標(biāo)準(zhǔn)號(hào) |
中文名稱(chēng) |
英文名稱(chēng) |
| ANSI/AMCA 520-2004 |
試驗(yàn)促動(dòng)器的實(shí)驗(yàn)室方法 |
|
| ANSI/AMCA 610-1995 |
空氣流動(dòng)速率測(cè)量站的試驗(yàn)方法 |
Methods of Testing Airflow Measurement Stations for Rating |
| ANSI/AMCA 99-0068-2003 |
AMCA詞匯:產(chǎn)品定義 |
(The AMCA Vocabulary: Product Definitions ) |
| ANSI/AMCA 99-2404-2003 |
離心式風(fēng)扇用傳動(dòng)設(shè)備 |
(Drive Arrangements for Centrifugal Fans ) |
| ANSI/AMCA 99-2406-2003 |
離心式風(fēng)扇的轉(zhuǎn)向和排量標(biāo)識(shí) |
(Designation for Rotation and Discharge of Centrifugal Fans ) |
| ANSI/AMCA 99-2410-2003 |
管狀離心式風(fēng)機(jī)用傳動(dòng)設(shè)備 |
(Drive Arrangements for Tubular Centrifugal Fans ) |
| ANSI/AMCA 99-2412-2003 |
離心式風(fēng)扇用葉輪直徑和插座區(qū) |
(Impeller Diameters and Outlet Areas for Centrifugal Fans ) |
| ANSI/AMCA 99-2413-2003 |
工業(yè)離心式風(fēng)扇的葉輪直徑和出口面積 |
(Impeller Diameters and Outlet Areas for Industrial Centrifugal Fans ) |
| ANSI/AMCA 99-2414-2003 |
管狀離心式風(fēng)機(jī)用葉輪直徑和排氣口面積 |
(Impeller Diameters and Outlet Areas for Tubular Centrifugal Fans ) |
| ANSI/AMCA 99-3001-2003 |
軸流風(fēng)機(jī)的尺寸 |
(Dimensions for Axial Fans ) |
| ANSI/AMCA 99-3404-2003 |
有或無(wú)出口漸擴(kuò)段和進(jìn)氣箱的軸流風(fēng)機(jī)傳動(dòng)設(shè)備 |
(Drive Arrangements for Axial Fans With or Without Evase and Inlet Box ) |
| ANSI/ANS 10.2-1988 |
科研用計(jì)算機(jī)程序促進(jìn)的推薦設(shè)計(jì)規(guī)程 |
Portability of Scientific Computer Programs, Recommended Programming Practices to Facilitate the |
| ANSI/ANS 10.3-1995 |
數(shù)字計(jì)算機(jī)程序文件編制導(dǎo)則 |
Documentation of Computer Software |
| ANSI/ANS 10.4-1987 |
核工業(yè)科研和工程用計(jì)算機(jī)程序驗(yàn)證和校驗(yàn)導(dǎo)則 |
Verification and Validation of Scientific and Engineering Computer Programs for the Nuclear Industry, Guidelines for |
| ANSI/ANS 14.1-1975 |
快速脈沖反應(yīng)堆的運(yùn)行 |
Fast Pulse Reactors, Operation of |
| ANSI/ANS 14.1-2004 |
快速脈沖反應(yīng)堆的運(yùn)行 |
|
| ANSI/ANS 15.1-1990 |
研究反應(yīng)堆的技術(shù)開(kāi)發(fā)規(guī)范 |
Research Reactors, Development of Technical Specifications for |
| ANSI/ANS 15.10-1994 |
研究反應(yīng)堆的停運(yùn) |
Decommissioning of Research Reactors |
| ANSI/ANS 15.11-1993 |
研究反應(yīng)堆設(shè)施輻射的防護(hù) |
Radiation Protection at Research Reactor Facilities |
| ANSI/ANS 15.12-1977 |
研究反應(yīng)堆控制系統(tǒng)污水處理的設(shè)計(jì)目標(biāo)及監(jiān)控 |
Effluents, Design Objectives for and Monitoring of Systems Controlling Research Reactor |
| ANSI/ANS 15.15-1978 |
研究反應(yīng)堆的反應(yīng)堆安全系統(tǒng)準(zhǔn)則 |
Safety Systems of Research Reactors, Criteria for the Reactor |
| ANSI/ANS 15.16-1982 |
研究反應(yīng)堆的應(yīng)急方案 |
Emergency Planning for Research Reactors |
| ANSI/ANS 15.17-1981 |
