Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

Muswema, Jérémie Lunguya; Ekoko, Gracien Bakambo; Lukanda, V. M.; Lobo, Joseph; Darko, E. O.; Boafo, Emmanuel

doi:10.1016/j.nucengdes.2014.11.014

Cited by 20 publications

(17 citation statements)

References 5 publications

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“…Fission products are released from HTGR following the radionuclide transport mechanisms. The release mechanisms includes fuel, core, building ventilation, helium purification, gaseous radioactive waste system, and neutron activation of air circulating through the reactor cavity cooling system (RCCS) [2,[10][11][12][13]. Radioactive gases accumulate within the waste gas vacuum tank and are compressed by diaphragm compressor.…”

Section: Sourceterm Calculationmentioning

confidence: 99%

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Atmospheric Dispersion Analysis for Expected Radiation Dose due to Normal Operation of RSG-GAS and RDE Reactors

et al. 2018

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BATAN is planning to build an experimental power reactor, the RDE, to complement the RSG-GAS reactor that is already operating in the Serpong Nuclear Zone (KNS). The experimental power reactor is an HTGR (high-temperature gas-cooled reactor) with 10 MWt power, while the RSG-GAS is a pool-type water-cooled reactor with 30 MWt power. According to standard regulatory practices, under normal operating conditions of the plant, radiological assessment of atmospheric releases to the environment and assessment of public exposures are considered essential. The purpose of this study is to estimate the dose acceptance in Serpong Nuclear Zone (KNS) after operate the RDE operates in KNS-2. To assess the doses, the PC-CREAM 08 computer code was used. It uses a standard Gaussian plume dispersion model and composes a suite of models and data for estimation of the radiological impact assessments of routine and continual discharges from a nuclear reactor. The input data include sourceterm from the RDE and the RSG-GAS, a stack the height of 60 m annual radionuclides release, meteorological data from the Serpong local meteorological station, and agricultural products data from Serpong site. Results show that the highest individual dose in the area around KNS for adults is 6.16×10-3 mSv/y in the S (South) direction and 300 m distance from the stack of RSG. The highest collective dose around KNS within 3 km radius is 6.37×10-3 man-Sv/yr. The results show that the radiological impact of the KNS on the critical groups of public and the individual effective doses satisfy the limits given by the Nuclear Regulatory Agency of Indonesia (BAPETEN). The operation of RDE in KNS-2 does not add significantly to acceptance radiation dose in the environment in KNS. It can also be concluded that the estimated effective doses are lower than the dose constraint of 0.3 mSv/y associated with this plant.

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Section: Sourceterm Calculationmentioning

confidence: 99%

“…Radioactive gases accumulate within the waste gas vacuum tank and are compressed by diaphragm compressor. Surge tanks retain these gases for 30 days to allow for radioactive decay before release to the environment [12,13].…”

Section: Sourceterm Calculationmentioning

confidence: 99%

Atmospheric Dispersion Analysis for Expected Radiation Dose due to Normal Operation of RSG-GAS and RDE Reactors

et al. 2018

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“…Foudil et al have estimated the source term and doses for the NUR research reactor under a hypothetical severe accident [2]. Muswema et al carried out a study to drive the source term and analyze the radiological safety for the TRICOII research reactor in Kinshasa [3]. Charalampos et al published a study about source term derivation and radiological consequences for the Greek Research Reactor [4].…”

Section: Introductionmentioning

confidence: 99%

Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident

Xoubi

2020

Science and Technology of Nuclear Installations

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The source term for the JRTR research reactor is derived under an assumed hypothetical severe accident resulting in generation of the most severe consequences. The reactor core is modeled based on the reactor technical design specifications, and the fission products inventory is calculated by using the SCALE/TRITON depletion sequence to perform burnup and decay analyses via coupling the NEWT 2-D transport lattice code to the ORIGEN-S fuel depletion code. Fifty radioisotopes contributed to the evaluation, resulting in a source term of 3.7 × 1014 Bq. Atmospheric dispersion was evaluated using the Gaussian plume model via the HOTSPOT code. The plume centerline total effective dose (TED) was found to exceed the IAEA limits for occupational exposure of 0.02 Sv; the results showed that the maximum dose is 200 Sv within 200 m from the reactor, under all the weather stability classes, after which it starts to decrease with distance, reaching 0.1 Sv at 1 km from the reactor. The radiation dose plume centerlines continue to the exceed international basic safety standards annual limit of 1 mSv for public exposure, up to 80 km from the reactor.

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“…The HotSpot Health Phys ics code, based on a Gaussi an plume model (GPM), is used for ra di a tion dose cal cu la tion and con se quence as sess ment. The HotSpot code was es tab lished by the Law rence Livermore Na tional Lab o ra tory (LLNL) to pro vide emer gency re sponse per son nel with a fast, field-por table cal cu la tion tool for eval u at ing ac ci dents in volv ing ra dio ac tive ma te ri als which has been suc cess fully applied in var i ous ra dio log i cal con se quences eval u ations [3][4][5][6][7][8][9].…”

Section: Introductionmentioning

confidence: 99%

Radiological consequences assessment of a hypothetical accident during transportation of spent nuclear fuel

Cao

Cui

2019

NUCL TECH RAD PROT

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Dur ing the trans por ta tion of spent nu clear fu els, the po ten tial re lease of the ra dio ac tive ma teri als into the at mo sphere in the case of an ac ci dent be comes a se ri ous threat to pub lic health and the en vi ron ment. In China, a com mer cial re pro cess ing plant is planned to be com missioned around 2025 based on the China nu clear roadmap. Af ter be ing cooled on site the spent nu clear fu els are trans ported to the re pro cess ing plant by train or truck. This re quires the assess ment of ra dio log i cal con se quences of such ac ci dents dur ing trans por ta tion, there fore dose cal cu la tions un der hy po thet i cal ac ci dent con di tions have been pre sented in this pa per. The to tal ef fec tive dose equiv a lent and ground de po si tion are cal cu lated us ing the HotSpot health phys ics com puter code with site-spe cific me te o ro log i cal con di tions. The re sults in dicate that the to tal ef fec tive dose equiv a lent and ground de po si tion are both de creased with the in crease of the down wind dis tance. The max i mum of the to tal ef fec tive dose equiv a lent is about 1.4×10 1 Sv, which is larger than the reg u la tion limit for the pub lic. The TEDE coun ter plot shows that the in ner re gions marked with dose con tours of 1.0×10-3 Sv are higher than the reg u la tion lim its for the pub lic, how ever this needs no in ter ven tion but any un nec es sary trip to this area should be avoided. Key words: ra dio log i cal con se quences as sess ment, at mo spheric dis per sion mod el ling, spent nu clear fuel, to tal ef fec tive dose equivalent, HotSpot

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Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

Cited by 20 publications

References 5 publications

Atmospheric Dispersion Analysis for Expected Radiation Dose due to Normal Operation of RSG-GAS and RDE Reactors

Atmospheric Dispersion Analysis for Expected Radiation Dose due to Normal Operation of RSG-GAS and RDE Reactors

Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident

Radiological consequences assessment of a hypothetical accident during transportation of spent nuclear fuel

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