Estimation of radioactivity impact for RDE based on HTR-10 hypothetical accident - a case study

Udiyani, Pmu Pande Made; Kuntjoro, SK Sri; Husnayani, I.; Setiawan, M. Budi; Santa, S. A.

doi:10.1088/1742-6596/1198/2/022037

Cited by 7 publications

(4 citation statements)

References 16 publications

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“…Meanwhile, for postulation, LOCA (lost of coolant accident), is assumed to be the abnormal event [10][11]. Source term calculations using a mechanistic source term approach for large and SMR HTR and PWR-types have been carried out using similar methods in several studies [12][13][14]. The calculation of the LOCA accident conditions for the PWR-1000 MWe using the NUREG and EUR reference parameters [7][8][9][10][11], as well as the experimental, deterministic, and probabilistic process combination parameters have also been carried out [12][13][14][15].…”

Section: Introduction mentioning

confidence: 99%

Calculation of Radioactive Source Term Release From Flexblue NPP

Setiawan

Udiyani

2021

Tri Dasa Mega

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One of the National Research Programs (PRN) in the energy sector of the Indonesian Ministry of Research and Technology for the period of 2020-2024 is small modular reactor (SMR) nuclear power plant (NPP) assessment. The France’s Flexblue is a PWR-based SMR submerged reactor with a power of 160 MWe. The Flexblue reactor module was built on the ocean site and easily provided the supply of reactor modules, in accordance with the conditions of Indonesia as an archipelagic country. Therefore, it is necessary to know the release of fission products (source term), which is necessary for the study of the radiation safety of a nuclear reactor. This paper aims to examine the source term in normal operating conditions and abnormal normal operating conditions, as well as postulated accidents. Based on the Flexblue reactor core parameter data, the calculation of the reactor core inventory uses the ORIGEN2 software is previously evaluated. The source term calculation uses a mechanistic approach and a graded approach. The normal source term is calculated assuming the presence of impurities on the fuel plate, due to fabrication limitations. Meanwhile, the abnormal source term is postulated in the LOCA event. The core reactor inventory and source term is divided into 8 radionuclide groups which are Noble gasses group (Xe, Kr); Halogen (I); Akali Metal (Cs, Rb); Tellurium Group (Te, Sb, Sc); Barium-Strontium Group (Ba, Sr); Noble Metals (Ru, Rh, Pd, Mo, Tc, Co); Lanthanides group (La, Zr, Nd, Eu, Nb, Pm, Pr, Sm, Y, Cm, Am) and Cerium Group (Ce, Pu , Np).

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Section: Introduction mentioning

confidence: 99%

Calculation of Radioactive Source Term Release From Flexblue NPP

Setiawan

Udiyani

2021

Tri Dasa Mega

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“…Calculations on source term of normal operations for PWR-1000MWe, as well as SMRtype PWR and HTGR, have been carried out using similar methods in several studies [2][3][4], along with the environmental consequences [3][4][5][6]. Calculations for postulated accident conditions, both Design Basis Accident (DBA) and Beyond Design Basis Accident (BDBA), for PWR-1000MWe using the NUREG and EUR references have also been obtained [7][8][9][10][11]. Source term calculations using a combination of experimental, deterministic, and probabilistic processes have also been carried out [12][13][14][15].…”