研究反應(yīng)堆的消防措施標(biāo)準(zhǔn) |
Fire Protection Program Criteria for Research Reactors |
| ANSI/ANS 15.19-1991 |
研究反應(yīng)堆設(shè)施用特種核材料的船運(yùn)和接收 |
Shipment and Receipt of Special Nuclear Material (SNM) by Research Reactor Facilities |
| ANSI/ANS 15.21-1996 |
研究反應(yīng)堆安全分析報(bào)告格式和內(nèi)容 |
Format and Content for Safety Analysis Reports for Research Reactors |
| ANSI/ANS 15.4-1988 |
研究用反應(yīng)堆的人員選擇和培訓(xùn) |
Selection and Training of Personnel for Research Reactors |
| ANSI/ANS 15.7-1977 |
研究反應(yīng)堆現(xiàn)場(chǎng)評(píng)定 |
Site Evaluation, Research Reactor |
| ANSI/ANS 15.8-1976 |
研究反應(yīng)堆, 保險(xiǎn)程序要求(ANSI N402-1976的重新設(shè)計(jì)和重申) |
Quality assurance program requirements for research reactors |
| ANSI/ANS 16.1-2003 |
用短期試驗(yàn)法對(duì)固化低放射性廢物浸出性的測(cè)量 |
(Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure ) |
| ANSI/ANS 19.1-2002 |
反應(yīng)堆設(shè)計(jì)計(jì)算用核數(shù)據(jù)集 |
(Nuclear Data Sets for Reactor Design Calculations ) |
| ANSI/ANS 19.11-1997 |
水慢化動(dòng)力堆反應(yīng)性的慢化劑溫度系數(shù)計(jì)算和測(cè)量 |
Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors |
| ANSI/ANS 19.3-1983 |
中子反應(yīng)速率分布與核反應(yīng)堆反應(yīng)性的測(cè)定 |
Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors, Determination of |
| ANSI/ANS 19.3.4-2002 |
核反應(yīng)堆熱能沉積率的測(cè)定 |
(Determination of Thermal Energy Deposition Rates in Nuclear Reactors ) |
| ANSI/ANS 19.4-1976 |
核分析鑒定用參考動(dòng)力反應(yīng)堆物理測(cè)量的數(shù)據(jù)獲得及文獻(xiàn)工作指南 |
Acquisition and Documentation of Reference Power Reactor Physics Measurements for Nuclear Analysis Verification, Guide for |
| ANSI/ANS 19.5-1995 |
標(biāo)準(zhǔn)反應(yīng)堆的物理測(cè)量要求 |
Physics Measurements, Requirements for Reference Reactor |
| ANSI/ANS 19.6.1-1997 |
壓水反應(yīng)堆重新裝料起動(dòng)物理試驗(yàn) |
Reload Startup Physics Tests for Pressurized Water Reactors |
| ANSI/ANS 2.10-2003 |
核電站地震測(cè)量?jī)x表所示數(shù)據(jù)的處理和初始評(píng)價(jià)標(biāo)準(zhǔn) |
(Criteria for the Handling and Initial Evaluation of Records from Nuclear Power Plant Seismic Instrumentation ) |
| ANSI/ANS 2.12-1978 |
核動(dòng)力反應(yīng)堆現(xiàn)場(chǎng)內(nèi)在的與外部人為危險(xiǎn)綜合考慮導(dǎo)則 |
Natural and External Man-Made Hazards at Power Reactor Sites, Guidelines for Combining |
| ANSI/ANS 2.25-1982 |
需獲準(zhǔn)建立熱電廠(chǎng)的大地生態(tài)考查 |
Surveys of Terrestrial Ecology Needed to License Thermal Power Plants |
| ANSI/ANS 2.8-1992 |
核反應(yīng)堆場(chǎng)所的溢流設(shè)計(jì)基礎(chǔ)的測(cè)定 |
Determining Design Basis Flooding at Power Reactor Sites |
| ANSI/ANS 3.1-1993 |
核電廠(chǎng)人員選擇,資格和培訓(xùn) |
Selection, Qualification, and Training of Personnel for Nuclear Power Plants |
| ANSI/ANS 3.2-1994 |
核電廠(chǎng)操作期的質(zhì)量保證和行政控制 |
Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants |
| ANSI/ANS 3.4-1996 |
核電廠(chǎng)持證上崗人員的健康認(rèn)證與監(jiān)測(cè) |
Medical Certification and Monitoring of Personnel Requiring Operating Licenses for Nuclear Power Plants |
| ANSI/ANS 3.5-1998 |
操作者訓(xùn)練和檢驗(yàn)用核電廠(chǎng)模擬裝置 |
Nuclear Power Plant Simulators for Use in Operator Training and Examination |
| ANSI/ANS 3.7.1-1995 |
核電廠(chǎng)輻射事故現(xiàn)場(chǎng)醫(yī)療護(hù)理用的設(shè)備 |
Emergencies, Facilities and Medical Care for On-Site Nuclear Power Plant Radiological |
| ANSI/ANS 3.8.1-1995 |
核電廠(chǎng)應(yīng)急功能及組織機(jī)構(gòu)標(biāo)準(zhǔn) |
Nuclear Power Plants - Criteria for Emergency Response Functions and Organizations |
| ANSI/ANS 3.8.2-1995 |
核電廠(chǎng)應(yīng)急設(shè)施的功能和物理特征準(zhǔn)則 |
Criteria for Functional and Physical Characteristics of Emergency Response Facilities |
| ANSI/ANS 3.8.3-1995 |
核電廠(chǎng)應(yīng)急方案與實(shí)施程序準(zhǔn)則 |
Nuclear Power Plants - Criteria for Emergency Response Plans and Implementing Procedures |
| ANSI/ANS 3.8.4-1995 |
核電廠(chǎng)應(yīng)急能力的維護(hù)準(zhǔn)則 |
Nuclear Power Plants - Criteria for Maintaining Emergency Response Capability |
| ANSI/ANS 3.8.5-1992 |
緊急輻射場(chǎng)的監(jiān)測(cè)、采樣和分析準(zhǔn)則 |
Criteria for Emergency Radiological Field Monitoring, Sampling, and Analysis |
| ANSI/ANS 3.8.6-1995 |
核電廠(chǎng)應(yīng)急進(jìn)行場(chǎng)外輻射評(píng)估的準(zhǔn)則 |
Criteria for Conduct of Offsite Radiological Assessment for Emergency Response for Nuclear Power Plants |
| ANSI/ANS 3.8.7-1998 |
應(yīng)急準(zhǔn)備演習(xí)和訓(xùn)練的計(jì)劃、開(kāi)發(fā)、指導(dǎo)和評(píng)價(jià)標(biāo)準(zhǔn) |
Criteria for Planning, Development, Conduct, and Evaluation of Drills and Exercises for Emergency Preparedness |
| ANSI/ANS 40.35-1991 |
低能級(jí)放射性廢物的體積壓縮 |
Volume Reduction of Low Level Radioactive Waste |
| ANSI/ANS 40.37-1993 |
輕便的低能級(jí)放射性廢物處理裝置 |
Mobile Radioactive Waste Processing Systems |
| ANSI/ANS 5.1-2005 |
輕水反應(yīng)堆衰變熱功率 |
|
| ANSI/ANS 5.10-1998 |
非活性核設(shè)施氣載釋放率 |
Airborne Release Fractions at Non-Reactor Nuclear Facilities |
| ANSI/ANS 51.10-1991 |
加壓水冷反應(yīng)堆的供水系統(tǒng) |
Auxiliary Feedwater System for Pressurized Water Reactors |
| ANSI/ANS 55.1-1992 |
輕水冷卻反應(yīng)堆中固體放射性廢物的處理系統(tǒng) |
Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants |
| ANSI/ANS 55.4-1993 |
輕水反應(yīng)堆廠(chǎng)氣態(tài)放射性廢物處理系統(tǒng) |
Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants |
| ANSI/ANS 55.6-1993 |
輕水冷卻反應(yīng)堆中液體放射性廢物的處理系統(tǒng) |
Liquid Radioactive Waste Processing Systems for Light Water Reactor Plants |
| ANSI/ANS 56.8-1994 |
核反應(yīng)堆安全殼系統(tǒng)泄漏測(cè)試要求 |
