduced scale apparatus was utilized to simulate the combustion behavior in real plant with 1-dimensional transient behavior at the experimental setup, which uses wet cubic wood with ash content as simulated waste. LHV (lower heating value) of solid fuel, fuel particle size and flow rate of combustion air were taken as important parameters of the bed combustion. For the quantitative analysis, FPR (flame propagation rate), TBT (total burn-out time) and PBT (particle burn-out time) was defined. LHV represent the capability of heat release of the fuel, so that a higher LHV results in faster reaction rate of the fuel bed, which is shown by higher FPR. Fuel particle size is related with surface area per unit mass as well as heat and mass transfer coefficient. As the particle size increases the FPR decreases owing to decreasing specific surface area. Air injection supplies oxygen to the reaction zone. However oversupply of combustion air increases convection cooling of the bed and possibly extinguishes the flame.

A Study on the Effect of Reclaiming-Fuel in Coement Kiln (시멘트 공장에서의 재생연료 사용효과 연구)

  • 김도겸;이장화
    • Proceedings of the Korea Concrete Institute Conference
    • /
    • 1996.10a
    • /
    • pp.37-43
    • /
    • 1996
  • The high Temperatures and long residence times in the combustion zones of cement kiln can use to burn liquid and solid wastes, such as fuel-wastes, sludges and tire-wastes. To the lastest time, treatment methods of industrial waste are incineration treatment, ocean dumping and land dumping. These are the main methods, but all of them may cause vatious kinds of secondary pollution, including air pollution and water pollution. From this point of view, to reuse the Reclaiming-Fuel in Cement Kiln is the most outstanding waste treatment plant in the world and dose not cause any pollution at all.

  • PDF

Requirements for the Transportation of Spent Nuclear Fuel (SNF) in Terms of Fuel Integrity and Data Needed According to

  • Noh, J.S.;Kim, Y.K.;Kim, T.W.
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2017.10a
    • /
    • pp.115-116
    • /
    • 2017
  • For the safe transportation of SNF and licensing, the integrity of SNF should be evaluated carefully. Researches to obtain the data for SNF cladding properties, i.e. impact toughness, DBTT (hydride behavior) when evaluating transportation of SNF, shall be precisely implemented by simulating the condition of real SNF to the hilt, accordingly.

  • PDF

Technical Issues of Remote Assembler for TRU Fuel Assembly

  • Lee, Young-Ho;Park, Sang-Gyu;Kim, Ki-ho;Park, Jeong-Yong;Lee, Chan-Bock
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2017.10a
    • /
    • pp.91-92
    • /
    • 2017
  • In this study, assembling procedure of TRU fuel assembly was reviewed and divided into rod bundle assembling, mating preassemblies and welding, and inspection and non-destructive examination. Based on this assumption, the design criteria of a remote assembler for TRU fuel assembly of PGSFR is defined and predictable technical issues are proposed.

  • PDF

Spent Nuclear Fuel Safety Evaluation Methodology (SSEM) for Storage and Transportation

  • Kim, Y.K.;Noh, J. S.;Lee, S.K.;Kim, T.W.
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2017.10a
    • /
    • pp.57-58
    • /
    • 2017
  • New approach to achieve the safety goals in transportation and dry storage of SNF, so called SSEM has been proposed. The main concept of the SSEM is that it simplifies the reviewing processes of each campaign of the transportation or storage of SNF with standard format. This SSEM could be considered as a model case for assuring public that the SNF be managed safely.

  • PDF