thermal reactor 中文意思是什麼
thermal reactor
解釋
熱堆-
What kinds of thermal stress are there in the reactor ?
在反應堆里有哪一種熱應力？ -
Computing worth of thin slab control rod in thermal research reactor
熱中子研究堆薄板型控制棒價值計算 -
In this paper, high heat penetration into a moving particulate bed is described mathematically with a comprehensive heat and mass transfer model. the distribution of gas velocity and pressure, the temperature field of gas and solid in the moving particulate bed are examined for different conditions. the results show that thermal penetration into the moving packed - bed particles by fluid flow in porous media is high only in the position near the gas entrance. the thermal penetration thickness tends to increase with the fluid flow velocity and decrease with the particle moving velocity. in the region of thermal penetration, the porosity of solid bed has significant effect on gas field and pressure loss. it is feasible to reduce the gas pressure loss by a larger width / height packed bed in design and operation. the correspondence between thermal infection depth and particle bed height would be helpful to keep high oapacity of reactor and reduce the cost of operation
針對移動顆粒床中物料層內的高溫氣體滲流傳熱現象，考慮滲流與傳熱的相互作用，採用局部非熱平衡假設建立了多孔介質滲流傳熱物理數學模型並進行了數值計算.研究了不同情況下床內填充多孔介質中的流速、氣固溫度和床層壓力損失.計算結果表明，高溫熱氣對移動床顆粒料層的熱滲透主要發生在滲流入口端區域，增大入口滲流速度以及減小床層物料下移速度將導致物料溫度沿床高慢速下降，熱滲透深度擴大，熱滲透作用區域內的物料溫度水平提高.在熱滲透作用區域，孔隙率對流場和壓力損失有很大的影響.研究結果對于移動顆粒床反應器的設計與運行具有一定的參考作用 -
A measurement method regarding reactor core thermal power and error analysis
反應堆堆芯熱功率測量方法及其誤差分析 -
In the thermal reactor it promotes corrosion, and in the catalystic reactor it tends to poison the catalyst.
在熱反應器中，它促進腐蝕，在催化反應器中，它能使催化劑中毒。 -
Study of thermal oxidation degradation of shenfu coal at ambient temperature in a fixed - bed reactor
神府煤固定床低溫熱氧化降解研究 -
3 ). the flow velocity and temperature change rapidly in hot plenum under the transient condition such as in the case of reactor scram condition. thermal stratification phenomena will be observed nearby the inlet of intermediate heat exchanger
在事故停堆后的瞬態分析中，熱鈉池的流場和溫場變化劇烈，並在中間熱交換器的入口附近形成穩定的熱分層。 -
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，在物理計算中採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；在熱工水力計算中採用了一維的熱傳導模型與單通道模型；在求解點堆方程中採用了hermite插值的方法，克服了點堆方程的剛性問題。 -
The let factors rlet ( rlet = 0. 05 ) of neutron response for liftld in various n + y mixed fields in the fast neutron reactor have been determined experimentally due to the existing let effects of the response for liftld to neutron absorbed dose. the experimental results show that the let factor for neutrons from thermal energy to 5mev energy is about 0. 050. so it is workable to measure the photon fluence in the pulse reactor with 7liftld
為確定liftld能否用於n 、混合場的區分測量，本文定義了let效應因子，並對liftld的let效應因子進行了實驗測定，測量結果表明： liftld對熱中子至5mev中子響應的let效應因子值約為0 . 050 ，因此，選用~ 7liftld用於脈沖堆光子注量測量是可行的。 -
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 。 -
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:基於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 multi - functional blanket for waste transmutation and fuel production has been developed. based on studies for feasibility and reliability of fusion - driven hybrid reactor, the conceptual design of dwtb is presented, especially the analysis activities of liquid metal mhd pressure drop in the fds blanket that is included into thermal - hydraulic analysis
本論文針對雙冷嬗變核廢物包層設計，從液態金屬磁流體動力學觀點出發，提出與液態金屬mhd效應相關的研究設計概念，並對雙冷嬗變核廢物包層中液態金屬mhd壓降進行分析研究和模擬計算，評價其可行性。 -
In order for students to master the knowledge of reactor system, physics, thermal hydraulics, shielding, structure, fuel, etc. and the design flow chart, a local thermal hydraulic system is designed by students
設計部分是將所學的有關核反應堆系統、物理、熱工、屏蔽、結構、元件等相關知識，應用到核反應堆輸熱系統的設計中，並掌握核反應堆熱工設計流程與方法。
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