Nuclear Reactors - Containment System Leakage Testing Requirements |
| ANSI/ANS 56.8-2002 |
核反應(yīng)堆.安全殼系統(tǒng)泄漏測(cè)試要求 |
(Nuclear Reactors - Containment System Leakage Testing Requirements ) |
| ANSI/ANS 57.1-1992 |
輕水反應(yīng)堆燃料處理系統(tǒng)的設(shè)計(jì)要求 |
Design Requirements for Light Water Reactor Fuel Handling Systems |
| ANSI/ANS 57.10-1996 |
輕水反應(yīng)堆廢燃料的壓力設(shè)計(jì)準(zhǔn)則 |
Design Criteria for Consolidation of LWR Spent Fuel |
| ANSI/ANS 57.5-1996 |
輕水反應(yīng)堆燃料組件的機(jī)械設(shè)計(jì)和評(píng)估 |
Light Water Reactors Fuel Assembly Mechanical Design and Evaluation |
| ANSI/ANS 57.7-1988 |
獨(dú)立的廢燃料貯存設(shè)備的設(shè)計(jì)準(zhǔn)則 |
Design Criteria for an Independent Spent Fuel Storage Installation (Water Pool Type) |
| ANSI/ANS 57.8-1995 |
核燃料組件的標(biāo)識(shí) |
Nuclear Fuel Assembly Identification |
| ANSI/ANS 57.9-1992 |
獨(dú)立的廢燃料貯藏設(shè)備的設(shè)計(jì)準(zhǔn)則 |
Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type) |
| ANSI/ANS 58.11-1995 |
輕水反應(yīng)堆冷卻準(zhǔn)則 |
Cooldown Criteria for Light Water Reactors |
| ANSI/ANS 58.14-1993 |
輕水反應(yīng)堆安全與壓力綜合分類(lèi)準(zhǔn)則 |
Safety and Pressure Integrity Classification Criteria for Light Water Reactors |
| ANSI/ANS 58.2-1988 |
輕水反應(yīng)堆核電站設(shè)定管子斷裂影響的防護(hù)設(shè)計(jì)基礎(chǔ) |
Design Basis for Protection of Light Water Nuclear Power Plants against Effects of Postulated Pipe Rupture |
| ANSI/ANS 58.21-2003 |
外部事件PRA方法 |
(External Events PRA Methodology ) |
| ANSI/ANS 58.3-1992 |
核安全有關(guān)的系統(tǒng)的件的物理防護(hù) |
Physical Protection for Nuclear Safety-Related Systems and Components |
| ANSI/ANS 58.6-1996 |
輕水反應(yīng)堆實(shí)施遠(yuǎn)距離關(guān)閉的準(zhǔn)則 |
Remote Shutdown for Light Water Reactors, Criteria for |
| ANSI/ANS 58.8-1994 |
關(guān)于操作安全的時(shí)間響應(yīng)設(shè)計(jì)準(zhǔn)則 |
Nuclear Power Plants - Time Response Design Criteria for Safety Related Operator Actions |
| ANSI/ANS 58.9-2002 |
輕水反應(yīng)堆有關(guān)安全的液體系統(tǒng)的單一故障準(zhǔn)則應(yīng)用 |
(Application of the Single Failure Criterion for Light Water Reactor Safety-Related Fluid Systems ) |
| ANSI/ANS 59.1-1986 |
與核安全有關(guān)的輕水反應(yīng)堆水冷卻系統(tǒng) |
Cooling Water Systems for Light Water Reactors, Nuclear Safety Related |
| ANSI/ANS 59.2-1985 |
主安全外殼的采暖、通風(fēng)和空調(diào)系統(tǒng)的安全準(zhǔn)則 |
Nuclear Power Plants - HVAC Systems Located Outside Primary Containment, Safety Criteria for |
| ANSI/ANS 59.3-1992 |
控制空氣系統(tǒng)的核安全準(zhǔn)則 |
Nuclear Safety Criteria for Control Air Systems |
| ANSI/ANS 59.51-1997 |
應(yīng)急柴油發(fā)動(dòng)機(jī)用的燃油系統(tǒng) |
Fuel-Oil Systems for Emergency Diesel Generators |
| ANSI/ANS 59.52-1998 |
備用柴油發(fā)電機(jī)的安全用潤(rùn)滑油系統(tǒng) |
