熱核發電廠 的英文怎麼說
中文拼音 [rèhéfādiànchǎng]
熱核發電廠
英文
fusion power plant-
To major in developing the power plant simulators and thermal energy automation systems for several years, making the selection and comparison with different types of the nuclear power plant designs and equipments, and doing some research in the waste burning technology
從事電廠模擬機和熱工自動化控制系統的開發工作多年；從事核電設備技術特點的比較與選型工作；從事垃圾發電技術研究。Based on the analysis of the tangshan xinqu and qian an and gangyao thermoelectric power units, a model of real - time ordering power by heat on combined heat and power based on working chart is erected, a method of related generating electric power appraisement is set up, and the software of ordering power by heat on combined heat and power system is developed. based on delphi language and sql server database, the structure and functions of ordering power by heat on combined heat and power system are discussed, and a method of data processing is also put forward. the function of data storage and past data query and account report forms is achieved
為解決此問題，本文以唐山新區熱電廠、遷安熱電廠、缸窯熱電廠的供熱機組為例，根據其機組工況圖建立機組「以熱定電「運行的數學模型，並編制了相應的軟體文中介紹了基於delphi語言與sqlserver數據庫的軟體結構功能與特點，軟體可實時給出各參數和熱電聯產以熱定電考核曲線，能夠實現數據存儲、歷史數據查詢、統計報表等多種功能，這對于電力管理部門合理地為熱電廠下達發電指標，加強和完善對熱電聯產企業的管理，提供了理論依據和技術支持。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 。The break was assumed to be a single tube double - ended and three - tube double - ended shear break. the diameter of the break orifice is 0. 876mm and 1. 518mm respectively. the characteristic responses of main thermal - hydraulic parameters, such as primary pressure, secondary pressure, break flow rate, pressurizer level, secondary side level of steam generator and so on, were presented in this thesis
試驗再現了核電廠蒸汽發生器單根傳熱管雙端斷裂事故和三根傳熱管雙端斷裂事故發生后的熱工水力現象，給出了事故過程中一次系統壓力、二次系統壓力、破口流量、蒸汽發生器二次側水位、穩壓器水位、元件表面溫度等主要參數的瞬態響應。分享友人