F09 卫生、安全、劳动保护 标准查询与下载

DIN 25403-7:1996 核燃料处理和装运临界安全性.水中低浓缩二氧化铀栅棒的临界数据

The document specifies requirements relating to criticality safety during the processing and handling of fissile materials, in particular criticality data for low enriched uranium dioxide lattices in water. The data and graphs which are given in the standard apply to an isolated lattice system of uranium-dioxide (UO) rods without cladding tube in light water (HO) with maximum reflection by light water.#,,#

Criticality safety in processing and handling fissile materials - Part 7: Criticality data for low enriched uranium dioxide lattices in water

DIN 25474:1996 核技设施(反应堆除外)保持临界安全的管理措施

The document provides guidance on measures with administrative character for observation of criticality safety in nuclear facilities excluding the reactor. It gives instructions on the handling of nuclear fuel the transport of nuclear fuel outside of nuclear facilities or for protection against influences of ther persons, are not dealt with in the document.#,,#

Measures of administrative character for conservation of criticality safety in nuclear facilities excluding reactors

EJ/T 994-1996 轻水堆核电厂工作人员辐射防护培训规定

Regulations on Radiation Protection Training for Workers of Light Water Reactor Nuclear Power Plants

EJ/T 988-1996 用于评估铀燃料制造厂核临界事故潜在辐射后果的假定

Assumptions used to assess the potential radiological consequences of a nuclear criticality accident at a uranium fuel fabrication plant

ISO 1709:1995 核能 贮存 装卸和加工易裂变材料的临界安全原则

Specifies the basic principles and limitations which govern operations with fissile materials. Describes general criticality safety criteria for equipment design and for the development of operating controls. Does not cover quality assurance requirements or details of equipment or operational procedures, does not deal with the effects of radiation on man or materials.These criteria apply to operations with fissile materials outside nuclear reactors but within the boundaries of nuclear facilities. Replaces the first edition, which has been technically revised.

Nuclear energy - Fissile materials - Principles of criticality safety in storing, handling and processing

DIN 25403-4:1995 核燃料的处理和和搬运时的临界安全性.第4部分:二氧化铀轻水混合物的临界数据

The document specifies requirements relating to criticality safety during the processing and handling of fissile material, in particular criticality data for uranium dioxid light-water mixtures. It gives numerical values and curves shall be used on isolated system of uranium dioxid (UO) homogeniously distributed in light water with uranium enrichments of 5 %, 20 % and 100 % massfractions U 235 with maximum reflection by light water.

Criticality safety in processing and handling fissile materials - Part 4: Criticality data for uranium dioxide light-water mixtures

DIN 25403-8:1995 核燃料的处理和和搬运时的临界安全性.第8部分:硝酸双氧铀(100%铀235)轻水混合物的临界数据

Criticality safety in processing and handling of fissile materials - Part 8: Criticality data of uranyl nitrate (100% uranium 235) light-water mixture

DIN 25403-2:1995 核燃料的处理和和搬运时的临界安全性.第2部分:铀235金属轻水混合物的临界数据

The document specifies requirements relating to criticality safety during the processing and handling of fissile material, in particular criticality data for uranium 235 metal light-water mixtures. The given numerical values and curves shall be used on a isolated system of uranium 235 metal homogeniously distributed in light water maximum reflection by light water.#,,#

Criticality safety in processing and handling fissile materials - Part 2: Criticality data for uranium 235 metal light-water mixtures

EJ/T 967-1995 用于评估核燃料后处理厂核临界事故潜在辐射后果的假定

Assumptions used to assess potential radiological consequences of nuclear criticality accidents at nuclear fuel reprocessing plants

EJ/T 945-1995 铀矿山安全性评价

Safety Evaluation of Uranium Mine

DIN 25422:1994 放射性材料的保存.保存设施的防辐射、防火及防盗安全保护方面的要求

This document consists of safety related requirements for the planning and installing of storage facilities against radiation, fire and theft. The requirements correspond with  6 und  74 radiation protection order so far radioactive material is concerned.#,,#

