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HJ 1127-2020 in English

HJ 1127-2020 in English

VALID

Technical Specifications on Determination of Gamma-ray Emitting Radionuclides in Environmental Samples for Emergency Monitoring

  • Issued on:2020-04-09
  • Implemented on:2020-04-30
  • File Format:PDF
  • Delivery:Via email within 5 business days
Price(USD): $630.00
$612.00
Standard No: HJ 1127-2020
Document status: VALID
Title in English: Technical Specifications on Determination of Gamma-ray Emitting Radionuclides in Environmental Samples for Emergency Monitoring
Title in Chinese: 应急监测中环境样品 γ 核素测量技术规范
Language: English
File Format: Electronic (PDF)
Delivery: Via email within 5 business days
Issued on: 2020-04-09
Implemented on: 2020-04-30
Professional Classification: HJ-Environment
Related Keywords: environmental samples
biological samples
sample processing aerosol samples
nuclear accident emergency monitoring
emergency monitoring introduction analysis
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本标准规定了核与辐射事故应急情况下,环境样品 γ 核素的测量技术。
本标准适用于应急监测中,使用实验室高纯锗 γ 能谱仪测量环境介质中 γ 核素,其他测量手段也可参照本标准。


Introduction

Analysis of the core content of the standard

This standard establishes for the first time a complete technical system for the measurement of γ nuclides in environmental samples for nuclear accident emergency monitoring in my country, focusing on the application requirements of high-purity germanium γ spectrometers. The efficiency calibration database provided in Appendix A covers 4 types of P-type (40-70%) and 5 types of N-type (30-70%) detectors, including Monte Carlo simulation efficiency curves for soil, water, biological and other media.


Comparison of Technical Requirements of Key Instruments

Parameters P-type detector N-type detector
Energy response range Above 50 keV Above 20 keV
Relative detection efficiency ≥20% ≥20%
Energy resolution (60Co 1332.5 keV) ≤2.5 keV

Special requirements for sample processing

  • Aerosol samples: Ultra-large flow (φ70×15 mm) need to be pressed into a cake shape, and large flow (φ50×6 mm) needs to be folded
  • Biological samples: Leafy vegetables need to be chopped into 1 cm segments and compacted when measured using the 2L Marin cup (Appendix F)
  • Contaminated samples: The detector must be wrapped with plastic film and a background check must be performed immediately after measurement

Innovations in quality control

The standard proposes a quality control indicator of double sample error ratio (DER) ≤3.0, and requires at least one retest for every 20 samples. Quantitative control is achieved through the formula: DER = |ACoriginal-ACdup|/√(uc2+uc2).


Application of Nuclide Identification Database

The fission product master nuclide library established in Appendix E contains 77 key nuclides, which are divided into the following categories according to their half-lives:

  1. Early stage of accident (<24h): short-lived nuclides such as 132I and 135I
  2. Middle stage (1-10d): 131I and 140Ba
  3. Late stage (>30d): long-lived nuclides such as 137Cs and 90Sr

Implementation Suggestions

Suggested laboratories:

  • Pre-establishment of efficiency calibration database for different detector types
  • Regular update of nuclide library (refer to ASTM D7784-12 standard)
  • Special verification of Marin Cup measurement geometry (Appendix F)

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