核電專(zhuān)業(yè)英語(yǔ)

前言

　　核電工程技術(shù)涉及的學(xué)科領(lǐng)域廣泛，包含很多高新技術(shù)。目前，美、英等發(fā)達(dá)國(guó)家在該領(lǐng)域處于領(lǐng)先地位，很多新的研究成果和新技術(shù)的介紹都以英文發(fā)表，每個(gè)從事核電工程研究、設(shè)計(jì)和運(yùn)行的專(zhuān)業(yè)人員都需要閱讀大量的英文資料。為了滿足越來(lái)越多的核電工程專(zhuān)業(yè)人員學(xué)習(xí)專(zhuān)業(yè)英語(yǔ)的需要，編寫(xiě)了本書(shū)?！　”緯?shū)內(nèi)容涵蓋了核電工程所涉及的主要學(xué)科，在介紹核反應(yīng)堆物理及核反應(yīng)堆熱工等基礎(chǔ)知識(shí)的同時(shí)，也介紹了各種類(lèi)型的核反應(yīng)堆及主要設(shè)備的原理和使用特性等。主要內(nèi)容包括：核反應(yīng)堆物理的基礎(chǔ)知識(shí)、核材料、核反應(yīng)堆熱工水力學(xué)、反應(yīng)堆結(jié)構(gòu)、核動(dòng)力系統(tǒng)和主要設(shè)備、核反應(yīng)堆運(yùn)行及核安全、核動(dòng)力的發(fā)展及新一代反應(yīng)堆等。本書(shū)內(nèi)容廣泛，選用不同風(fēng)格的文章，做到內(nèi)容新、知識(shí)面寬；選用的課文概念性和知識(shí)性強(qiáng)、難度適中，不涉及復(fù)雜的專(zhuān)業(yè)理論。為了便于讀者掌握專(zhuān)業(yè)詞匯，每課課后對(duì)重要的關(guān)鍵詞作了英、中文兩種解釋?zhuān)瑫r(shí)還列出了重要的詞匯解釋、課文中的難點(diǎn)注釋。為了加深讀者對(duì)課文內(nèi)容的理解，課后還附有習(xí)題和答案?！　”緯?shū)的內(nèi)容安排由淺入深、由基礎(chǔ)到專(zhuān)業(yè)，可適合不同層次的學(xué)生使用。全書(shū)圍繞著核電工程這一主題，在專(zhuān)業(yè)部分中以新一代壓水堆核電站動(dòng)力裝置為主線，介紹了目前運(yùn)行的核電技術(shù)以及新一代的核電技術(shù)。書(shū)中的每一課都有相當(dāng)?shù)莫?dú)立性，可以根據(jù)學(xué)生的興趣和專(zhuān)業(yè)方向選擇使用，同時(shí)也考慮了課文內(nèi)容滿足總體需要，保證全書(shū)內(nèi)容是一個(gè)完整的整體。　　本書(shū)的閱讀內(nèi)容取自英文的原版教科書(shū)和工程設(shè)計(jì)說(shuō)明書(shū)。書(shū)中的引文，編者盡力與版權(quán)所有者取得聯(lián)系，但仍有部分聯(lián)系不上，在此深表歉意。　　全書(shū)共20個(gè)單元，由哈爾濱工程大學(xué)閻昌琪教授編寫(xiě)，由中國(guó)原子能科學(xué)研究院阮於珍研究員主審，阮老師提出了許多寶貴的意見(jiàn)和建議，在此深表謝意?！　∮捎诰幷咚剿?，書(shū)中難免存在缺點(diǎn)和不足，敬請(qǐng)讀者提出寶貴意見(jiàn)。

內(nèi)容概要

本書(shū)為普通高等教育核工程與核技術(shù)專(zhuān)業(yè)規(guī)劃教材。    本書(shū)的內(nèi)容涵蓋了與核電有關(guān)的基礎(chǔ)理論知識(shí)和專(zhuān)業(yè)知識(shí)，介紹了反應(yīng)堆結(jié)構(gòu)、核動(dòng)力系統(tǒng)和設(shè)備，也包括了近年來(lái)核電的新發(fā)展，例如第三代和第四代反應(yīng)堆的介紹。書(shū)中涉及的核電專(zhuān)業(yè)詞匯廣泛、內(nèi)容豐富、知識(shí)性強(qiáng)。    為了便于讀者掌握專(zhuān)業(yè)詞匯，每課課文后對(duì)重要的關(guān)鍵詞作了英、中文兩種解釋?zhuān)瑫r(shí)還列出了重要的詞匯解釋、課文中的難點(diǎn)注釋。為了加深讀者對(duì)課文內(nèi)容的理解，課后還附有習(xí)題和答案。    本書(shū)可作為普通高等教育本科核工程與核技術(shù)專(zhuān)業(yè)的英語(yǔ)閱讀教材，也可作為核電工程技術(shù)人員的培訓(xùn)和自學(xué)用書(shū)，同時(shí)可作為能源動(dòng)力類(lèi)等相關(guān)專(zhuān)業(yè)人員的閱讀材料。

