Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor
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Sriyono Sriyono
, Deden Saprudin
, Mohamad Rafi
, Geni R. Sunaryo
, Nugraha Luhur
Abstract
The liquid radioactive waste generated by the G.A. Siwabessy reactor (RSG-GAS) is categorized into low-activity liquid radwaste (LALR) and medium-activity liquid radwaste (MALR). The radionuclide content of both LALR and MALR can use as an indicator of the structural integrity of the reactor’s systems, structures, and components (SSC). To evaluate the degradation of the reactor SSC, the radionuclide species were identified, and their activities were measured using gamma spectroscopy. Based on the identified radionuclides, the process of their formation can be traced. The radionuclides identified in LALR were 24Na, 51Cr, 59Fe, 60Co, 65Zn, and 124Sb, while the radionuclides in MALR were 24Na, 51Cr, 58Co, 59Fe, 60Co, 65Ni, 65Zn, 89Kr, 90Kr, 109Cd, 131I, 132I, 140Ba, 137Cs, 146Ce, and several others. The radionuclides found can be classified into corrosion product activation (60Co, 65Zn, 51Cr, 59Fe, 24Na, 65Ni), topaz impurities activation (51Cr, 59Fe, 60Co, 65Zn), fission product (90Kr, 140Ba, 131I, 137Cs, etc.), and demineralized water impurities activation (51Cr, 59Fe, 65Zn, 60Co, etc.). After comparing the activity value of each radionuclide with the limit value in the safety analysis report document, we can conclude that the activity of each one is below the required level. It can infer that the structural integrity of reactor SSC is still well maintain. During routine monitoring, the radionuclide content in the primary coolant fluctuates depending on the reactor load. The concentration of radionuclides detected varies when a large or small number of research samples are loaded onto the core. Nevertheless, their activities remain within the required safety limits.
Funding source: BRIN Indonesia
Award Identifier / Grant number: B-265/V/TN/4/2022
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Research funding: This research is supported by the National Research and Innovation Agency of Indonesia (BRIN) through the degree by research (DBR) scholarship scheme and Government of Republic of Indonesia finance budget under Rumah Program HITN-2023.
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Author contributions: All authors contributed equally in this research.
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Conflict of interest statement: There is no conflict of interest.
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Supplementary Material
This article contains supplementary material (https://doi.org/10.1515/kern-2022-0113).
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Artikel in diesem Heft
- Frontmatter
- An approach for an extension of the deflagration model in containment code system COCOSYS to separate burned and unburned atmosphere via junctions
- Neutronic analysis of the European sodium cooled fast reactor with Monte Carlo code OpenMC
- Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor
- Performance evaluation of a currently in-use dry storage cask design for spent accident tolerant fuel loading case under normal operation condition
- Optimization of divertor design for Pakistan spherical tokamak
- Role of impurity and thermal noise on the radiation sources in ITER using DT fuel
- An investigation of multistream plate-fin heat exchanger modelling and design: a review
- Ensuring safety of new, advanced small modular reactors for fundamental safety and with an optimal main heat transport systems configuration
- Study on calculation model and risk area of radionuclide diffusion in coastal waters under nuclear leakage accidents with different levels
- Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer
- Experimental study on boiling heat transfer of γ-Fe2O3 nanofluids on a downward heated surface
- Evaluating the influence of radial power heterogeneity of fuel rod on its temperature in an accelerator driven subcritical system
- Heat transfer enhancement of heat exchanger using rectangular channel with cavities
- Calendar of events