27.120.01 核能综合 标准查询与下载

NB/T 20130-2012 混凝土辐射屏蔽

本标准规定了用于辐射屏蔽目的的混凝土的辐射屏蔽设计、选材、建造等的特征要求。 本标准适用于放射性的实验室、放射化学站、试验装置，核电厂用于辐射屏蔽目的的混凝土。

Concrete radiation shielding

ASTM C992-11 核废料储存架用硼基中子吸收材料系统标准规格

1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system. 1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials. 1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron, enriched in boron-10 could also be used. 1.4 The materials systems described herein shall be functional – that is always be capable to maintain a B10 areal density such that subcriticality Keff <0.95 or Keff <0.98 or Keff < 1.0 depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool. 1.5 A number of acceptable boron-based absorbing materials combinations are currently available while others are being developed for use in the future. This specification defines criteria essential and applicable to all materials combinations and identifies parameters a buyer should specify to satisfy a unique or particular requirement. 1.6 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.

Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks

JC/T 2023-2010 钨酸铅闪烁晶体

本标准规定了钨酸铅（PbWO）闪烁晶体的术语和定义、技术要求、检测方法、检验规则、标志、包装、运输和贮存。 本标准适用于高能粒子探测用钨酸铅闪烁晶体

Lesd tungstate scintillation crystals

JC/T 2018-2010 高能粒子探测用掺铊碘化铯晶体

本标准规定了高能粒子探测用掺铊碘化铯晶体的技术要求、检验方法、检验规则及包装、标志、运输和贮存。 本标准适用于高能粒子探测用长尺寸（150mm

Thallium doped cesium iodide crystal for high-energy particles detection

JC/T 2017-2010 氟化铅晶体

本标准规定了氟化铅（PbF）晶体的产品标记、技术要求、检测方法、检验规则、包装、标志、运输和贮存。 本标准适用于氟化铅晶体。

Lead fluoride crystal

ASTM C1562-10 临时废核燃料干燥储存系统长期运行过程中使用的材料的评估的标准指南

Information is provided in this document and other referenced documents to assist the licensee and the licensor in analyzing the materials aspects of performance of SNF and DCSS components during extended storage. The effects of the service conditions of the first licensing period are reviewed in the license renewal process. These service conditions are highlighted and discussed in Annex A1 as factors that affect materials performance in an ISFSI. Emphasis is on the effects of time, temperature, radiation, and the environment on the condition of the SNF and the performance of components of ISFSI storage systems. The storage of SNF that is irradiated under the regulations of 10 CFR Part 50 is governed by regulations in 10 CFR Part 72. Regulatory requirements for the subsequent geologic disposal of this SNF are presently given in 10 CFR Part 60, with specific requirements for the use of Yucca Mountain as a repository being given in the regulatory requirements of 10 CFR Part 63. Between the life-cycle phases of storage and disposal, SNF may be transported under the requirements of 10 CFR Part 71. Therefore, in storage, it is important to acknowledge the transport and disposal phases of the life cycle. In doing this, the materials properties that are important to these subsequent phases are to be considered in order to promote successful completion of these subsequent phases in the life cycle of SNF. Retrievability of SNF (or high-level radioactive waste) is set as a requirement in 10 CFR Part 72.122(g)(5) and 10 CFR Part 72.122(l). Care should be taken in operations conducted prior to disposal, for example, storage, transfer, and transport, to ensure that the SNF is not abused and that SNF assemblies will be retrievable, the protective value of the cladding is not degraded and remains capable of serving as an active barrier to radionuclide release during transfer and transport operations. It is possible that cladding could be altered during dry storage. The hydrogen effects, fracture toughness of the cladding and the creep behavior are important parameters to be evaluated and controlled during the dry storage phase of the life cycle. These degradation mechanisms are discussed in Annex A2 and Annex A4.1.1 Part of the total inventory of commercial spent nuclear fuel (SNF) is stored in dry cask storage systems (DCSS) under licenses granted by the U.S. Nuclear Regulatory Commission (NRC). The purpose of this guide is to provide information to assist in supporting the renewal of these licenses, safely and without removal of the SNF from its licensed confinement, for periods beyond those governed by the term of the original license. This guide provides information on materials behavior under conditions that may be important to safety evaluations for the extended service of the renewal period. This guide is written for DCSS containing light water reactor (LWR) fuel that is clad in zirconium alloy material and stored in accordance with the Code of Federal Regulations (CFR), at an independent spent-fuel storage installation (ISFSI). The components of an ISFSI, addressed in this document, include the commercial SNF, canister, cask, and all parts of the storage installation including the ISFSI pad. The language of this guide is based, in part, on the requirements for a dry SNF storage license that is granted, by the U.S. Nuclear Regulatory Commission (NRC), for up to 20 years. Although government regulations may differ for various nations, the guidance on materials properties and behavior given here is expected to have broad applicability. 1.2 This guide addresses many of the factors affecting the time-dependent behavior of materials under ISFSI service [10 CFR Part 72.42]. These factors are those regarded to be important to performance, in license extension, beyond the currently licensed 20-year period. Examples of these factors are given in this guide and they include materials al......

Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems

ASTM E1297-08 通过铌放射活性测定快中子反应速率的标准试验方法

p>Refer to Practice E 261 for a general discussion of the determination of decay rates, reaction rates, and neutron fluence rates with threshold detectors (1-29). Refer to Practice E 1006, Practice E 185 and Guide E 1018 for the use and application of results obtained by this test method.(34-36) The half-life of 93mNb is 5730 ± 220 days (30) and has a K X-ray emission probability of 0.1099 ± 0.0025 per decay (30). The Kα and Kβ X-rays of niobium are at 16.5213–16.152 and 18.618–18.953 keV, respectively. The recommended 93Nb (n,n′)93mNb cross section comes from the IRDF-90 cross section compendium (31), was drawn from the RRDF-98 cross section evaluations (37) and is shown in Fig. 1. Chemical dissolution of the irradiated niobium to produce very low mass-per-unit area sources is an effective way to obtain consistent results. The direct counting of foils or wires can produce satisfactory results provided appropriate methods and interpretations are employed. It is possible to use liquid scintillation methods to measure the niobium activity provided the radioactive material can be kept uniformly in solution and appropriate corrections can be made for interfering activities. The measured reaction rates can be used to correlate neutron exposures, provide comparison with calculated reaction rates, and determine neutron fluences. Reaction rates can be determined with greater accuracy than fluence rates because of the current uncertainty in the cross section versus energy shape. The 93Nb(n,n′)93mNb reaction has the desirable properties of monitoring neutron exposures related to neutron damage of nuclear facility structural components. It has an energy response range corresponding to the damage function of steel and has a half-life sufficiently long to allow its use in very long exposures (up to about 40 years). Monitoring long exposures is useful in determining the long-term integrity of nuclear facility components.1.1 This test method describes procedures for measuring reaction rates by the activation reaction 93Nb(n,n′)93mNb. 1.2 This activation reaction is useful for monitoring neutrons with energies above approximately 0.5 MeV and for irradiation times up to about 30 years. 1.3 With suitable techniques, fast-neutron reaction rates for neutrons with energy distribution similar to fission neutrons can be determined in fast-neutron fluences above about 1016cm−2. In the presence of high thermal-neutron fluence rates (>1012cm−2·s−1), the transmutation of 93mNb due to neutron capture should be investigated. In the presence of high-energy neutron spectra such as are associated with fusion and spallation sources, the transmutation of 93mNb by reactions such as (n,2n) may occur and should be investigated. 1.4 Procedures for other fast-neutron monitors are referenced in Practice E 261. 1.5 Fast-neutron fluence rates can be determined ......

Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

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

ASME N511-2007 核气体处理、加热、通风和空气调节系统的现行测试

In-Service Testing of Nuclear Air Treatment, Heating, Ventilating, and Air-Conditioning Systems

In-Service Testing of Nuclear Air Treatment, Heating, Ventilating, and Air-Conditioning Systems

ANSI/NIRMA CM1.0-2007 核设备结构管理指南

This standard provides guidelines for the development and implementation of Configuration Management (CM) Programs by organizations operating nuclear facilities. The principle focus is on establishing essential elements of a CM Program and identifying associated industry-acceptable approaches for satisfying the requirements for each element. Its purpose is to be a guidance document not a prescriptive standard. The goal is to ensure the consistency between the design requirements, physical installations and related facility information for nuclear power plants and other nuclear facilities as applicable.

Guidelines for Configuration Management for Nuclear Facilities

EJ/T 1201-2006 核燃料后处理厂退役设计安全准则

本标准规定了核燃料后处理厂退役设计的安全准则。 本标准适用于正常关闭的核燃料后处理厂的退役设计。非正常关闭的后处理厂以及放射性废物处理设施的退役设计也可参照使用。

Safety criteria for decommissioning design of spect fuel reprocessing plant

ASTM C992-06 核乏燃料贮存架用硼基中子吸收材料系统的标准规范

1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 0.2% by weight (depending upon the geological origin of the boron). Boron, enriched in boron-10 could also be used. 1.4 The materials systems described herein shall be functional - that is always be capable to maintain a B10 areal density such that subcriticality Keff 0.95 or Keff 0.98 or Keff 1.0 depending on the design specification for the service life (approximately 40 years) in the operating environment of a nuclear spent fuel pool.1.5 A number of acceptable boron-based absorbing materials combinations are currently available while others are being developed for use in the future. This specification defines criteria essential and applicable to all materials combinations and identifies parameters a buyer should specify to satisfy a unique or particular requirement.1.6 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.

Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks

EJ 375-2005 职业性内照射个人监测规定

本标准规定了对工作人员职业内照射个人监测原则、监测方法、监测计划及对测量结果解释的基本要求。 本标准适用于职业照射的内照射个人监测。

Regulations of individual monitoring for occupational internal exposure

EJ/T 604-2005 NIM标准机箱、插件产品规范

本规范规定了NIM标准机箱(以下简称机箱)及NIM标准插件(以下简称插件)的技术要求、试验方法和检验规则。 本规范适用于NIM标准机箱及插件的设计、生产和质量检验。

Specification for NIM standard bin and module

EJ/T 1082-2005 核电厂防火准则

本标准规定了核电厂从建造到运行整个寿期的火灾预防、探测和灭火的要求。 本标准适用于轻水堆、重水堆和气冷堆类型的核电厂，对钠冷快中子增殖堆没有特别地论述，但是在这些导则中可以找到可用于快中子增殖堆系统的防火措施。

Fire protection criteria for nuclear power plants

SNI 18-7106-2005 放射性元素试验用电离室系统的使用和校准

Calibration and usage of ionization chamber systems for assay of radionuclides

SNI 18-7105-2005 放射性核素成像装置的性质和测试条件. 伽马相机类型

Characteristics and test condition of radionuclide imaging devices - Gamma cameras anger type

EJ/T 499-2004 压水堆核电厂一次中子源棒设计和制造技术条件

本标准规定了压水堆核电厂一次中子源棒的结构设计、材料、制造、试验和检验、包装、运输、操 作和贮存等技术要求。 本标准适用于压水堆核电厂一次中子源棒的设计、制造、包装和运输。

Specification for design and manufacture of primary neutron source rod for pressurized water reactor nuclear power plant

DIN 55991-3:2003 涂料.核设施涂层.第3部分:涂覆作业、计划和程序

The document lays down general principles for planning and procedure of coating work for nuclear facilities, with the aim to ensure the correct processing of coating materials tested according to DIN 55991-1 and fulfilling the requirements given in DIN 55991-1. The document applies to coating work for mineral surfaces bound with cement and for metallic surfaces for the control area of nuclear facilities.#,,#

Coating materials - Coatings in nuclear facilities - Part 3: Coating work, planning and procedure

DIN 53781:2003 涂层材料.核设备涂层抗电离辐射试验方法

Coating materials - Methods for testing the resistance of coatings to ionizing radiation in nuclear plants