pwr Pwr,;pwr＝power.
Pwr,; pwr＝power. “power pwr“ 中文翻譯： 功率、電源“pwr mon“ 中文翻譯： 功率監視器“pwr plt“ 中文翻譯： 動力裝置“pwr power“ 中文翻譯： 電源功率; 電源動力“pwr sup“ 中文翻譯： 電源“pwr-sw“ 中文翻譯： 開機信號“tx pwr“ 中文翻譯： 發射功率“light water pwr“ 中文翻譯： 輕水壓水堆“pressurized water reactor (pwr)“ 中文翻譯： 壓水式反應器“pwr (= pressurized water reactor)“ 中文翻譯： 壓水式反應器“pwr power or power position“ 中文翻譯： 電源或強力位置“pwr stng oil cooler“ 中文翻譯： 動力轉向油冷卻器“pwron after pwr-fail“ 中文翻譯： 電源回復后的電源失敗選擇“pwp peasants and workers party of india“ 中文翻譯： 印度農工黨“pwp“ 中文翻譯： 純水滲透率; 肺毛細血管楔壓“pwoven bag“ 中文翻譯： 聚丙烯編織帶“pwood“ 中文翻譯： 一堆木材
px |
|
Abstract : a thermo - economical diagnostic mathematical model for pressurizedwater reactor ( pwr ) nuclear cogeneration plant is proposed based on heat assignment method . this model simplifies the calculation of thermal system and can be used to calculate the index variations caused by heating steam parameters as temperature , return percentage and return place of the return water . some examples are given to show the usefulness of this model 文摘:基于熱電聯產機組熱量法分配的特點，建立了熱電聯產壓水堆機組熱力系統發生變化對熱經濟性指標影響的計算模型，提出了供熱系統參數? ?供熱回水率、回水溫度、回水地點變化對壓水堆機組熱經濟性影響的定量診斷數學模型，可將復雜的熱力系統全面計算簡化成3個一次方程.通過實例計算，驗證了所提數學模型是正確可行的，同時具有概念清晰、計算簡捷的特點 |
|
The paper researched the model and simulation of pwr nuclear power plant and found the basis for the research and simulation of “ ads “ . the paper mainly include : 1 . the modeling of main component of the pwr nuclear power plant main circuit system and established the suitable teaching system ' s physics - mathematics modeling for microcomputer simulation 本文研究了壓水堆核電站系統的建模和仿真問題，初步完成了pwr核電站物理運行的pc機教學仿真演示平臺系統，同時為“加速器驅動潔凈核能系統” ( ads )的基礎研究成果演示與仿真奠定基礎。 |
|
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回路系統為模擬對象，該裝置為雙環回路系統，容積比為1 ： 1000 ，高度比為1 ： 1 。 |
|
There was a joyous celebration that sunday , with many former residents , some in wheelchairs , others leaning on walking sticks , along with their children and grandchildren , making their way up the hill to the moravian church . master initiated new seekers there after her lecture at the pwr . old friends were reunited 星期日當天是個充滿歡慶喜悅的日子，有許多以前的居民，或坐著輪椅或拄著?杖，帶著他們的兒孫一路來到小山丘上的摩拉維亞教堂師父在世界宗教大會開示完畢后，曾在這里幫一些求道者印心，欣慶老友得以重聚相逢。 |
|
A mathematic model of reactor , steam generator , pressurizer is developed based on characteristic of pwr coolant system . for reactor , the point reactor kinetics equation with six - group delayed neutrons is used and influence of coolant ' s and fuel ' s temperature is considered , conduction model of one dimension and single - channel model is used in thermal and hydraulic calculation , third - order hermite polynomial is used to solve the point reactor kinetics equation 對于反應堆，在物理計算中采用了帶有六組緩發中子的點堆方程，同時考慮了多普勒效應及冷卻劑溫度效應對反應性的影響；在熱工水力計算中采用了一維的熱傳導模型與單通道模型；在求解點堆方程中采用了hermite插值的方法，克服了點堆方程的剛性問題。 |
|