Lubricating Oil Systems for Safety Related Emergency Diesel Generators |
| ANSI/ANS 6.1.1-1991 |
中子及ｒ射線(xiàn)能量與劑量因素的關(guān)系 |
Neutron and Gamma-Ray Fluence-to-Dose Factors |
| ANSI/ANS 6.3.1-1987 |
輕水反應(yīng)堆(LWR)中輻射屏蔽的測(cè)試過(guò)程 |
Program for Testing Radiation Shields in Lightwater Reactors |
| ANSI/ANS 6.4-1997 |
核動(dòng)力廠(chǎng)的混凝土輻射屏蔽.核分析導(dǎo)則和導(dǎo)則設(shè)計(jì) |
Concrete Radiation Shielding for Nuclear Power Plants, Guidelines on the Nuclear Analysis and Design of |
| ANSI/ANS 6.4.2-1985 |
輻射屏蔽材料的規(guī)范 |
Radiation Shielding Materials, Specification for |
| ANSI/ANS 6.4.3-1991 |
工程材料中γ射線(xiàn)衰變系數(shù)和結(jié)構(gòu)因素 |
Gamma-Ray Attenuation Coefficients and Buildup Factors for Engineering Materials |
| ANSI/ANS 6.6.1-1987 |
LWR核電站直接和散射伽馬輻射的計(jì)算和測(cè)量 |
Calculation and Measurement of Direct and Scattered Gamma Radiation from LWR Nuclear Power Plants, |
| ANSI/ANS 8.1-1983 |
反應(yīng)堆外部可裂變材料的操作中核臨界安全 |
Operations with Fissionable Materials Outside Reactors, Nuclear Criticality Safety in |
| ANSI/ANS 8.10-1983 |
操作中使用屏蔽和限制的核臨界安全控制標(biāo)準(zhǔn) |
Nuclear Criticality Safety Controls in Operations with Shielding and Confinement, Criteria for |
| ANSI/ANS 8.12-1987 |
反應(yīng)堆外部钚鈾混合燃料核臨界控制和安全 |
Plutonium-Uranium Fuel Mixtures Outside Reactors, Nuclear Criticality Control and Safety of |
| ANSI/ANS 8.14-2004 |
反應(yīng)堆外部核設(shè)施中可溶性中子吸收劑的使用 |
|
| ANSI/ANS 8.15-1981 |
專(zhuān)用錒系素的核臨界控制 |
Nuclear Criticality Control of Special Actinide Elements |
| ANSI/ANS 8.17-1984 |
反應(yīng)堆外部的輕水反應(yīng)堆燃料的搬運(yùn)、貯藏和運(yùn)輸準(zhǔn)則 |
Handling, Storage, and Transportation of LWR Fuel Outside Reactors, Criteria for |
| ANSI/ANS 8.19-1996 |
核臨界安全性管理規(guī)程 |
Nuclear Criticality Safety - Administrative Practices |
| ANSI/ANS 8.20-1991 |
核臨界安全培訓(xùn) |
Nuclear Criticality Safety Training |
| ANSI/ANS 8.21-1995 |
混合的中子吸收在核設(shè)施外圍反應(yīng)堆的使用 |
Use of Fixed Neutron Absorbers in Nuclear Facilities Outside Reactors |
| ANSI/ANS 8.22-1997 |
限制和控制慢化劑基礎(chǔ)上的核臨界安全 |
Nuclear Criticality Safety Based on Limiting and Controlling Moderators |
| ANSI/ANS 8.23-1997 |
核臨界事故應(yīng)急設(shè)計(jì)和反應(yīng) |
Nuclear Criticality Accident Emergency Planning and Response |
| ANSI/ANS 8.3-1997 |
核臨界事故報(bào)警系統(tǒng) |
Criticality Accident Alarm System |
| ANSI/ANS 8.5-1996 |
易裂變材料溶液中用硼硅玻璃拉希環(huán)作中子吸收劑 |
Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material |
| ANSI/ANS 8.6-1983 |
次臨界中子增殖現(xiàn)場(chǎng)測(cè)量的安全 |
Safety in Conducting Subcritical Neutron-Multiplication Measurements in situ |
| ANSI/ANS/HPSSC 6.8.1-1981 |
輕水核反應(yīng)堆輻射監(jiān)測(cè)系統(tǒng),定位和設(shè)計(jì)標(biāo)準(zhǔn) |
