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GB/T 41591-2022Initial criticality tests for pressurized water reactor of nuclear power plants (English PDF)

压水堆核电厂反应堆首次临界试验

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Issued by

SAMR; SAC

Level / Type

National · Recommended

Issue date

July 11, 2022

Implementation date

February 1, 2023

Scope

GB/T 41591-2022 is the English-translated version of 压水堆核电厂反应堆首次临界试验.

GB/T 41591-2022 sets out the first criticality test of the reactor of a pressurized water reactor nuclear power plant. It fixes the purpose of the test, the initial conditions, the test methods, the precautions, the acceptance criteria and the requirements for test records and reports.

The method clause covers reaching first criticality, verifying the linearity and overlap of the ex-core nuclear instrumentation system, determining the neutron fluence rate range for the zero-power physics experiments and calibrating the reactivity meter.

It defines the inverse count rate ratio, reactivity, doubling period, startup rate in decades per minute and the starting interval of predicted primary coolant boron concentration.

It applies during the commissioning of a new plant, cites NB/T 20145, was issued on 11 July 2022 and has applied since 1 February 2023.

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Document preview — GB/T 41591-2022

National Standard of the People's Republic of China

ICS
27.120.20
Classification
F 63

Issued by: State Administration for Market Regulation; Standardization Administration of the PRC

Contents

  • Preface
  • 1 Scope
  • 2 Normative references
  • 3 Terms and Definitions
  • 4 Test purpose
  • 5 Test initial conditions
  • 6 Test method
  • 6.1 Method overview
  • 6.2 The first critical
  • 6.3 Verification of linearity and overlap of the ex-reactor nuclear instrumentation system
  • 6.4 Determining the neutron fluence rate range for zero-power physical experiments
  • 6.5 Calibrating the Reactivity Meter
  • 7 Notes
  • 8 Acceptance Criteria
  • 9 Test records and reports

Foreword

This document is in accordance with the provisions of GB/T 1.1-2020 "Guidelines for Standardization Work Part 1: Structure and Drafting Rules of Standardization Documents" drafted.

This document is proposed and managed by the National Nuclear Energy Standardization Technical Committee (SAC/TC58).

1 Scope

This document specifies the test purpose, initial conditions, test methods, precautions, acceptance guidelines, and requirements for test records and reports of the first criticality test of a pressurized water reactor nuclear power plant.

This document applies to the first criticality test of the reactor during the commissioning phase of a new pressurized water reactor nuclear power plant.

2 Normative references

The contents of the following documents constitute essential provisions of this document through normative references in the text. Among them, dated citations documents, only the version corresponding to that date applies to this document; for undated references, the latest edition (including all amendments) applies to this document.

NB/T 20145 Nuclear power plant commissioning test procedures and report writing specifications

3 Terms and Definitions

The following terms and definitions apply to this document.

3.1 Inverse count rate ratio; ICRR

The inverse of the ratio of the current neutron count rate to the base count rate.

Calculate according to formula (1): ICRR = C0/C.

where: C0 --- base count rate; C --- Current neutron count rate.

3.2 Reactive reactivity

A parameter that characterizes the degree to which a chain nuclear fission reaction medium or system deviates from criticality.

3.3 Double period

The time required for the neutron fluence rate in the reactor to change exponentially by a factor of 1.

3.4 Startup rate

A physical quantity that characterizes the rate of change of the neutron fluence rate in a reactor.

Note: The starting rate is in DPM (DecadesPerMinute), and 1DPM means that the neutron fluence rate increases 10 times per minute according to an exponential law.

3.5 Starting interval

An interval of predicted primary coolant boron concentration before the reactor reaches criticality.

Note: Considering factors such as calculation error, measurement error and uncertainty, the reactor may enter a critical state at any time during the start-up interval.

......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 15 pages — is available in the English PDF.

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