27.120.10 反应堆工程 标准查询与下载
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NF; Supports
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- 27.120.10
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- 2010-01-01
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 2: Code for Concrete Containments
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- 27.120.10
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- 2010-01-01
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NB; Class 1: Components
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- 27.120.10
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- 2010-01-01
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NE; Class: MC Components
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- 27.120.10
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- 2010-01-01
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NC; Class 2: Components
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- 27.120.10
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Subsection NCA - General Requirements for Division 1 and Division 2
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- 27.120.10
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection ND; Class 3: Components
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- 27.120.10
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- 2010-01-01
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ASME Boiler & Pressure Vessel Code - Section 11: Rules for Inservice Inspection of Nuclear Power Plant Components
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- 27.120.10
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- F69
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- 2010-01-01
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NH; Class 1: Components in Elevated Temperature Service
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- 27.120.10
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- F69
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- 2010-01-01
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NG; Core Support Structures
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- 27.120.10
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- 2010-01-01
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Appendices
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- 27.120.10
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This guide deals with the difficult problem of benchmarking neutron transport calculations carried out to determine fluences for plant specific reactor geometries. The calculations are necessary for fluence determination in locations important for material radiation damage estimation and which are not accessible to measurement. The most important application of such calculations is the estimation of fluence within the reactor vessel of operating power plants to provide accurate estimates of the irradiation embrittlement of the base and weld metal in the vessel. The benchmark procedure must not only prove that calculations give reasonable results but that their uncertainties are propagated with due regard to the sensitivities of the different input parameters used in the transport calculations. Benchmarking is achieved by building up data bases of benchmark experiments that have different influences on uncertainty propagation. For example, fission spectra are the fundamental data bases which control propagation of cross section uncertainties, while such physics-dosimetry experiments as vessel wall mockups, where measurements are made within a simulated reactor vessel wall, control error propagation associated with geometrical and methods approximations in the transport calculations. This guide describes general procedures for using neutron fields with known characteristics to corroborate the calculational methodology and nuclear data used to derive neutron field information from measurements of neutron sensor response. The bases for benchmark field referencing are usually irradiations performed in standard neutron fields with well-known energy spectra and intensities. There are, however, less well known neutron fields that have been designed to mockup special environments, such as pressure vessel mockups in which it is possible to make dosimetry measurements inside of the steel volume of the “vessel”. When such mockups are suitably characterized they are also referred to as benchmark fields. A benchmark is that against which other things are referenced, hence the terminology “to benchmark reference” or “benchmark referencing”. A variety of benchmark neutron fields, other than standard neutron fields, have been developed, or pressed into service, to improve the accuracy of neutron dosimetry measurement techniques. Some of these special benchmark experiments are discussed in this standard because they have identified needs for additional benchmarking or because they have been sufficiently documented to serve as benchmarks. One dedicated effort to provide benchmarks whose radiation environments closely resemble those found outside the core of an operating reactor was the Nuclear Regulatory Commission''s Light Water Reactor Pressure Vessel Surveillance Dosimetry Improvement Program (LWR-PV-SDIP) (1) . This program promoted better monitoring of the radiation exposure of reactor vessels and, thereby, provided for better assessment of vessel end-of-life conditions. An objective of the LWR-PV-SDIP was to develop improved procedures for reactor surveillance and document them in a series of ASTM standards (see Matrix E706). The primary means chosen for validating LWR-PV-SDIP procedures was by benchmarking a series of experimental and analytical studies in a variety of fields (see Guide E2005).1.1 This guide covers general approaches for benchmarking neutron transport calculations in light water reactor systems. A companion guide (Guide
Standard Guide for Benchmark Testing of Light Water Reactor Calculations
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- 2010
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3.1 This guide describes approaches for using neutron fields with well known characteristics to perform calibrations of neutron sensors, to intercompare different methods of dosimetry, and to corroborate procedures used to derive neutron field information from measurements of neutron sensor response. 3.2 This guide discusses only selected standard and reference neutron fields which are appropriate for benchmark testing of light-water reactor dosimetry. The Standard Fields considered are neutron source environments that closely approximate the unscattered neutron spectra from 252Cf spontaneous fission and 235U thermal neutron induced fission. These standard fields were chosen for their spectral similarity to the high energy region (E > 2 MeV) of reactor spectra. The various categories of benchmark fields are defined in Terminology E170. 3.3 There are other well known neutron fields that have been designed to mockup special environments, such as pressure vessel mockups in which it is possible to make dosimetry measurements inside of the steel volume of the “vessel.” When such mockups are suitably characterized they are also referred to as benchmark fields. A variety of these engineering benchmark fields have been developed, or pressed into service, to improve the accuracy of neutron dosimetry measurement techniques. These special benchmark experiments are discussed in Guide E2006, and in Refs (1)4 and (2). 1.1 This guide covers facilities and procedures for benchmarking neutron measurements and calculations. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to calibrate integral neutron sensors; the use of certified-neutron-fluence standards to calibrate radiometric counting equipment or to determine interlaboratory measurement consistency; development of special benchmark fields to test neutron transport calculations; use of well-known fission spectra to benchmark spectrum-averaged cross sections; and the use of benchmarked data and calculations to determine the uncertainties in derived neutron dosimetry results. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