書(shū)籍目錄

前言Unit 1 The Basic Concepts for Nuclear Physics  1.1 Atoms and Nuclei  1.2 Isotopes  1.3 Mass Defect  1.4 Binding Energy  1.5 Energy Levels  1.6 Fission  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 2 Radiation  2.1 Radioactivity  2.2 Excitation and Ionization by Electrons  2.3 Heavy Charged Particle Slowing by Atoms  2.4 Heavy Charged Particle Scattering by Nuclei  2.5 Gamma Ray Interactions with Matter  2.6 The Properties of Alpha, Beta and Gamma Radiation  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 3 Nuclear Materials  3.1 Fuels  3.2 Moderators  3.3 Coolants  3.4 Cladding Materials  3.5 Control Materials  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 4 The Theory of Nuclear Reactors  4.1 Th6 Chain Reaction  4.2 The Neutron Cycle in a Thermal Reactor  4.3 Conversion and Breeding  4.4 Fuel Cycles  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 5 Nuclear Reactor Concepts  5.1 Power Reactors  5.2 Consumption of Nuclear Fuels  5.3 Reactor Control  5.4 Other Effects on Reactor Operation  5.5 The Fast Breeder Reactor  5.6 Uranium as an Energy Resource  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 6 Nuclear ReactorThermohydraulics  6.1 Methods of Heat Transmission  6.2 Conduction in Reactor Fuel  6.3 Heat Removal by Coolant  6.4 Boiling Heat Transfer  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 7 Pressurized water Reactor  7.1 General  7.2 Pressurized Water Reactor Components  7.3 Introduction to the Nuclear Steam Supply System 80+  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 8 Reactor vessel and Internals  8.1 Reactor Vessel  8.2 Reactor Vessel Internals  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 9 Reactor Core and Fuel  9.1 Introduction  9.2 Core  9.3 Fuel Rod  9.4 Fuel Assembly  9.5 Control Element Assemblies and Drive Mechanisms  9.6 Control Element Drive Mechanisms (CEDM)  9.7 Neutron Sources  9.8 Burnable Absorber Rod Assembly  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 10 The Main Components in PWR Coolant System  10.1 Steam Generators  10.2 Pressurizer  10.3 Reactor Coolant Pumps and Motors  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 11 Pressurized Water Reactor Systems and Containment  11.1 Plant Heat Balance and the Steam Cycle  11.2 PWR Primary and Secondary Loops  11.3 Auxiliary system for Primary Loop  11.4 Containment  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 12 The Steam Turbine  12.1 Introduction  12.2 Classification of Turbines  12.3 Impulse and Reaction Blading  12.4 Velocity Compounding Curtis Stage  12.5 The Reaction-Turbine Principle  12.6 Reaction Blading  12.7 Sealing Arrangement  12.8 Twisted and Tapered Blades  12.9 Erosion Control and Moisture Removal  12.10 Other Blade Features  12.11 Low Pressure Turbine  12.12 Turbine Control  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 13 Main Steam, Feed and Condensate Systems  13.1 Introduction  13.2 Main Steam and Feedwater Piping  13.3 Main Steam Piping System Flow Restrictor  13.4 Safety Requirements  13.5 Feed and Condensate System Description  13.6 Transients  13.7 Controls  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 14 Operation of a Nuclear Power Plant  14.1 Introduction  14.2 Plant Safety  14.3 Plant Operations  14.4 Normal Mode  14.5 Abnormal Mode  14.6 Off-Normal (Upset) Mode  14.7 Control Rooms and Instrumentation  14.8 System Parameters  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 15 Radiation Hazards and Shielding  15.1 Introduction  15.2 Health Physics  15.3 The Biological Effects of Radiation Exposure  15.4 The Effects of Inhaled and Ingested Radioactivity  15.5 Reactor Shielding  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 16 Nuclear Safety  16.1 Safety and Hazards in Nuclear Power  16.2 Reactor Accidents  16.3 The Accident at Three Mile Island  16.4 The Accident at Chernobyl  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 17 Westinghouse APl000 Advanced Passive Plant  17.1 Introduction  17.2 Major Equipment Description  17.3 Safety Through Simplicity  17.4 Passive Safety Systems  17.5 Probabilistic Risk Assessment  17.6 Simplification  17.7 Cost and Construction Schedule  17.8 Licensing  17.9 AP1000 Deployment  17.10 Conclusions  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 18 European Pressurized Water Reactor (EPR)  18.1 Introduction  18.2 Construction Schedule  18.3 Operation, Maintenance and Services  18.4 Opreational Flexibility  18.5 Safety Systems  18.6 Primary System  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 19 The Heavy-Water-Moderated Reactor  19.1 General Characteristics of the Heavy Water Reactor  19.2 The CANDU Pressure Tube Heavy Water Reactor  19.3 Advanced CANDU Reactor  Self-test  關(guān)鍵字解釋  詞匯  課文注釋Unit 20 Generation IV Nuclear Power  20.1 Introduction  20.2 The Gas-Cooled Fast Reactor (GFR)  20.3 Very-High-Temperature Reactor System (VHTR)  20.4 Supercritical Water-Cooled Reactor (SCWR)  20.5 Sodium-Cooled Fast Reactor (SFR)  20.6 Lead-Cooled Fast Reactor (LFR)  20.7 Molten Salt Reactor (MSR)  20.8 Generation IV and the Hydrogen Economy  Self-test  關(guān)鍵字解釋  詞匯  課文注釋附錄Ⅰ Self-test習(xí)題答案附錄Ⅱ 詞匯表參考文獻(xiàn)

