Determination of 137Cs and 90Sr in wood fuels and their ashes available in Austria.

IF 0.7 4区 环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES
Viktoria Herzner, Christian Katzlberger, Christoph Pfeifer, Franz Josef Maringer, Martin Weigl-Kuska
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Abstract

This study assessed the radiological risk of wood fuels and their ashes in Austria, including wood chips, logs, pellets, and briquettes. Commercially purchased wood fuels are often of unknown origin and may have been imported. 137Cs activity concentrations were measured in wood fuels (69 samples) and their ashes (27 samples) using gamma-ray spectrometers with high-purity germanium detectors. 90Sr analyses were performed on 12 ash samples after chemical separation using PerkinElmer 1220 Quantulus™ liquid scintillation counters. Results showed 137Cs activity concentrations ranging from 0.327 to 8.36 Bq kg-1 in wood fuels (average 2.1 Bq kg-1) and from 11.80 to 867 Bq kg-1 in ashes (average 310 Bq kg-1). The 90Sr activity concentrations in ashes ranged from 363 to 1200 Bq kg-1 (average 655 Bq kg-1). Summarizing, this study suggests that wood fuels currently available in Austria do not pose a significant radiological risk from their ashes, negating the need for import regulations.

Abstract Image

Abstract Image

Abstract Image

奥地利木材燃料及其灰烬中137Cs和90Sr的测定。
本研究评估了奥地利木质燃料及其灰烬的辐射风险,包括木屑、原木、颗粒和煤块。商业上购买的木质燃料往往来源不明,可能是进口的。利用带高纯度锗探测器的伽马射线能谱仪测量了木材燃料(69个样本)及其灰烬(27个样本)中的137Cs活度浓度。使用PerkinElmer 1220 quantum™液体闪烁计数器对化学分离后的12份灰分样品进行90Sr分析。结果表明,137Cs活性浓度在木材燃料中为0.327 ~ 8.36 Bq kg-1(平均2.1 Bq kg-1),在灰烬中为11.80 ~ 867 Bq kg-1(平均310 Bq kg-1)。灰烬中90Sr活度浓度为363 ~ 1200 Bq kg-1(平均655 Bq kg-1)。总而言之,这项研究表明,奥地利目前可获得的木质燃料不会因其灰烬而造成重大的辐射风险,因此无需制定进口法规。
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来源期刊
Radiation protection dosimetry
Radiation protection dosimetry 环境科学-公共卫生、环境卫生与职业卫生
CiteScore
1.40
自引率
10.00%
发文量
223
审稿时长
6-12 weeks
期刊介绍: Radiation Protection Dosimetry covers all aspects of personal and environmental dosimetry and monitoring, for both ionising and non-ionising radiations. This includes biological aspects, physical concepts, biophysical dosimetry, external and internal personal dosimetry and monitoring, environmental and workplace monitoring, accident dosimetry, and dosimetry related to the protection of patients. Particular emphasis is placed on papers covering the fundamentals of dosimetry; units, radiation quantities and conversion factors. Papers covering archaeological dating are included only if the fundamental measurement method or technique, such as thermoluminescence, has direct application to personal dosimetry measurements. Papers covering the dosimetric aspects of radon or other naturally occurring radioactive materials and low level radiation are included. Animal experiments and ecological sample measurements are not included unless there is a significant relevant content reason.
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