F63 动力堆 标准查询与下载

EJ/T 1112-2000 压水堆核电厂用涂料.漆膜可去污性的测定

Determination of the decontaminability of coatings for use in pressurized water reactor nuclear power plants

EJ/T 1111-2000 压水堆核电厂用涂料漆膜受γ射线辐照影响的试验方法

Test method for effects of gamma radiation on coatings for use in Pressurized water reactor nuclear power plants

EJ/T 759.2-2000 核电厂控制室 控制器和屏幕显示的应用 第2部分：屏幕显示的应用

Applications of controllers and screen displays in nuclear power plant control rooms Part 2: Applications of screen displays

EJ/T 320-1998 压水堆核电厂反应堆总体设计准则

General design criteria of reactor for pressurized water reactor nuclear power plants

ANSI/ANS 19.11-1997 水慢化动力堆反应性的慢化剂温度系数的计算和测量

This standard provides guidance and specifies criteria for determining the MTC in water moderated power reactors. Measurement of the isothermal temperature coefficient of reactivity (ITC) at hot zero power (HZP) conditions is covered in American National Standard Reload Startup Physics Tests for Pressurized Water Reactors, ANSI/ANS-19.6.1-1997 [1]. This standard therefore addresses the calculation of the ITC at HZP and the calculation and measurement of the MTC at power. At present, this standard addresses the calculation and measurement of the MTC only in PWRs, because that is the only type of power reactor currently sited in the United States for which measurement of the MTC is required.

Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors

ANSI/ANS 57.5-1996 轻水反应堆燃料组件的结构设计和评估

This standard sets forth a series of design conditions and functional requirements for the design of fuel assemblies for light water cooled commercial power reactors. It includes specific requirements for design, as well as design criteria to ensure adequate fuel assembly performance. The standard establishes a procedure for performing an evaluation of the mechanical design of fuel assemblies. It does not address the various aspects of neutronic or thermal-hydraulic performance except where these factors impose loads or constraints on the mechanical design of the fuel assemblies.

Light Water Reactors Fuel Assembly Mechanical Design and Evaluation

EJ/T 322-1994 压水堆核电厂反应堆压力容器设计准则

Design criteria for reactor pressure vessels in pressurized water reactor nuclear power plants

IEC 60737:1982 核动力反应堆中堆芯温度或主包壳温度测量 特性和试验方法

This standard is appicable to general aspects of design, characteristics, manufacturing and test methods for in-core temperature measurement instrumentation in nuclear power plants. Emphasis is placed on the features peculiar to the nuclear application a

In-core temperature or primary envelope temperature measurements in nuclear power reactors. Characteristics and test methods

UNI 7459-1975 核设备－动力反应堆．保护系统的设计标准

La p/esente norma ha lo scopo di stabilire i criteri di progetto dei sistemi di protezione dei reattori nucleari destinati alla produzione di energia elettrica, ai fini delle prestazioni funzionali e della affidabilità. La completa rispondenza di un sistema di protezione alla presente norma non ne assicura necessariamente la piena adeguatezza. D'altra parte, la mancata applicazione di uno qualunque dei criteri, ove non siano adottate altre giustificate soluzioni di progetto, può, nella maggior parte dei casi, essere indice di carenza del sistema.

Nuclear power plants. Power reactors. Criteria for protection systems.