• Title/Summary/Keyword: Cool-Down

Search Result 267, Processing Time 0.027 seconds

Generation of Pressure/Temperature Limit Curve for Reactor Operation (원자로 운전을 위한 압력/온도 한계곡선의 설정)

  • 정명조;박윤원
    • Computational Structural Engineering
    • /
    • v.10 no.4
    • /
    • pp.155-164
    • /
    • 1997
  • A reactor pressure vessel, which contains fuel assemblies and reactor vessel internals, has the thermal stress resulting from the cool-down and heat-up of the vessel wall in combination with the pressure stress from system pressure resulting in large stresses. The combination of the pressure stress and thermal stress along with a decrease in fracture toughness may cause through-wall propagation of a relatively small crack. Therefore, it is necessary to define the relations between operating pressure and temperature during cool-down and heat-up. In this study, theory of fracture mechanics for a pressure/temperature limit curve is investigated and a numerical procedure for generating it is developed. Plant-specific limit curves for the Kori unit 1 plant, the oldest nuclear power plant in Korea, have been obtained for several cooling and heating rates and their results are discussed.

  • PDF

Transient Simulation of an Automotive Air-Conditioning System (자동차 에어컨 비정상과정 시뮬레이션)

  • 오상한;원성필
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
    • /
    • v.13 no.11
    • /
    • pp.1089-1096
    • /
    • 2001
  • The cool-down performance after soaking is very important in an automotive air-conditioning system and is considered as the key design variable. Therefore, understanding of the overall transient characteristics of the system is essential to the preliminary design as well as steady-state characteristics. The objective of this study is to develop a computer simulation model and estimate theoretical1y the transient performance of an automotive air-conditioning system. To accomplish this, a mathematical modelling of each component, such as compressor, condenser, expansion valve, and evaporator, is presented first of all. For a detailed calculation, condenser and evaporator are divided into many subsections. Each sub-section is an elemental volume for modelling. In models of expansion valve and compressor, dynamic behaviors are not considered in an attempt to simplify the ana1ysis, but the quasi-static ones are just considered, such as the relation between mass flow rate and pressure drop in expansion device, polytropic process in compressor, etc. The developed simulation model is validated with a comparison to laboratory test data of an automotive air-conditioning system. The overall time-tracing properties of each component agreed fairly well wish those of test data in this case.

  • PDF

RCD success criteria estimation based on allowable coping time

  • Ham, Jaehyun;Cho, Jaehyun;Kim, Jaewhan;Kang, Hyun Gook
    • Nuclear Engineering and Technology
    • /
    • v.51 no.2
    • /
    • pp.402-409
    • /
    • 2019
  • When a loss of coolant accident (LOCA) occurs in a nuclear power plant, accident scenarios which can prevent core damage are defined based on break size. Current probabilistic safety assessment evaluates that core damage can be prevented under small-break LOCA (SBLOCA) and steam generator tube rupture (SGTR) with rapid cool down (RCD) strategy when all safety injection systems are unavailable. However, previous research has pointed out a limitation of RCD in terms of initiation time. Therefore, RCD success criteria estimation based on allowable coping time under a SBLOCA or SGTR when all safety injection systems are unavailable was performed based on time-line and thermal-hydraulic analyses. The time line analysis assumed a single emergency operating procedure flow, and the thermal hydraulic analysis utilized MARS-KS code with variables of break size, cooling rate, and operator allowable time. Results show while RCD is possible under SGTR, it is impossible under SBLOCA at the APR1400's current cooling rate limitation of 55 K/hr. A success criteria map for RCD under SBLOCA is suggested without cooling rate limitation.

Thermal stress intensity factor solutions for reactor pressure vessel nozzles

  • Jeong, Si-Hwa;Chung, Kyung-Seok;Ma, Wan-Jun;Yang, Jun-Seog;Choi, Jae-Boong;Kim, Moon Ki
    • Nuclear Engineering and Technology
    • /
    • v.54 no.6
    • /
    • pp.2188-2197
    • /
    • 2022
  • To ensure the safety margin of a reactor pressure vessel (RPV) under normal operating conditions, it is regulated through the pressure-temperature (P-T) limit curve. The stress intensity factor (SIF) obtained by the internal pressure and thermal load should be obtained through crack analysis of the nozzle corner crack in advance to generate the P-T limit curve for the nozzle. In the ASME code Section XI, Appendix G, the SIF via the internal pressure for the nozzle corner crack is expressed as a function of the cooling or heating rate, and the wall thickness, however, the SIF via the thermal load is presented as a polynomial format based on the stress linearization analysis results. Inevitably, the SIF can only be obtained through finite element (FE) analysis. In this paper, simple prediction equations of the SIF via the thermal load under, cool-down and heat-up conditions are presented. For the Korean standard nuclear power plant, three geometric variables were set and 72 cases of RPV models were made, and then the heat transfer analysis and thermal stress analysis were performed sequentially. Based on the FE results, simple engineering solutions predicting the value of thermal SIF under cool-down and heat-up conditions are suggested.

