nuclear pressure vessel 中文意思是什麼

nuclear pressure vessel 解釋
核壓力容器
  • nuclear : adj 1 核的，成核的；有核的。2 【物理學】原子核的；原子能的；原子彈的；核動力的。3 〈比喻〉核心的...
  • pressure : n 1 壓；按；擠；榨。2 【物理學】壓力，壓強；大氣壓力；電壓。3 精神壓力，政治[經濟、輿論等]壓力。4...
  • vessel : n. 1. 容器，器皿〈桶、缽、碗等〉。2. 船，艦；飛船。3. 〈喻、謔〉人。4. 【解剖學；動物學】管，脈管，血管；【植物；植物學】導管。
  1. Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; division 1 ; appendices ; 2005 addenda july 1, 2005

    Asme鍋爐和壓力容器規范.第3部分:核設備元件結構原理. 1類.附錄.補充件2005
  2. Positioning of moving table for checking screw holes of nuclear reactor pressure vessel

    核反應堆壓力殼螺栓孔檢測自動小車的定位
  3. Asme boiler pressure vessel code - section 11 : rules for inservice inspection of nuclear power plant components

    Asme鍋爐和壓力容器規程.第11節:核電廠部件運行期間檢測規則
  4. Asme boiler pressure vessel code - section 11 : rules for inservice inspection of nuclear power plant components ; 2005 addenda july 1, 2005

    Asme鍋爐和壓力容器規范.第11部分:核電站組件在使用中進行檢驗的原則.補充件2005
  5. The program fearpv is applied to 3 - d transient sealing analysis of nuclear pressure vessel during the total process, including bolt pretensioning process, heating and compression process, thermostated heating and constant pressure process, and the cooling and decompressing process. according to the analysis and computational results in this thesis, although the actual structure and work conditions of the pressure vessel in nuclear power station are much more complex than that of the pressure vessel model, the program fearpv still can get quite good convergence on the plasticity and

    由本文分析計算可知，雖然電站核壓力容器的結構及計算工況較壓力容器模擬體復雜得多，然而反應堆壓力容器瞬態密封有限元分析程序對塑性迭代和接觸迭代仍具有很好的收斂性，數值穩定性好，得到的結果具有良好的規律性，在升溫、升壓、恆溫、恆壓、降溫和降壓等過程中其規律和壓力容器模擬體基本相似。
  6. Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; division 3 ; containment systems and transport packaging for spent nuclear fuel and high level radioactive waste

    Asme鍋爐和壓力容器規程.第3節:核設施元部件製造規則.第3分冊.消耗核燃料和高級放射性廢物用盛裝系統和運輸包裝
  7. Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; division 3 ; containment systems and transport packaging for spent nuclear fuel and high level radioactive waste ; 2005 addenda july 1, 2005

    Asme鍋爐和壓力容器規范.第3部分:核設備元件結構原理. 3類.失效核燃料和高等級放射性廢物的密封系統和運輸包裝.補充件2005
  8. Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; subsection nca ; general requirements for division 1 and division 2

    Asme鍋爐和壓力容器規程.第3節:核設施元部件製造規則.第nca子節. 1和2分冊的一般要求
  9. Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; subsection nca ; general requirements for division 1 and division 2 ; 2005 addenda july 1, 2005

    Asme鍋爐和壓力容器規范.第3部分:核設備元件結構原理. nca部分. 1類和2類的一般要求.補充件2005
  10. Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; division 2 ; code for concrete reactor vessels and containments

    Asme鍋爐和壓力容器規程.第3節:核設施元部件製造規則.第2分冊.混凝土反應堆容器和外殼規范
  11. Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; division 2 ; code for concrete reactor vessels and containments ; 2005 addenda july 1, 2005

    Asme鍋爐和壓力容器規范.第3部分:核設備元件結構原理. 2類.混凝土反應堆容器和安全殼規范.補充件2005
  12. Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; division 1 ; subsection ng ; core support structures

    Asme鍋爐和壓力容器規程.第3節:核設施元部件製造規則.第1分冊.第ng子節.堆芯支撐結構
  13. Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; division 1 ; subsection ng ; core support structures ; 2005 addenda july 1, 2005

    Asme鍋爐和壓力容器規范.第3部分:核設備元件結構原理. 1類. ng部分.核心支撐結構.補充件2005
  14. Asme boiler pressure vessel code - section 3 : rules for construction of nuclear facility components ; division 1 ; subsection nf ; supports

    Asme鍋爐和壓力容器規程.第3節:核設施元部件製造規則.第1分冊.第nf子節.支撐件
  15. Influence of pressurized thermal shock on nuclear pressure vessel

    周向斜接管內壓圓柱形容器的應力集中
  16. The theme comes from the project the program development for transient sealing in reactor pressure vessel. this project is the subproject of the research project commissioned by the technical industry committee, department of defense, which is about the advanced reactor design in advanced pressurized water reactor nuclear power station

    本論文來源於國防科學技術工業委員會關于先進壓水堆核電站先進反應堆設計技術研究項目（批文號：科工委[ 1999 ] 149號）的子課題「反應堆壓力容器瞬態密封程序研製」 。
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