27.120.10 反应堆工程 标准查询与下载
共找到 572 条与 反应堆工程 相关的标准，共 39 页
Owners' Report For Repair/Replacement activity as required by the provisions of the ASME Code, section XI
- ICS
- 27.120.10
- CCS
- F65
- 发布
- 2011-07
- 实施
Certificate Holders' Data Report for Storage Tanks
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2011-07
- 实施
To establish a proper calibration area for nuclear surface gauges. To reduce the chance of improper calibration. Note 18212;The quality of the results produced by this standard is dependent on the competence of the personnel performing it, and the suitability of the equipment and facilities used. Agencies that meet the criteria of practice D3740 are generally considered capable of competent and objective testing/inspection/etc. Users of this standard are cautioned that compliance with practice D3740 does not in itself assure a means of evaluating some of those factors.1.1 This guide outlines procedures for setup of a nuclear gauge calibration facility in either a shielded bay or an unshielded areaGuide A and Guide B, respectively. 1.2 This guide does not attempt to describe the calibration techniques or methods. It is assumed that this guide will be used by persons familiar with the operations of the gauge and in performing proper calibration, service and maintenance. 1.3 This guide does not attempt to address maintenance or service procedures related to the gauge. 1.4 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system may not be exact equivalents; therefore, each system shall be used independently of the other. Combining values from the two systems may result in non-conformance with the standard. 1.5 This guide 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 guide to establish appropriate safety, and health practices and determine the applicability of regulatory limitations prior to use. 1.6 This guide offers an organized collection of information or a series of options and does not recommend a specific course of action. This document cannot replace education or experience and should be used in conjunction with professional judgment. Not all aspects of this guide may be applicable in all circumstances. This ASTM standard is not intended to represent or replace the standard of care by which the adequacy of a given professional service must be judged, nor should this document be applied without consideration of a project’s many unique aspects. The word “Standard” in the title of this document has been approved through ASTM consensus process. 1.7 All observed and calculated values shall conform to the guidelines for significant digits and rounding established in practice D6026. 1.7.1 The method used to specify how data are collected, calculated, or recorded in this standard is not directly related to the accuracy to which the data can be applied in the design or other uses, or both. How one applies the results obtained using this standard is beyond its scope.
Standard Guide for Calibration Facility Setup for Nuclear Surface Gauges
- ICS
- 27.120.10
- CCS
- F82
- 发布
- 2011
- 实施
This report identifies several Non Destructive Examination (NDE) technologies of advanced monitoring, diagnostics and prognostics systems (e.g., acoustic emission, ultrasonic, advanced material characterization) applicable to components of High Temperature Gas-cooled Reactors (HTGRs) for in-service inspection.
NON DESTRUCTIVE EXAMINATION (NDE) AND IN-SERVICE INSPECTION (ISI) TECHNOLOGY FOR HIGH TEMPERATURE REACTORS
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2011
- 实施
Nuclear power plants. Instrumentation and control systems important for safety. Separation
- ICS
- 27.120.10
- CCS
- 发布
- 2011
- 实施
- 2012-01-01
This standard specifies the minimum acceptable startup reactor physics test program to determine if the operating characteristics of the core are consistent with the design predictions, which provides assurance that the core can be operated as designed.
Reload Startup Physics Tests for Pressurized Water Reactors
- ICS
- 27.120.10
- CCS
- F60
- 发布
- 2011
- 实施
This standard provides guidance for performing and validating the sequence of steady state calculations leading to prediction, in all types of nuclear reactors, of: (1) Reaction rate spatial distributions (2) Reactivity (3) Change of isotopic compositions with time. The standard provides: (1) Guidance for the selection of computational methods. (2) Criteria for verification of calculational methods used by reactor core analysts (3) Criteria for evaluation of accuracy and range of applicability of data and methods (4) Requirements for documentation of the preceding. The scope of the standard is shown schematically in Figure 1.
Steady-State Neutronics Methods for Power Reactor Analysis
- ICS
- 27.120.10
- CCS
- F60
- 发布
- 2011
- 实施
Rules for Inservice Inspection of Nuclear Power Plant Components
- ICS
- 27.120.10
- CCS
- F60
- 发布
- 2011
- 实施
Rules for Construction of Nuclear Facility Components
- ICS
- 27.120.10
- CCS
- F60
- 发布
- 2011
- 实施
Each power reactor has a specific DEX value that is their technical requirement limit. These values may vary from about 200 to about 900 μCi/g based upon the height of their plant vent the location of the site boundary, the calculated reactor coolant activity for a condition of 1% fuel defects, and general atmospheric modeling that is ascribed to that particular plant site. Should the DEX measured activity exceed the technical requirement limit the plant enters an LCO requiring action on plant operation by the operators. The determination of DEX is performed in a similar manner to that used in determining DEI, except that the calculation of DEX is based on the acute dose to the whole body and considers the noble gases 85mKr, 85Kr, 87Kr, 88Kr, 131mXe, 133mXe, 133Xe, 135mXe, 135Xe, and 138Xe which are significant in terms of contribution to whole body dose. It is important to note that only fission gases are included in this calculation, and only the ones noted in 1. For example 83mKr is not included even though its half life is 1.86 hours. The reason for this is that this radionuclide cannot be easily determined by gamma spectrometry (low energy x-rays at 32 and 9 keV) and its dose consequence is vanishingly small compared to the other, more prevalent krypton radionuclides. Activity from 41Ar, 19F, 16N, and 11C, all of which predominantly will be in gaseous forms in the RCS, are not included in this calculation. If a specific noble-gas radionuclide is not detected, it should be assumed to be present at the minimum-detectable activity. The determination of DOSE-EQUIVALENT XE-133 shall be performed using effective dose-conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12, or the average gamma-disintegration energies as provided in ICRP Publication 38 (′′Radionuclide Transformations'') or similar source.1.1 This practice applies to the calculation of the dose equivalent to 133Xe in the reactor coolant of nuclear power reactors resulting from the radioactivity of all noble gas fission products. 1.2 The values given in parentheses are mathematical conversions to SI units, which are provided for information only and are not considered standard. 1.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.
Standard Practice for Calculation of Dose Equivalent Xenon (DEX) for Radioactive Xenon Fission Products in Reactor Coolant
- ICS
- 27.120.10
- CCS
- F60
- 发布
- 2011
- 实施
Nuclear facilities. Criteria for the design and the operation of containment and ventilation systems for nuclear reactors
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2010-08-31
- 实施
- 2010-08-31
his International Standard specifies the applicable requirements related to the design and the operation of containment and ventilation systems of nuclear power plants and research reactors, taking into account the following.
Nuclear facilities - Criteria for the design and the operation of containment and ventilation systems for nuclear reactors
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2010-08
- 实施
Certificates Holders' Certificate of Conformance for Welded Supports
- ICS
- 27.120.10
- CCS
- J33
- 发布
- 2010-07-01
- 实施
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Appendices
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2010-07-01
- 实施