Storage of radioactive materials - Requirements on protection against radiation, fire and theft to be met by storage facilities

ANS 58.8-1994(R2008) 安全相关操作者动作的时间响应设计标准

This standard establishes time response design criteria for safety-related operator actions to be used in the design of light water reactor (LWR) nuclear power plants. The criteria are used to determine the minimum response time intervals for safety-related operator actions that are taken to mitigate design basis events (DBEs) which result in an automatic reactor trip. This standard specifies time requirements that are to be met to receive credit in the safety analysis for operator actions that initiate or control safety-related functions. Specifically, the criteria provide bases: (1) For establishing certain requirements for determining whether a particular action to initiate or control a safety-related system might be accomplished by operator action or must be accomplished by an automatic action. (2) For determining when design modifications can obviate the need for automatic actions that would otherwise be required. (3) For general guidance for hardware, such as instrumentation, controls, indicators, and annunciators necessary to support safety-related operator actions.

Time Response Design Criteria for Safety-Related Operator Actions

EJ/T 683-1992 铀、钍矿冶放射性废物安全管理

Safety management of radioactive waste in uranium and thorium mining and metallurgy

ANSI/ANS 58.3-1992 核安全有关的系统和元件的物理防护

This standard sets forth physical protection criteria for nuclear safety-related systems and components in stations using light water reactors (LWRs). This standard includes an identification of potential hazards to nuclear safety-related systems and components and acceptable means of ensuring the protection of this equipment from these hazards.

Physical Protection for Nuclear Safety-Related Systems and Components

DIN ISO 7753:1991 核能.临界状态探测和报警系统的性能和试验要求

The standard specifies performance and testing requirements for criticality detection and alarm systems, it is applicable to all operations with plutonium, uranium 233, uranium enriched in the 235 isotope, and other fissionable materials in which inadvertent criticality may occur and cause the exposure of personnel to unacceptable amounts of radiation.

Nuclear energy; performance and testing requirements for criticality detection and alarm systems; identical with ISO 7753:1987

DIN 25403-1:1991 处理和搬运易裂变材料的临界安全性.原则

The standard specifies requirements for the handling of fissile materials inside of nuclear facilities. It is not valid for nuclear power plants. The requirements concern technical criteria and recommendations to guarantee criticality safety during processing and handling of fissile materials.

Criticality safety in processing and handling of fissile materials; principles

ANSI/ANS 8.20-1991 核临界安全培训

This standard provides criteria for nuclear criticality safety training for personnel associated with operations outside reactors where a potential exists for criticality accidents. It is not sufficient for the training of nuclear criticality staff.

Nuclear Criticality Safety Training

EJ/T 515-1990 受权的检查机构、核在役检验员、主检验员的资格和责任

Qualifications and responsibilities of authorized inspection agencies, nuclear in-service inspectors, and chief inspectors

EJ/T 516-1990 核电厂检查、检验和试验人员资格

本标准规定了核电厂检查、检验和试验人员资格的基本要求。 本标准适用于在核电厂制造、建造、调试和运行阶段中，对构筑物、系统和部件从事检查、检验和试验的人员。 本标准也适用于参于核电厂各项活动的其他有关单位的相应人员。 本标准不适用于无损检测人员。

Qualifications of nuclear power plant inspection, inspection and test personnel

ISO 7753:1987 核能 临界探测和报警系统的性能和检验要求

Is applicable to all operations with plutonium, uranium 233, uranium enriched in the 235 isotope, and other fissionable materials. Does not require separate additional instrumentation when the operating instrumentation of the facilities meets its requirements. Is principally concerned with gamma-radiation rate-sensing systems. Annex A refers to the specification of a minimum accident of concern, annex B provides examples of application, and annex C provides guidance for development of emergency plans. Does not include details of administrative steps or specific design and description of instrumentation.

Nuclear energy; Performance and testing requirements for criticality detection and alarm systems