Section: Introduction *mentioning

confidence: 99%

Source Term Assessment for 100 Mwe Pressurized Water Reactor

Udiyani

Setiawan

2020

Tri Dasa Mega

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One of the barriers on the implementation of nuclear energy in Indonesia is public perception towards the safety of nuclear power plants (NPPs). Therefore, it is necessary to perform a study about the radiation impact of normal and abnormal operations of an NPP. In accordance to the program of Ministry of Research and Technology period 2020-2024, concerning the plan to build a small modular reactor (SMR)-type NPP, a radiation safety study has been performed for the 100 MWe Pressurized Water Reactor (PWR-100MWe). Source term release of radioactive substances into the environment from PWR-100MWe is a starting point in the study of the radiological consequences of reactor operation. Therefore, this paper will examine the PWR-100MWe source term under normal and abnormal operating conditions, according to the design and the design basis accident (DBA). The initial trigger of the DBA is Lost of Coolant Accident (LOCA) such as Small LOCA and Large LOCA. Due to the limitations of available SMR data, the study of PWR-100MWe source term refers to the assumption of the release fraction of fission products per subsystem in a larger 1000MWe PWR. It is expected from this assumption that pessimistic source term will be obtained. The study begins with calculation of PWR-100MWe core inventory using ORIGEN2 code based on PWR-100MWe reactor parameters. Through the mechanistic source term model and PWR-1000MWe release parameters, source terms will be obtained for normal operation and abnormal conditions i.e. DBA. Normal source term is used to calculate the consequences of normal operation, which will be used for environmental monitoring and environmental safety analysis of the site. Whereas accident source term is the basis for calculating the radiological consequences of accidents used for SAR documents and nuclear preparedness.Keywords: SMR, PWR-100MWe, normal operation, source term, accident

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“…The priority of BATAN activities in the energy sector for the past five years is the design development of Experimental Power Reactor (ReaktorDayaEksperimental/RDE). RDE is a high temperature gas-cooled reactor (HTGR) with a power of 10 MWt,which is expected to be capable to conduct experiments related to high temperatures and partial fulfillment of electrical energy for the Serpong Nuclear Region in Puspiptek [1][2][3][4][5]. HTGR isa GenIV advanced reactor concept.…”

Section: Introduction *mentioning

confidence: 99%

“…The coating consists of four layers that serve to hold the fission products inside the fuel element. The coolant used is helium and its moderatoris graphite [2,[4][5][6][7][8][9][10][11]. Thanks to these features, unlike the light water reactor (LWR), HTGR is meltdown-proof [2,11].…”

Section: Introduction *mentioning

confidence: 99%

Estimation of the Radioactive Source Term From Rde Accident Postulation

et al. 2019

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The design process of Experimental Power Reactor (Reaktor Daya Eksperimental/RDE) has been carried out by BATAN for the last five years, adopting HTGR-type reactor with thermal power of 10 MW. RDE is designed with the reference of similar reactor, namely HTR-10. During this process, source term estimation is required to prove the safety of RDE design, as well as to fulfill the concept of As Low As Reasonably Achievable (ALARA) in radiation protection. The source term is affected by the magnitude of the radioactive substances released from the reactor core due to an accident. Conservative accident postulations on the RDE are water ingress and depressurization accidents. Based on these postulations, source term estimation was performed. It follows the mechanistic source term flow, with conservative assumptions for the radioactive release of fuel into the coolant, reactor building, and finally discharged into the environment. Assumptions for the calculation are taken from conservative removable parameters.The result of source term calculation due to the water ingress accident for Xe-133 noble gas is 8.97E+12 Bq, Cs-137 is 3.59E+07 Bq, and I-131 is 4.34E+10 Bq. As for depressurization accident, the source term activity for Xe-133 is 3.90E+13Bq, Cs-137 is 1.56E+07 Bq, and I-131 is 1.89E+10Bq. The source term calculation results obtained in this work shows a higher number compared to the HTR-10 source term used as a reference. The difference is possibly due to the differences in reactor inventory calculations and the more conservative assumptions for source term calculation.Keywords: RDE, HTGR, Radioactive, Source term, accident

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Estimation of radioactivity impact for RDE based on HTR-10 hypothetical accident - a case study

Cited by 7 publications

References 16 publications

Calculation of Radioactive Source Term Release From Flexblue NPP

Calculation of Radioactive Source Term Release From Flexblue NPP

Source Term Assessment for 100 Mwe Pressurized Water Reactor

Estimation of the Radioactive Source Term From Rde Accident Postulation

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