Experimental study on natural circulation using liquid nitrogen for superconducting applications

  • Choi, Yeon Suk
    • Progress in Superconductivity and Cryogenics
    • /
    • v.15 no.3
    • /
    • pp.49-52
    • /
    • 2013
  • An experiment to investigate the natural circulation of a cryogen has been performed. The study is motivated mainly by our recent development of cryogenic cooling system for prototype superconducting cyclotron without any circulating pump. In the natural circulation loop system, a cooling channel is attached on the outer surface of the aluminium block and the liquid nitrogen passes through inside of the channel to cool the block indirectly. A cryocooler as a heat sink is located at the top to re-condense cryogenic vapor coming from the aluminium block in which electrical heater is installed as a heat source. The main dimensions are determined using the relevant analysis and the natural circulation loop is successfully fabricated. The temperature distributions in the loop are measured during initial cool-down process and in steady state, from which the modified Grashof numbers are calculated and compared with the existing correlation estimated with one-dimensional analysis for steady state flow.

Development of a Oil-Cooler for High-Speed CNC Lathe (고속 CNC선반용 공랭식 오일 냉각기 개발)

  • Yum, Man-Oh
    • Journal of the Korean Society of Manufacturing Process Engineers
    • /
    • v.2 no.4
    • /
    • pp.11-16
    • /
    • 2003
  • Recently, CNC lathe is in need of higher speed for precision works. So more intensive and compact heat exchanger is necessary to cool down the heat in short time from drills and works during high speed working. In this study, to increase heat transfer coefficient per unit volume, inner groove tube is designed and compact oil cooler, 57% volume of conventional type, is manufactured. The heat transfer performance is experimented and is compared with the performance of conventional type.

  • PDF

Neon liquefaction system manufacture and characteristic that use GM refrigerator (GM 냉동기를 이용한 네온액화시스템 제작과 특성)

  • 권운식;손명환;백승규;이언용;권영길;서정세;문태선;조창호
    • Proceedings of the Korea Institute of Applied Superconductivity and Cryogenics Conference
    • /
    • 2003.10a
    • /
    • pp.278-280
    • /
    • 2003
  • We manufactured neon liquefaction system for cooling system of HTS motor. The neon liquefaction system consists of a GM refrigerator, a liquefaction vessel and a vacuum chamber. It is found that the neon starts to be liquefied in the liquefaction vessel after 35 minutes of cool-down from gas state of 294k. Capacity of neon liquefaction system and the liquefaction rate were about 36W, 0.1g/s.

  • PDF

A Development of Fabrication of Processes of SU-8 PR Mold for UV-LIGA (UV-LIGA 공정용 SU-8 PR 몰드 제작 공정 개발)

  • 김창교
    • Proceedings of the KAIS Fall Conference
    • /
    • 2002.11a
    • /
    • pp.238-242
    • /
    • 2002
  • 본 논문에서는 3차원 마이크로구조물을 위한 새로운 Thick Photoresist(TPR) 공정 기술을 개발하였다. 일반적으로 Thin Photoresist는 얇은 두께로 코팅을 할 수 있다. 그러나 SU-8과 같은 TRP은 몇 십 ㎛ 또는 그 이상으로 코팅이 가능하고 높은 종횡비를 얻을 수 있다. SU-8과 같은 TPR을 사용하여 마이크로구조물을 제작할 때 TPR의 crack들은 bake시의 갑작스런 tool down에 의한 stress에 의해 나타나는데, 이러한 crack들은 마이크로구조물의 도금을 어렵게 만든다. 본 논문에서는 TPR의 코팅, baking 시간 조절, cool down과 PEB(Post Expose Sake) 시간 조절을 통하여 stress에 의해 발생되는 crack이 없는 3차원 마이크로구조물을 제작할 수 있는 새로운 공정 기술을 개발하였다.

Phase Transition and Thermal Expansion Behavior of Zirconia Setter Fabricated from Fused CaO Stabilized Zirconia

  • Park, Ji-Hoon;Bang, Il-Hwan;Lee, Sang-Jin
    • Journal of the Korean Ceramic Society
    • /
    • v.56 no.2
    • /
    • pp.184-190
    • /
    • 2019
  • To improve resistance in thermal shock of zirconia setter which is frequently and repeatedly exposed to high temperature, high degree of porosity and control of thermal expansion are needed for which the fused CSZ (CaO stabilized zirconia) is used to produce the zirconia setter. In the present study, the effects of sintering temperature, cool down condition, addition of CaO stabilizer, and addition of other additives on phase transition and thermal expansion behavior of the fabrication process of zirconia setter, were examined. The zirconia setter, fabricated with fused CSZ at 1550℃, exhibited 20.4 MPa of flexural strength, 6.8% of absorbance, and 27.9% of apparent porosity. The rapid change in thermal expansion of zirconia setter is observed at temperature around 800℃, and it was reduced by low firing temperature, slowed cooled down, and addition of CaO.