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GB/T 43062-2023 English PDF

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GB/T 43062-2023: Nuclear energy - Determination of neutron fluence and displacement per atom(dpa) in reactor vessel and internals
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Basic data

Standard ID GB/T 43062-2023 (GB/T43062-2023)
Description (Translated English) Nuclear energy - Determination of neutron fluence and displacement per atom(dpa) in reactor vessel and internals
Sector / Industry National Standard (Recommended)
Classification of Chinese Standard F60
Classification of International Standard 27.120.10
Word Count Estimation 14,125
Date of Issue 2023-09-07
Date of Implementation 2023-09-07
Issuing agency(ies) State Administration for Market Regulation, China National Standardization Administration

GB/T 43062-2023: Nuclear energy - Determination of neutron fluence and displacement per atom(dpa) in reactor vessel and internals


---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
ICS 27.120.10 CCSF60 National Standards of People's Republic of China Nuclear power reactor pressure vessels and internals Determination of neutron fluence and number of atomic dislocations (dpa) (ISO 19226.2017,MOD) Published on 2023-09-07 Implemented on 2023-09-07 State Administration for Market Regulation Released by the National Standardization Administration Committee

Table of contents

Preface III Introduction IV 1 Scope 1 2 Normative reference documents 1 3 Terms and Definitions 1 4 Transport theory calculation model 2 4.1 General 2 4.1.1 Output requirements 2 4.1.2 Stationary source transport calculation method 3 4.2 Transport calculation 3 4.2.1 Data input 3 4.2.2 Discrete ordinate method (SN) 3 4.2.3 Monte Carlo transport method 4 4.2.4 Conjugate fluence calculation 4 4.3 Verification of calculated neutron fluence values 4 4.4 Determination of calculation uncertainty 4 5 Neutron dose determination of reactor pressure vessels 5 5.1 General 5 5.2 General requirements for neutron metrology evaluation of reactor pressure vessels5 5.3 Stable product neutron dosimeter 5 5.4 Dosimeter response parameters 6 5.5 Uncertainty estimation and measurement verification in standard neutron fields 6 6 Comparison of calculation and measurement 6 6.1 General 6 6.2 Direct comparison of calculated activity with measured sensor activity6 6.3 Comparison of Calculated Response Rate and Measured Average Full Power Response Rate 6 6.4 Comparison between calculation and measurement using least squares adjustment method 6 7 Determination of the best estimated fluence7 8 Calculation methods for dpa and gas production 7 8.1 General 7 8.2 Number of atomic dislocations (dpa) 7 8.3 Gas generation 7 Reference 9

Foreword

This document complies with the provisions of GB/T 1.1-2020 "Standardization Work Guidelines Part 1.Structure and Drafting Rules of Standardization Documents" Drafting. This document is modified to adopt ISO 19226.2017 "Nuclear energy reactor pressure vessels and internal components Neutron fluence and atomic dislocation times (dpa) determination”. Compared with ISO 19226.2017, this document has made the following structural adjustments. ---Chapter 8 adds 8.1 to avoid the appearance of suspended sections, 8.2 corresponds to 8.1 in ISO 19226.2017, and 8.3 corresponds to ISO 19226. 8.2 in.2017. The technical differences between this document and ISO 19226.2017 and their reasons are as follows. ---Replaced ANSI/ANS19.10 and ASTME170-16a (see Chapter 2) with normatively quoted GB/T 4960.2 to suit In response to my country's technical conditions, the operability is increased. The following editorial changes have been made to this document. ---Adjusted the notes in the scope and placed them at the end of this chapter; --- Added enumeration instructions for the two types of nuclear databases "China CENDL" and "Russian BROND" (see 4.2.1) to improve example explanations Integrity of knowledge; ---Added references ANSI/ANS19.10 and ASTME170-16a (see references [1] and [2]); ---Deleted references [1]~[6], [21]~[29] (see references in ISO 19226.2017). Please note that some content in this document may be subject to patents. The publisher of this document assumes no responsibility for identifying patents. This document is proposed and coordinated by the National Nuclear Energy Standardization Technical Committee (SAC/TC58). This document was drafted by. Nuclear Industry Standardization Institute, China General Nuclear Power Research Institute Co., Ltd., China Institute of Atomic Energy, Shanghai Nuclear Engineering Engineering Research and Design Institute Co., Ltd., China Nuclear Power Research and Design Institute, China Nuclear Power Co., Ltd., and China Nuclear Power Engineering Co., Ltd. The main drafters of this document. Liu Shangyuan, Deng Ruiyuan, Sun Yecong, Li Dongsheng, He Xinfu, Wu Feifei, Jia Qi, Zheng Zheng, Dong Zhenbang, Zhang Xueyao, Miao Jianxin, Luo Jun, Tian Yingnan, Wang Yaxiao.

Introduction

This document is intended for use in the following situations. a) Involves the determination of exposure parameters used to predict radiation damage to reactor pressure vessels and reactor internals. The irradiation parameter can be neutron injection Amount and/or number of atomic dislocations (dpa). b) Involves the determination of material properties of reactor pressure vessels and reactor internals exposed to neutron irradiation. c) Licensing procedures involving regulatory agencies, such as the preparation of regulatory guidelines and analysis of pressure vessels and reactors irradiated by neutrons; Reports on the integrity and material properties of reactor internal components should be made. Nuclear power reactor pressure vessels and internals Determination of neutron fluence and number of atomic dislocations (dpa)

1 Scope

This document specifies a procedure for the assessment of irradiation of components between the reactor core and the containment vessel based on a given core neutron source. The amount of irradiation can be expressed by neutron fluence, number of atomic dislocations (dpa) or helium nuclide production. The evaluation of irradiation may use neutron fluence rate as appropriate. calculations or measurements from dosimeters in the pressure vessel and reactor cavity. This document applies to different reactor types such as pressurized water reactors (PWRs), boiling water reactors (BWRs) and pressurized heavy water reactors (PHWRs). Determination of neutron fluence and atomic dislocation number (dpa) of the reactor pressure vessel and internal components. This document also establishes a method for evaluating the neutron damage characteristics of reactor pressure vessels and internal components of PWRs, BWRs, and PHWRs. process. Damage mainly refers to direct damage due to the number of atomic dislocations caused by collision with neutrons, and indirect damage caused by gas production. Receive damage. The extent of both types of damage depends strongly on the neutron energy spectrum. Therefore, for a given neutron fluence and neutron energy spectrum, the total cumulative original The calculation of the number of ion ionization times is an important data for reactor life management. Note. The “neutron source” in this document refers to the distribution of fission neutron sources in the reactor core.

2 Normative reference documents

The contents of the following documents constitute essential provisions of this document through normative references in the text. Among them, the dated quotations For undated referenced documents, only the version corresponding to that date applies to this document; for undated referenced documents, the latest version (including all amendments) applies to this document. GB/T 4960.2 Nuclear scientific and technical terminology fission reactor

3 Terms and definitions

The terms and definitions defined in GB/T 4960.2 and the following apply to this document. 3.1 accuracyofameasured/calculatedvalue The difference between a measured/calculated value and the true value, usually due to systematic errors caused by the measurement or calculation process. 3.2 benchmarkexperimentbenchmarkexperiment A well-defined set of physical experiments whose results are judged to be sufficiently accurate to be used as a reference point for calculations. Note. This judgment is made by a group of experts in the field. 3.3 The most accurate neutron based on all available measurements, calculations and adjustments based on bias estimates, least squares analysis and engineering judgment fluence value. 3.4 Mathematical equations, approximations, assumptions, relevant parameters, and computational procedures that produce computational results.

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