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This guide is relevant to the design of specialized support equipment and tools that are remotely operated, maintained, or viewed through shielding windows, or combinations thereof, or by other remote viewing systems. Hot cells contain substances and processes that may be extremely hazardous to personnel or the external environment, or both. Process safety and reliability are improved with successful design, installation, and operation of specialized mechanical and support equipment. Use of this guide in the design of specialized mechanical and support equipment can reduce costs, improve productivity, reduce failed hardware replacement time, and provide a standardized design approach.1.1 Intent: 1.1.1 This guide presents practices and guidelines for the design and implementation of equipment and tools to assist assembly, disassembly, alignment, fastening, maintenance, or general handling of equipment in a hot cell. Operating in a remote hot cell environment significantly increases the difficulty and time required to perform a task compared to completing a similar task directly by hand. Successful specialized support equipment and tools minimize the required effort, reduce risks, and increase operating efficiencies. 1.2 Applicability: 1.2.1 This guide may apply to the design of specialized support equipment and tools anywhere it is remotely operated, maintained, and viewed through shielding windows or by other remote viewing systems. 1.2.2 Consideration should be given to the need for specialized support equipment and tools early in the design process. 1.2.3 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. 1.3 Caveats: 1.3.1 This guide is generic in nature and addresses a wide range of remote working configurations. Other acceptable and proven international configurations exist and provide options for engineer and designer consideration. Specific designs are not a substitute for applied engineering skills, proven practices, or experience gained in any specific situation. 1.3.2 This guide does not supersede federal or state regulations, or both, or codes applicable to equipment under any conditions. 1.3.3 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 standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.
Standard Guide for Hot Cell Specialized Support Equipment and Tools
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Mechanical drive systems operability and long-term integrity are concerns that should be addressed primarily during the design phase; however, problems identified during fabrication and testing should be resolved and the changes in the design documented. Equipment operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions. This standard is intended as a supplement to other standards, and to federal and state regulations, codes, and criteria applicable to the design of equipment intended for this use. This standard is intended to be generic and to apply to a wide range of types and configurations of mechanical drive systems.1.1 Intent: 1.1.1 The intent of this standard is to provide general guidelines for the design, selection, quality assurance, installation, operation, and maintenance of mechanical drive systems used in remote hot cell environments. The term mechanical drive systems used herein, encompasses all individual components used for imparting motion to equipment systems, subsystems, assemblies, and other components. It also includes complete positioning systems and individual units that provide motive power and any position indicators necessary to monitor the motion. 1.2 Applicability: 1.2.1 This standard 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 equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, for example, without radiation shielding windows, periscopes, or a video monitoring system (Guides C1572 and C1661). 1.2.2 The system of units employed in this standard is the metric unit, also known as SI Units, which are commonly used for International Systems, and defined, by Standard for Use of International System of Units. Common nomenclature for specifying some terms; specifically horsepower uses a combination of both metric and inch-pound units. 1.3 User Caveats: 1.3.1 This standard is not a substitute for applied engineering skills, proven practices and experience. Its purpose is to provide guidance. 1.3.1.1 The guidance set forth in this standard relating to design of equipment is intended only to alert designers and engineers to those features, conditions, and procedures that have been found necessary or highly desirable to the design, selection, operation and maintenance of mechanical drive systems for the subject service conditions. 1.3.1.2 The guidance set forth results from discoveries of conditions, practices, features, or lack of features that were found to be sources of operational or maintenance problems, or causes of failure. 1.3.2 This standard does not supersede federal or state regulations, or both, and codes applicable to equipment under any conditio......
Standard Guide for Mechanical Drive Systems for Remote Operation in Hot Cell Facilities
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Practices E185 and E2215 describe a minimum program for the surveillance of reactor vessel materials, specifically mechanical property changes that occur in service. This guide may be applied in order to generate additional specific fracture toughness property information on radiation-induced property changes to better assist the determination of the optimum reactor vessel operation schemes.1.1 This guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practices E185 and E2215 for the surveillance of nuclear reactor vessels. The supplemental mechanical property tests outlined permit the acquisition of additional information on radiation-induced changes in fracture toughness, notch ductility, and yield strength properties of the reactor vessel steels. 1.2 This guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and postirradiation test planning. Guidance on data reduction and computational procedures is also given. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.
Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
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1.1 Scope. This standard specifies the minimum fire protection requirements for existing light water nuclear power plants during all phases of plant operation, including shutdown, degraded conditions, and decommissioning.
Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants
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- 27.120.10
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NH; Class 1: Components in Elevated Temperature Service; 2009b Addenda July 1, 2009
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- 27.120.10
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- F69
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- 2009-01-01
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NF; Supports; 2009b Addenda July 1, 2009
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- 27.120.10
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- 2009-01-01
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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NE; Class: MC Components; 2009b Addenda July 1, 2009
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- 27.120.10
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- 2009-01-01
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