Radiation Monitoring Systems for Light Water Nuclear Reactors, Location and Design Criteria for Area |
| ANSI/API 10A-2001 |
良好粘接用水泥和材料規(guī)范(第23版) |
Specification for Cements and Materials for Well Cementing (Twenty Third Edition) |
| ANSI/API 10B-3-2004 |
深水固井水泥成分檢測(cè)的推薦實(shí)施規(guī)程 |
|
| ANSI/API 10D-2001 |
弓形彈簧鑄塑中心化子的規(guī)范(第6版) |
Specification for Bow-Spring Casing Centralizers (Sixth Edition) |
| ANSI/API 10F-2001 |
水泥灌漿浮標(biāo)設(shè)備性能試驗(yàn)的推薦實(shí)施規(guī)程 |
Recommended Practice for Performance Testing of Cementing Float Equipment |
| ANSI/API 1104-1999 |
管道和相關(guān)設(shè)施的焊接 |
Welding of Pipelines and Related Facilities |
| ANSI/API 1107-1992 |
管道保養(yǎng)焊接規(guī)程 |
Pipeline Maintenance Welding Practices |
| ANSI/API 1160-2001 |
危險(xiǎn)液體管道的管理系統(tǒng)完整性 |
Managing System Integrity for Hazardous Liquid Pipeline |
| ANSI/API 1163-2005 |
在線(xiàn)檢查系統(tǒng)合格標(biāo)準(zhǔn)(第1版) |
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| ANSI/API 13M-2004 |
完井液體粘性測(cè)量的推薦規(guī)程 |
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| ANSI/API 14A-2005 |
井下安全閥設(shè)備的規(guī)范 |
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| ANSI/API 2000-1992 |
通風(fēng)大氣式低壓貯罐 |
Venting Atmospheric and Low-Pressure Storage Tanks (Nonrefrigerated and Refrigerated) |
| ANSI/API 2015-2001 |
石油貯罐的安全入口和清洗 |
Safe Entry and Cleaning of Petroleum Storage Tanks |
| ANSI/API 2510-1996 |
船上及輸油管總站、天然氣加工廠(chǎng)、煉油廠(chǎng)、石油化工廠(chǎng)及油罐區(qū)的液化石油氣裝置的設(shè)計(jì)及制造 |
Design and Construction of LPG Installations |
| ANSI/API 2530 Part 1-1991 |
天然氣流體測(cè)量.同心,方邊,有孔測(cè)量?jī)x.第1部分:通用方程式和不確定性指南 |
Natural Gas Fluids Measurement - Concentric, Square-Edged Orifice Meters, Part 1 - General Equations and Uncertainty Guidelines |
| ANSI/API 2530 Part 2-1991 |
天然氣流體測(cè)量.同心,方邊,有孔測(cè)量?jī)x.第2部分:安裝要求和規(guī)范 |
Natural Gas Fluids Measurement - Concentric, Square-Edged Orifice Meters, Part 2 - Specification and Installation Requirements |
| ANSI/API 2530 Part 3-1991 |
石油測(cè)量標(biāo)準(zhǔn)手冊(cè).第14章:天然氣流體測(cè)量.第3節(jié):同心,方邊,有孔測(cè)量?jī)x.第3部分:天然氣應(yīng)用 |
Manual of Petroleum Measurement Standards, Chapter 14 - Natural Gas Fluids Measurement, Section 3 - Concentric, Square-Edged Orifice Meters, Part 3 - Natural Gas Applications |
| ANSI/API 2610-1994 |
油庫(kù)和貯罐設(shè)備的設(shè)計(jì)、建造、操作、維護(hù)和檢查 |
Design, Construction, Operation, Maintenance and Inspection of Terminal and Tank Facilities |
| ANSI/API 520-1992 |
煉油廠(chǎng)中減壓設(shè)備的定尺寸、選擇和安裝.第1部分:定尺寸和選擇 |
Sizing, Selection, and Installation of Pressure-Relieving Devices in Refineries - Part I, Sizing and Selection |
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