F48 核燃料元件及其分析试验方法 标准查询与下载

EJ/T 802-1993 压水堆核电厂燃料组件管座焊缝x射线照相检验方法

X-ray photographic inspection method for weld seam of fuel assembly pipe seat in pressurized water reactor nuclear power plant

EJ/T 781-1993 研究堆板型燃料元件铀均匀性检测方法

Research on detection method of uranium homogeneity in stacked fuel elements

EJ/T 782-1993 U2Si-Al燃料板铀-235装载量的控制与测量

Control and Measurement of U2Si-Al Fuel Plate Uranium-235 Loading

DIN 25705:1993 烧结的核燃料片的陶瓷相学

Ceramography of sintered nuclear fuel tablets

EJ/T 733-1992 反应堆燃料棒表面铀沾污测定方法

Method for Determination of Uranium Contamination on the Surface of Reactor Fuel Rods

EJ/T 724-1992 核燃料后处理厂防火准则

Guidelines for Fire Protection of Nuclear Fuel Reprocessing Plants

EJ/T 723-1992 轻水堆核燃料元件厂防火准则

Code of fire protection for light water reactor nuclear fuel plant

EJ/T 679-1992 脉冲堆燃料元件技术条件

Pulse reactor fuel element technical conditions

EJ/T 680-1992 U3Si2-Al板型燃料组件设计导则

Design guidelines for U3Si2-Al plate-type fuel assemblies

EJ 658-1992 脉冲堆燃料元件设计准则

Design criteria for pulsed reactor fuel elements

ASTM E453-79(1996)e1 燃料元件的包覆检验包括机械性能的测定

1.1 This practice covers the procedures for postirradiation examination of cladding, determination of breached nuclear fuel elements, selection of material and tests for radiation studies, determination of radiation conditions, conduction of tests for mechanical properties of cladding, and the reporting of data.1.2 The purpose of this practice is to provide detailed guidelines for the postirradiation examination of fuel element cladding and to achieve better correlation and interpretation of the data in the field of radiation effects.1.3 This practice may be applied to metallic cladding from all types of fuel elements. The tests described in this practice for determining mechanical properties of the fuel element cladding practice should be included in the preirradiation characterization of the cladding and for planning irradiation effects tests for evaluation of materials for cladding and other components in nuclear reactors. Note 18212;The values stated in SI units as described in Standard E 380 are to be regarded as the standard.

Standard Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties

ASTM E453-79(2001) 燃料元件的包覆检验包括机械性能的测定

The physical and mechanical properties of cladding materials can be altered by exposure to a high-energy neutron flux. The magnitude and relationship of these changes are functions of the material and its metallurgical condition; the amount, rate, and energy spectrum of the radiation; the exposure temperature; the test temperature; the purity, velocity, volume, and purification system of the coolant; and effects of contained fuel.1.1 This practice covers the procedures for postirradiation examination of cladding, determination of breached nuclear fuel elements, selection of material and tests for radiation studies, determination of radiation conditions, conduction of tests for mechanical properties of cladding, and the reporting of data.1.2 The purpose of this practice is to provide detailed guidelines for the postirradiation examination of fuel element cladding and to achieve better correlation and interpretation of the data in the field of radiation effects.1.3 This practice may be applied to metallic cladding from all types of fuel elements. The tests described in this practice for determining mechanical properties of the fuel element cladding practice should be included in the preirradiation characterization of the cladding and for planning irradiation effects tests for evaluation of materials for cladding and other components in nuclear reactors. Note 18212;The values stated in SI units as described in Standard E 380 are to be regarded as the standard.

Standard Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties

NF C66-131:1975 架空线路用绝缘子和器材.外带金属加固件的长杆型陶瓷绝缘子.特性.尺寸

INSULATORS AND FITTINGS FOR OVERHEAD LINES. LONG ROD INSULATORS OF CERAMIC MATERIAL WITH EXTERNAL METAL FITTINGS. CHARACTERISTICS. DIMENSIONS.