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<p>Radionuclide analysis in reactor coolant water is critical for ensuring operational safety, fuel integrity, and adherence to the as low as reasonably achievable (ALARA) principle. This study aims to identify and quantify gamma-emitting radionuclides in-situ in the coolant water of the GA Siwabessy multipurpose reactor (RSG-GAS) during operation at 15&#xa0;MW thermal power. A high-purity germanium (HPGe)-based gamma spectrometry system was employed to continuously analyze water samples drawn from three strategic locations (A, B, and C) at depths of 10–1100&#xa0;cm in the reactor pool. Identified radionuclides were classified into three main categories: (1) activation products of impurities (<sup>41</sup>Ar, <sup>24</sup>Na, <sup>38</sup>Cl, <sup>42</sup>K), (2) corrosion products from structural materials (<sup>27</sup>Mg, <sup>28</sup>Al, <sup>5</sup><sup>6</sup>Mn, <sup>6</sup><sup>5</sup>Ni, <sup>5</sup><sup>9</sup>Fe), and (3) fission products released from fuel cladding (<sup>86</sup>Rb, <sup>135</sup>Xe, <sup>135</sup>I, <sup>131</sup>I, <sup>13</sup><sup>7</sup>Cs). Results revealed the highest activity at Location A (900&#xa0;cm depth), dominated by corrosion radionuclides particularly <sup>28</sup>Al (16,979&#xa0;Bq/L) and <sup>27</sup>Al&#xa0;(13,240&#xa0;Bq/L) indicating ongoing interaction between structural materials and the irradiated environment. Meanwhile, volatile fission products such as <sup>131</sup>I (36.6&#xa0;Bq/L) and <sup>137</sup>Cs (118.4&#xa0;Bq/L) remained below the limits specified in the RSG-GAS Safety Analysis Report (SAR) <sup>131</sup>I (1495&#xa0;Bq/L), <sup>133</sup>I (27,230&#xa0;Bq/L) and <sup>137</sup>Cs (239&#xa0;Bq/L), confirming fuel cladding integrity. The in-situ system proved effective as a real-time monitoring tool for assessing coolant quality and detecting early anomalies, thereby supporting proactive water-chemistry management and safer reactor operations.</p>

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Radionuclide analysis of RSG-GAS reactor cooling water using an in-situ gamma spectrometer

  • 期刊论文

  • 发表日期：

    2026年4月30日

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  • Nugraha Luhur,
  • Mohamad Rafi,
  • Deden Saprudin,
  • Muhammad Budi Setiawan,
  • Kusdiana,
  • Muhammad Gading Permadi,
  • Fahmi Alfa Muslimu,
  • Puspitasari Ramadania,
  • Saka Wahyu Hidayat,
  • Elistia Rizka Susanti

摘要

Radionuclide analysis in reactor coolant water is critical for ensuring operational safety, fuel integrity, and adherence to the as low as reasonably achievable (ALARA) principle. This study aims to identify and quantify gamma-emitting radionuclides in-situ in the coolant water of the GA Siwabessy multipurpose reactor (RSG-GAS) during operation at 15 MW thermal power. A high-purity germanium (HPGe)-based gamma spectrometry system was employed to continuously analyze water samples drawn from three strategic locations (A, B, and C) at depths of 10–1100 cm in the reactor pool. Identified radionuclides were classified into three main categories: (1) activation products of impurities (41Ar, 24Na, 38Cl, 42K), (2) corrosion products from structural materials (27Mg, 28Al, 56Mn, 65Ni, 59Fe), and (3) fission products released from fuel cladding (86Rb, 135Xe, 135I, 131I, 137Cs). Results revealed the highest activity at Location A (900 cm depth), dominated by corrosion radionuclides particularly 28Al (16,979 Bq/L) and 27Al (13,240 Bq/L) indicating ongoing interaction between structural materials and the irradiated environment. Meanwhile, volatile fission products such as 131I (36.6 Bq/L) and 137Cs (118.4 Bq/L) remained below the limits specified in the RSG-GAS Safety Analysis Report (SAR) 131I (1495 Bq/L), 133I (27,230 Bq/L) and 137Cs (239 Bq/L), confirming fuel cladding integrity. The in-situ system proved effective as a real-time monitoring tool for assessing coolant quality and detecting early anomalies, thereby supporting proactive water-chemistry management and safer reactor operations.