The enriched uranium fuel in the form of uranium dioxide for the pwr is fabricated into a few hundreds of small fuel pellets , which are stacked up , enclosed and sealed in a zirconium alloy tube of about 3 . 8 metres in length and 9 . 5 mm in diameter ( the fuel rod ) 濃縮鈾經過加工后會制成小圓柱型的二氧化鈾芯塊，然后數百個小指頭般大的芯塊會被堆疊在一條長3 . 8米、直徑9 . 5毫米的鋯合金包殼管(燃料棒)中并加以密封。 |
|
The enriched uranium fuel in the form of uranium dioxide for the pwr is fabricated into a few hundreds of small fuel pellets , which are stacked up , enclosed and sealed in a zirconium alloy tube of about 3 . 8 metres in length and 9 . 5 mm in diameter the fuel rod 濃縮鈾經過加工后會制成小圓柱型的二氧化鈾芯塊，然后數百個小指頭般大的芯塊會被堆疊在一條長3 . 8米直徑9 . 5毫米的鋯合金包殼管燃料棒中并加以密封。 |
|
Bwr is a light water reactor using ordinary water as coolant and moderator similar to the pwr except it only has a single circuit connecting the reactor and the turbine without a steam generator 沸水式反應堆是輕水反應堆的一種，這種反應堆和壓水式反應堆相似，均利用普通水作為冷卻劑及慢化劑，但沸水式反應堆只有一個連接反應堆和渦輪機的回路，且沒有裝設蒸汽發生器。 |
|
The high control criteria of water vapor quality in secondary circuit of 1000 mw pwr is introduced , and the criteria are compared with those in thermoelectric generating set 摘要介紹了壓水堆核電站1000mw機組二回路水汽質量的高控制標準，并與火力發電機組的水汽質量控制標準進行了對比。 |
|
The high control criteria of water vapor quality in secondary circuit of 1000 mw pwr is introduced , and the criteria are compared with those in thermoelectric generating set 介紹了壓水堆核電站1000mw機組二回路水汽質量的高控制標準，并與火力發電機組的水汽質量控制標準進行了對比。 |
|
The paper reports the model of the reactor core of the pwr nuclear power plant and established the suitable core physics - mathematics model for microcomputer simulation 摘要闡述了pwr核電站堆芯的模型化問題，提出了適用于微機仿真的核電站堆芯的物理數學模型。 |
|
In addition , the fission rate in the pwr can also be controlled by adjusting the boron ( a neutron absorber ) concentration in the primary coolant circuit 此外，壓水式反應堆的核裂變也可透過調節一回路內冷卻劑中的硼濃度來控制(硼亦是一種中子吸收體) 。 |
|
In addition , the fission rate in the pwr can also be controlled by adjusting the boron a neutron absorber concentration in the primary coolant circuit 此外，壓水式反應堆的核裂變也可透過調節一回路內冷卻劑中的硼濃度來控制硼亦是一種中子吸收體。 |
|
In this paper , the method for transient characteristic calculation of pwr ( pressurized water reactor ) coolant system is studied and a model is developed 本文根據壓水堆冷卻劑系統的特點，對反應堆、蒸汽發生器、穩壓器分別建立各自獨立的模型。 |
|
Furthermore , this article introduces the techniques to ensure the water vapor quality in secondary circuit of pwr 還介紹了保證壓水堆核電站二回路水汽質量的措施。 |
|
Light water pwr 輕水壓水堆 |
|
High - frequency switching power source implemented by pwr - top 3 - end high - tension switch devices 三端高壓開關器件實現的高頻開關電源 |
|
Design and construction rules for nuclear island systems of 2 600mw pwr nuclear power plants 壓水堆核電廠核島系統設計建造規范 |
|
Mathematical model for coil - coding control rod position detector in pwrs 壓水堆線圈編碼控制棒位置探測器的數學模型 |