F49 核材料、核燃料生产、处理设备和设施 标准查询与下载

EJ/T 808-2007 铀燃料元件厂设计准则

本标准规定了铀燃料元件厂设计所遵循的准则和基本要求。 本标准适用于含铀-235 丰度小于 5% 的铀燃料元件厂或试验设施的设计，亦可供其它丰度的铀加工、贮存设施设计参照使用。

Criteria for design of uranium fuel element fabrication plants

EJ/T 883-2006 压水堆核电厂乏燃料贮存设计准则

本标准规定了压水堆核电厂乏燃料贮存设施设计应遵循的基本要求。 本标准适用于具有独立燃料厂房的压水堆核电厂乏燃料贮存设施的设计；对于乏燃料贮存设施设在安全壳内的压水堆核电厂，其乏燃料贮存设施的设计可参照本标准的适用条款进行。

Design criteria for pressurized water reactor spent fuel storage facilities at nuclear power plant

HJB 364-2006 核弹头使用及管理人员资格和培训要求

Qualification and training requirements for nuclear warhead use and management personnel

EJ/T 1171-2004 铀矿冶设施选址规定

Regulations for uranium mine and processing plant site selection

ASME B00033-2004 第III节:第3部分.核废料和高放射性废物的安全壳系统和运输包装.到期日期:2004年7月

Boiler and Pressure Vessel.Section III: Division 3 - Containment Systems And Transport Packaging For Spent Nuclear Fuel And High Level Radioactive Waste Due July 2004

Section III: Division 3 - Containment Systems And Transport Packaging For Spent Nuclear Fuel And High Level Radioactive Waste Due July 2004

EJ 1107-2000 铀矿冶设施退役整治工程设计规定

The design regulations for decommissioning and restoration of uranium mining and milling facilities

ASTM C1217-00(2006) 核材料及放射性材料处理用设备设计的标准导则

1.1 Intent1.1.1 This guide covers equipment used in shielded cell or canyon facilities for the processing of nuclear and radioactive materials. It is the intent of this guide to set down the conditions and practices that have been found necessary to ensure against or to minimize the failures and outages of equipment used under the subject circumstances.1.1.2 It is intended that this guide record the principles and caveats that experience has shown to be essential to the design, fabrication, and installation of equipment capable of meeting the stringent demands of operating, dependably and safely, in a nuclear processing environment that operators can neither see nor reach directly.1.1.3 This guide sets forth generalized criteria and guidelines for the design, fabrication, and installation of equipment used in this service. This service includes the processing of radioactive wastes. Equipment is placed behind radiation shield walls and cannot be directly accessed by the operators or by maintenance personnel because of the radiation exposure hazards. In the type of shielded cell or canyon facility of interest to users of this guide, either the background radiation level remains high at all times or it is impractical to remove the process sources of radiation to facilitate in situ repairs or carry out maintenance procedures on equipment. The equipment is operated remotely, either with or without visual access to the equipment.1.2 Applicability1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions:The materials handled or processed constitute a significant radiation hazard to man or to the environment.The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded.The material handled or processed must be retained, contained, and confined within known bounds for reasons of accountability or to minimize the spread of radioactive contamination.The materials handled or processed must be kept and maintained within one or more of the following conditions:In a specific geometric array or configuration, andWithin a range of conditions that have been determined to be a critically safe set of conditions for that piece of equipment, that is, 1) in a given and specified operational position where adjacent nuclear criticality interaction conditions are known and unchanging, 2) for a given and specified set or range of operating conditions, and 3) for a given and specified process.The equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, for example, without intervening shielded viewing windows, periscopes, or a television monitoring system.1.2.2 This guide is intended to be applicable to the design of equipment for the processing of materials containing uranium and transuranium elements in any physical form under the following conditions:Such materials constitute an unacceptable radiation hazard to the operators and maintenance personnel,The need exists for the confinement of the in-process material, of dusts and particulates, or of vapors and gases arising or resulting from the handling and processing of such materials, andAny of the conditions cited in apply.1.2.3 This guide is intended to apply to the design, fabrication, and installation of ancillary and support services equipment under the following conditions:Such equipment is installed in shielded cell or canyon environments, orSuch equipment is an integral part of an in-cell processing equipment configuration, or an auxiliary component or system thereof, even though an equipment item or system may not directly hold or contain nuclear or radioactive materials under normal processing conditions.

Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials

ASTM C1062-00 核燃料溶解装置的设计、制造和安装标准指南

1.1 It is the intent of this guide to set forth criteria and procedures for the design, fabrication and installation of nuclear fuel dissolution facilities. This guide applies to and encompasses all processing steps or operations beyond the fuel shearing operation (not covered), up to and including the dissolving accountability vessel.1.2 Applicability and Exclusions1.2.1 Operations-This guide does not cover the operation of nuclear fuel dissolution facilities. Some operating considerations are noted to the extent that these impact upon or influence design. 1.2.1.1 Dissolution Procedures-Fuel compositions, fuel element geometry, and fuel manufacturing methods are subject to continuous change in response to the demands of new reactor designs and requirements. These changes preclude the inclusion of design considerations for dissolvers suitable for the processing of all possible fuel types. This guide will only address equipment associated with dissolution cycles for those fuels that have been used most extensively in reactors as of the time of issue (or revision) of this guide. (See Appendix X1.)1.2.2 Processes-This guide covers the design, fabrication and installation of nuclear fuel dissolution facilities for fuels of the type currently used in Pressurized Water Reactors (PWR). Boiling Water Reactors (BWR), Pressurized Heavy Water Reactors (PHWR) and Heavy Water Reactors (HWR) and the fuel dissolution processing technologies discussed herein. However, much of the information and criteria presented may be applicable to the equipment for other dissolution processes such as for enriched uranium-aluminum fuels from typical research reactors, as well as for dissolution processes for some thorium and plutonium-containing fuels and others. The guide does not address equipment design for the dissolution of high burn-up or mixed oxide fuels.1.2.2.1 This guide does not address special dissolution processes that may require substantially different equipment or pose different hazards than those associated with the fuel types noted above. Examples of precluded cases are electrolytic dissolution and sodium-bonded fuels processing. The guide does not address the design and fabrication of continuous dissolvers.1.2.3 Ancillary or auxiliary facilities (for example, steam, cooling water, electrical services) are not covered. Cold chemical feed considerations are addressed briefly.1.2.4 Dissolution Pretreatment-Fuel pretreatment steps incidental to the preparation of spent fuel assemblies for dissolution reprocessing are not covered by this guide. This exclusion applies to thermal treatment steps such as "Voloxidation" to drive off gases prior to dissolution, to mechanical decladding operations or process steps associated with fuel elements disassembly and removal of end fittings, to chopping and shearing operations, and to any other pretreatment operations judged essential to an efficient nuclear fuels dissolution step.1.2.5 Fundamentals- This guide does not address specific chemical, physical or mechanical technology, fluid mechanics, stress analysis or other engineering fundamentals that are also applied in the creation of a safe design for nuclear fuel dissolution facilities.1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities

ASTM C1217-00 核材料及放射性材料处理用设备设计的标准导则

1.1 Intent: 1.1.1 This guide covers equipment used in shielded cell or canyon facilities for the processing of nuclear and radioactive materials. It is the intent of this guide to set down the conditions and practices that have been found necessary to ensure against or to minimize the failures and outages of equipment used under the subject circumstances. 1.1.2 It is intended that this guide record the principles and caveats that experience has shown to be essential to the design, fabrication, and installation of equipment capable of meeting the stringent demands of operating, dependably and safely, in a nuclear processing environment that operators can neither see nor reach directly. 1.1.3 This guide sets forth generalized criteria and guidelines for the design, fabrication, and installation of equipment used in this service. This service includes the processing of radioactive wastes. Equipment is placed behind radiation shield walls and cannot be directly accessed by the operators or by maintenance personnel because of the radiation exposure hazards. In the type of shielded cell or canyon facility of interest to users of this guide, either the background radiation level remains high at all times or it is impractical to remove the process sources of radiation to facilitate in situ repairs or carry out maintenance procedures on equipment. The equipment is operated remotely, either with or without visual access to the equipment. 1.2 Applicability: 1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions: 1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment. 1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded. 1.2.1.3 The material handled or processed must be retained, contained, and confined within known bounds for reasons of accountability or to minimize the spread of radioactive contamination. 1.2.1.4 The materials handled or processed must be kept and maintained within one or more of the following conditions: (1) In a specific geometric array or configuration, and (2) Within a range of conditions that have been determined to be a critically safe set of conditions for that piece of equipment, that is, 1) in a given and specified operational position where adjacent nuclear criticality interaction conditions are known and unchanging, 2) for a given and specified set or range of operating conditions, and 3) for a given and specified process. 1.2.1.5 The equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, for example, without intervening shielded viewing windows, periscopes, or a television monitoring system. 1.2.2 This guide is intended to be applicable to the design of equipment for the processing of materials containing uranium and trans-uranium elements in any physical form under the following conditions: 1.2.2.1 Such materials constitute an unacceptable radiation hazard to the operators and maintenance personnel, 1.2.2.2 The need exists for the confinement of the in-process material, of dusts and particulates, or of vapors and gases arising or resulting from the handling and processing of such materials, and 1.2.2.3 Any of the conditions cited in 1.2.1 apply. 1.2.3 This guide is intended to apply to the design, fabrication, and installation of ancillary and support services equipment under the following conditions: 1.2.3.1 Such equipment is installed in shielded cell or canyon environments, or 1.2.3.2 Such equipment is an integral part of an in-cell processing equipment configuration, or an auxiliary component or system thereof, even though an equipment ite......

Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials

EJ/T 1090-1998 铀矿冶设施所造成的气态(载)放射性与有毒性源项的确定

Determination of the gaseous radioactive and toxic source terms for uranium mining and milling facilities

EJ/T 1071-1998 铀矿冶工程设计规定

The design regulations for uranium mining metallurgy engineering

EJ/T 443-1997 铀矿石浓缩物包装桶技术条件

Specification of packaging tank for uranium ore concetrate

EJ/T 1037-1996 铀加工及燃料制造设施退役环境影响报告的标准格式与内容

Standard format and content for the decommissioning environmental impact report of uranium processing and fuel fabrication facilities

EJ/T 999-1996 核燃料后处理厂自控仪表工程设计规定

Regulations on Engineering Design of Automatic Control Instruments for Nuclear Fuel Reprocessing Plants

CSA N292.2-96-1996 照明油料干式储藏.第1版.通用指导书第1号

Dry Storage of Irradiated Fuel First Edition; General Instruction No 1

Dry Storage of Irradiated Fuel First Edition; General Instruction No 1

EJ/T 938-1995 核燃料后处理厂通风与空气净化设计规定

Design regulations for ventilation and air purification of nuclear fuel reprocessing plants

EJ/T 939-1995 核燃料后处理厂建（构）筑物、系统和部件的分级准则

Classification guidelines for nuclear fuel reprocessing plant buildings (structures), systems and components

EJ 877-1994 核燃料后处理厂安全设计准则

Safety Design Criteria for Nuclear Fuel Reprocessing Plants

EJ/T 854-1994 NC型气体离心机通用技术条件

General technical conditions of NC type gas centrifuge

EJ 809-1994 铀燃料元件厂抗震设计分级

Classification of seismic design for uranium fuel element plant