核試驗堆 的英文怎麼說
中文拼音 [héshìyànduī]
核試驗堆
英文
nuclear test reactor-
Based on the terszige and biot theory, initially analyze the economical of this experiment, directly save investment 22 % after compute. after that, computing the settlement of highway foundation, comparing the computing and survey value, the predict formula of vacuum - heaped load combining precompression for designing, this formula show that the distortion law of consolidation progress. at the same time, based on the position and room experiment, analyzes the intension transformation in soft soil and criteria of stabilization control
在太沙基和比奧固結理論的基礎上,先分析了此次試驗的經濟性,經核算直接節約投資22 ,經濟效益十分明顯;隨后對真空堆載聯合預壓法加固軟土路基的沉降量進行了估算,並與實測值作對比分析,得出了真空堆載聯合預壓下的沉降量估算公式,能反映「真空」加固過程的變化規律;同時根據現場和室內試驗,分析了軟土強度的變化,以及給出並驗證了工后沉降控制標準。Corrosion of metals and alloys - aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
金屬和合金的腐蝕.核動力反應堆用鋯合金的耐水腐蝕試驗In - core temperature or primary envelope temperature measurements in nuclear power reactors. characteristics and test methods
核動力反應堆中燃料芯體溫度或主包殼溫度測量.特性和試驗方法I would like to make a positive note of the canadian - russian program of interaction on the g8 themes as part of which two groups of members of the russian president s administration and the foreign ministry went for training to canada in 2005 on issues of protocol work, media support, the creation of the presidency s website, the preparation and approvals of the summit final documents
俄中雙方對快中子實驗反應堆的建設進度表示滿意。去年已進行了地震試驗,組織並安排了中國操作人員的培訓,完成了快中子實驗反應堆反應區技術方案文件的交接工作。核燃料生產的準備工作按計劃進行。Practice for testing graphite and boronated graphite components for high - temperature gas - cooled nuclear reactors
高溫氣冷核反應堆石墨及硼酸化石墨元部件試驗慣例Standard practice for testing graphite and boronated graphite components for high - temperature gas - cooled nuclear reactors
高溫氣冷核反應堆用石墨及硼酸化石墨元部件試驗的標準實施規程Large - scale compaction tests have been carried out and compared with design compacted standards before embankment in order to ensure embankment parameter for dam construction
摘要盤石頭水庫面板堆石壩,在填筑前進行了大型碾壓試驗,復核設計壓實標準,確定各區築壩材料的填築參數,供壩體施工採用。Radiation detectors for the instrumentation and protection of nuclear reactors ; characteristics and test methods
核反應堆儀器和防護用輻射探測器.特性和試驗方法Test investigation on sgtr of single tube break and three - tube break is carried out on hpitf of ciae to deeply understand the thermal - hydraulic behavior during pressurized - water - reactor ( pwr ) sgtr and to provide an integral data base for code assessment and development. the facility, a full height and 1 / 1000 - scale ( by volume ) of qinshan nuclear power plant, incorporates two identical loops with active pumps and steam generators ( sg ). the initial steady state of the test basically simulated that of the reference plant operation
為了深入了解核電廠蒸汽發生器傳熱管破裂事故發生后的熱工水力現象,以及對壓水堆( pwr )核電廠系統分析程序進行分析和評價,在高壓綜合試驗裝置上開展了蒸汽發生器傳熱管破裂試驗研究高壓綜合試驗裝置以秦山核電廠主迴路系統為模擬對象,該裝置為雙環迴路系統,容積比為1 : 1000 ,高度比為1 : 1 。Periodic tests and monitoring of the protection system of nuclear reactors
核反應堆防護系統的定期試驗和監視Nuclear power plants - in - core instrumentation - characteristics and test methods of self - powered neutron detectors
核電廠站.堆芯測試設備.自動力的中子探測器的特性和試驗方法Nuclear power plants - in - core instrumentation - characteristics and test methods of self - powered neutron detectors ; amendment 1
核電廠.堆芯儀器儀表.自給能中子探測器的特性和試驗方法.修改1分享友人