共找到 569 条与 反应堆工程 相关的标准,共 38 页
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Subsection NCA - General Requirements for Division 1 and Division 2
ASME Boiler & Pressure Vessel Code - Section 11: Rules for Inservice Inspection of Nuclear Power Plant Components
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NH - Class 1 Components in Elevated Temperature Service
IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NC - Class 2 Components
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NG - Core Support Structures
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection ND - Class 3 Components
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 2: Code for Concrete Containments
This report evaluates testing methods on the measurement of fracture properties for design of ASME Boiler and Pressure Vessel Code, Section VIII, Division 3 (ASME BPVC VIII-3) pressure vessels for hydrogen service.
EVALUATION OF FRACTURE PROPERTIES TEST METHODS FOR HYDROGEN SERVICE
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NE - Class MC Components
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NF - Supports
General principal of nuclear reactor instrumentation-First supplement to publication 60231(1967)
이 표준은 원자력 발전소의 원자로 계측에 관한 일반원칙, 중자자 속 측정, 온도 측정, 냉
General principal of nuclear reactor instrumentation-First supplement to publication 60231(1967)
General principal of nuclear reactor instrumentation-First supplement to publication 60231(1967)
Nuclear reactors-Response time in resistance temperature detectors(RTD)-In situ measurements
Identification of fuel assemblies for nuclear power reactors
Nuclear energy-Performance and testing requirements for criticality detection and alarm systems
Fourth supplement:Principles of instrumentation for pressurized water reactors
Nuclear reactors-Response time in resistance temperature detectors(RTD)-In situ measurements
General principles of nuclear reactor instrumentation
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