The Strategy to Support HTGR fuels for The 10 MW Indonesia's Experimental Power Reactor (RDE)

Taryo, Taswanda; Ridwan, Ridwan; Sunaryo, Geni Rina; Rachmawati, Meniek

doi:10.17146/urania.2018.24.1.3729

Cited by 6 publications

(3 citation statements)

References 19 publications

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“…Indonesia already has a plan to develop a High-Temperature Gas Cooled Reactor (HTGR) in collaboration with another country, where this reactor is named Reaktor Daya Eksperimental (RDE). A nuclear power reactor has a thermal power of 10 MWth and was previously designed by the National Nuclear Energy Agency (BATAN) [1]. Helium gas is used to extract heat from the reactor core, where the RDE is moderated with graphite and uses a spherical uranium fuel element (TRISO).…”

Section: Introduction mentioning

confidence: 99%

Design Scenario and Analysis for Preliminary Specification of Steam Generator in the Peluit-40

Riyandwita¹,

Subhan²,

Setiadipura³

et al. 2023

Tri Dasa Mega

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The helical steam generator is connected to an HTGR-type nuclear reactor called PeLUIt-40 for steam production. Steam is used to generate electricity and hydrogen. A once-through helical tube bundle was employed because of its ability to endure mechanical stress due to thermal expansion, high resistance to flow-induced vibrations, and better thermal performance compared to a straight tube one. To produce the targeted steam, a design analysis of the once-through helical steam generator needs to be conducted. A quick evaluation method was used to predict the preliminary specifications required for steam production. Simple thermodynamic calculations combined with empirical heat transfer coefficients covering convective and boiling processes at constant pressure were used to carry out the analysis. Two scenarios were conducted to evaluate the design choice based on the previous design of RDE-10.

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Section: Introduction mentioning

confidence: 99%

Design Scenario and Analysis for Preliminary Specification of Steam Generator in the Peluit-40

Riyandwita¹,

Subhan²,

Setiadipura³

et al. 2023

Tri Dasa Mega

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“…The RDE is developed by BATAN to be a basic reference and milestone of Indonesia in a nuclear power technology presence in the future [1]. This paper reviews (or notices) state of the art application of RDE in the preliminary design of RDE program that was introduced to the Agency for National Development Planning in the past year of 2014 [2]. The cylindrical shell constitutes structural components of RPV for RDE.…”

Section: Introductionmentioning

confidence: 99%

Cylindrical Shell Analysis of Reactor Pressure Vessel for Rde

Sudadiyo

2021

gnd

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CYLINDRICAL SHELL ANALYSIS OF REACTOR PRESSURE VESSEL FOR RDE. This study deals with the analysis of cylindrical shell design for Reactor Pressure Vessel (RPV) of Reaktor Daya Eksperimental (RDE).The RDE is developed by BATAN as the preliminary of nuclear technology in Indonesia. RPV is a container for confining helium gas at pressure (3 MPa) and temperature (circa 250 C). In reactor operation, mechanical stresses act to the RPV as in consequence of internal pressure, external pressure, and different loads due to dead weight and helium content load. Therefore, if the RPV could not retain its material strength it will cause failure. The applications and validity of Fortran code (RPV_RDE.exe) for the design analysis are represented by two simulation cases, which show good calculation results of design outputs compared to analytical solutions by hand calculations. Design outputs have met the safety requirements (on ultimate tensile strength 485 MPa) for the minimum wall thickness of cylindrical shell in upper portion of 60 mm with Hoop stress 104.47 MPa and in lower portion of 100 mm with Hoop stress 62.81 MPa, respectively.

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“…Since then, various studies have been further intensified, not only limited to the site selection but also for the NPP technology. The most recent study was the consideration of using the high temperature gas cooled reactor (HTGR) as a part of strategic milestone to introduce the largescale NPP in Indonesia [2]. All of those efforts were affected by the most recent nuclear accident in the Fukushima Daiichi NPP in 2011, which has changed the mindset of NPP technology industry worldwide related to nuclear safety.…”

Section: Introductionmentioning

confidence: 99%

Preliminary Assessment of Engineered Safety Features Against Station Blackout in Selected PWR Models

Ekariansyah

Widodo²,

Susyadi³

et al. 2021

Tri Dasa Mega

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The 2011 Fukushima accident did not prevent countries to construct new nuclear power plants (NPPs) as part of the electricity generation system. Based on the IAEA database, there are a total of 44 units of PWR type NPPs whose constructions are started after 2011. To assess the technology of engineered safety features (ESFs) of the newly constructed PWRs, a study has been conducted as described in this paper, especially in facing the station blackout (SBO) event. It is expected from this study that there are a number of PWR models that can be considered to be constructed in Indonesia from the year of 2020. The scope of the study is PWRs with a limited capacity from 900 to 1100 MWe constructed and operated after 2011 and small-modular type of reactors (SMRs) with the status of at least under licensing. Based on the ESFs design assessment, the passive core decay heat removal has been applied in the most PWR models, which is typically using steam condensing inside heat exchanger within a water tank or by air cooling. From the selected PWR models, the CPR-1000, HPR-1000, AP-1000, and VVER-1000, 1200, 1300 series have the capability to remove the core decay heat passively. The most innovative passive RHR of AP-1000 and the longest passive RHR time period using air cooling in several VVER models are preferred. From the selected SMR designs, the NuScale design and RITM-200 possess more advantages compared to the ACP-100, CAREM-25, and SMART. NuScale represents the model with full-power natural circulation and RITM-200 with forced circulation. NuScale has the longest time period for passive RHR as claimed by the vendor, however the design is still under licensing process. The RITM-200 reactor has a combination of passive air and water-cooling of the heat exchanger and is already under construction.

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The Strategy to Support HTGR fuels for The 10 MW Indonesia's Experimental Power Reactor (RDE)

Cited by 6 publications

References 19 publications

Design Scenario and Analysis for Preliminary Specification of Steam Generator in the Peluit-40

Design Scenario and Analysis for Preliminary Specification of Steam Generator in the Peluit-40

Cylindrical Shell Analysis of Reactor Pressure Vessel for Rde

Preliminary Assessment of Engineered Safety Features Against Station Blackout in Selected PWR Models

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