章節(jié)摘錄

　　The further development of the British system, the advanced gas-cooled reactor（AGR）,uses graphite as a moderator and a somewhat enriched fuel to compensate for the fact that thefuel is contained in stainless steel, which absorbs a significant fraction of the neutrons.　　We shall describe and discuss all the above reactors, and in particular their coolingproblems, in the following chapters. However, before doing so, it may be interesting to glanceback to prehistoric times. The light water-cooled and moderated reactors have been around farlonger than one might imagine. In fact, the invention of Enrico Fermi was preempted by natureapproximately 2 billion years earlier. In 1972, evidence was found of the dormant remains of anatural fission reactor located at Oklo, in the West African Republic of Gabon. This naturalreactor operated for a period of hundreds of thousands of years. Its existence was discoveredby an intriguing piece of detective work by French nuclear scientists.　　In May 1972, H. Bouzigues obtained a curious result during a routine analysis of standardsamples of uranium ore from Gabon. He found that they contained about 0.4% less 235U thanexpected. This was not due to an error in his analysis or to a natural variation. On this planet, atany particular time, the ratio of 235U to 238U is fixed; some other explanation had to be foundfor the discrepancy. A careful investigation carried out by the French Atomic Energy Agencytraced the abnormal ore to one particular location in Oklo. It was concluded that the deficiencyin 235U could be explained only by the occurrence of a natural fission reaction at the site. At thetime this natural reactor was operating, the ore was buried deep underground and naturalgroundwater served as a moderator and to some extent as a coolant. Such a reactor would notbe possible with the present-day concentration of 235U in naturally occurring uranium, as weexplained above. However, it should be remembered that the half-life of 235U is about 700million years and that of 238U is about 4.5 billion years. Thus, in prehistoric times, theconcentration of 235U was much higher than it is today. When the earth was formed some 4.6billion years ago, the concentration of 235U in natural uranium was about 25%, and it haddecreased to about 3% at the time when the Oklo reactor was operating.

編輯推薦

　　本書(shū)內(nèi)容涵蓋了核電工程所涉及的主要學(xué)科，在介紹核反應(yīng)堆物理及核反應(yīng)堆熱工等基礎(chǔ)知識(shí)的同時(shí)，也介紹了各種類(lèi)型的核反應(yīng)堆及主要設(shè)備的原理和使用特性等。主要內(nèi)容包括：核反應(yīng)堆物理的基礎(chǔ)知識(shí)、核材料、核反應(yīng)堆熱工水力學(xué)、反應(yīng)堆結(jié)構(gòu)、核動(dòng)力系統(tǒng)和主要設(shè)備、核反應(yīng)堆運(yùn)行及核安全、核動(dòng)力的發(fā)展及新一代反應(yīng)堆等。本書(shū)內(nèi)容廣泛，選用不同風(fēng)格的文章，做到內(nèi)容新、知識(shí)面寬；選用的課文概念性和知識(shí)性強(qiáng)、難度適中，不涉及復(fù)雜的專(zhuān)業(yè)理論。為了便于讀者掌握專(zhuān)業(yè)詞匯，每課課后對(duì)重要的關(guān)鍵詞作了英、中文兩種解釋?zhuān)瑫r(shí)還列出了重要的詞匯解釋、課文中的難點(diǎn)注釋。為了加深讀者對(duì)課文內(nèi)容的理解，課后還附有習(xí)題和答案。

圖書(shū)封面

圖書(shū)標(biāo)簽Tags

無(wú)

評(píng)論、評(píng)分、閱讀與下載

---

    核電專(zhuān)業(yè)英語(yǔ) PDF格式下載

---