Garger E K, Kashpur V A, Li W B, Tschiersch J
NASU-National Academy of Science of Ukraine, Institute for Safety Problems of Nuclear Power Plants, Kirova Str. 36-A, 07270, Chernobyl, Kiev Region, Ukraine.
Radiat Environ Biophys. 2006 Jul;45(2):105-14. doi: 10.1007/s00411-006-0047-2. Epub 2006 May 30.
The release of radioactive particles through large gaps in the containment of the destroyed Chernobyl reactor was assessed during two measurement periods. In 1996-1999, a total radionuclide flow rate of 274 Bq s(-1) or 8.64 x 10(9) Bq year(-1) was determined. These releases were predominantly due to (137)Cs (78.5%), (90)Sr (21.1%), and (239+240)Pu (0.4%). The mean activity concentration in the aerosol measured directly at the gaps was about 240 mBq m(-3) with an activity median aerodynamic diameter (AMAD) of 2.4 microm for (137)Cs, 120 mBq m(-3) with an AMAD in the range 3.1-13 microm for (90)Sr, 1.8 mBq m(-3) with an AMAD in the range 3.5-11 microm for (239+240)Pu, and 2.0 mBq m(-3) with an AMAD of 1.5 microm for (241)Am. The resulting total inhalation dose rate calculated close to the gaps was about 100 nSv h(-1). In the near environment, the mean (137)Cs activity in the aerosol was 2.2 mBq m(-3) with an AMAD of 2.2 microm, which gave rise to an inhalation dose rate of about two orders of magnitude lower than the corresponding dose rate at the gaps. Occasionally, however, dose levels were measured in the near environment that were similar to those at the gaps. In 2000-2003, lower activity concentrations were observed. The decrease was more pronounced at the gaps than in the near environment. The results indicate that effective dose due to inhalation must be considered for the dose assessment of construction workers who will be deployed at the Chernobyl site to reconstruct the old or to build the new Shelter, in the future.
在两个测量阶段对通过受损切尔诺贝利反应堆安全壳大缺口释放的放射性粒子进行了评估。在1996年至1999年期间,确定的总放射性核素流率为274贝克勒尔每秒(Bq s⁻¹)或8.64×10⁹贝克勒尔每年(Bq year⁻¹)。这些释放主要归因于¹³⁷铯(Cs,78.5%)、⁹⁰锶(Sr,21.1%)和²³⁹⁺²⁴⁰钚(Pu,0.4%)。在缺口处直接测量的气溶胶中的平均活度浓度,¹³⁷铯约为240毫贝克勒尔每立方米(mBq m⁻³),活度中值空气动力学直径(AMAD)为2.4微米;⁹⁰锶为120毫贝克勒尔每立方米,AMAD在3.1至13微米范围内;²³⁹⁺²⁴⁰钚为1.8毫贝克勒尔每立方米,AMAD在3.5至11微米范围内;²⁴¹镅(Am)为2.0毫贝克勒尔每立方米,AMAD为1.5微米。在靠近缺口处计算得出的总吸入剂量率约为100纳希沃特每小时(nSv h⁻¹)。在近环境中,气溶胶中的¹³⁷铯平均活度为2.2毫贝克勒尔每立方米,AMAD为2.2微米,由此产生的吸入剂量率比缺口处相应的剂量率低约两个数量级。然而,偶尔在近环境中测量到的剂量水平与缺口处的相似。在2000年至2003年期间,观察到活度浓度较低。缺口处的下降比近环境中更为明显。结果表明,对于未来将被部署到切尔诺贝利现场重建旧“石棺”或建造新“石棺”的建筑工人进行剂量评估时,必须考虑吸入所致的有效剂量。