Cite Article

The Analysis of Loss of Forced Flow Event on the HTGR Type Experimental Power Reactor

Choose citation format

BibTeX

@article{IJASEIT10817,
   author = {Andi S. Ekariansyah and Surip Widodo and - Sudarmono and - Susyadi and M. Darwis Isnaeni and R. Andika P. Dwijayanto},
   title = {The Analysis of Loss of Forced Flow Event on the HTGR Type Experimental Power Reactor},
   journal = {International Journal on Advanced Science, Engineering and Information Technology},
   volume = {10},
   number = {5},
   year = {2020},
   pages = {1986--1991},
   keywords = {experimental power reactor; loss of flow; RELAP5; accident simulation.},
   abstract = {Since 2014, Indonesia's National Atomic Energy Agency (BATAN) has been launching a plan to construct a 10 MWt Experimental Power Reactor (Reaktor Daya Eksperimental / RDE). The RDE design is based on the small-sized pebble-bed high-temperature gas-cooled reactor (HTGR) technology with TRISO fuels. By concept, HTR-10 design, which was developed by the INET of China, is used as the reference design. During the development process, a safety analysis report (SAR) of RDE design has to be prepared to be evaluated by the Indonesia Nuclear Regulatory Agency (BAPETEN). The report contains, among others the description of the RDE accident sequences, which can be only provided by simulations using a certain code. This paper emphasizes the transient analysis, which is simulated using RELAP5/SCDAP/Mod3.4 , which is a thermal-hydraulic code specified for light water coolant systems. The simulated event is the loss of primary coolant mass flow, which is caused by the failure of the primary gas blower motor. The methodology of simulation is first by modelling the RDE nuclear steam supply system to verify steady-state operational parameter of the RDE design. The second step is to simulate the event of loss of flow, which is followed by the failure to shut down the reactor. The simulation results in the decrease of the fuel pebble temperature during the event due to the negative fuel temperature reactivity coefficient and the core heat removal by the cavity cooling. Overall, the RELAP5 code has a limitation in the RDE simulation to define two different non-condensable gases, which reduces the accuracy of the simulation results.},
   issn = {2088-5334},
   publisher = {INSIGHT - Indonesian Society for Knowledge and Human Development},
   url = {http://ijaseit.insightsociety.org/index.php?option=com_content&view=article&id=9&Itemid=1&article_id=10817},
   doi = {10.18517/ijaseit.10.5.10817}
}

EndNote

%A Ekariansyah, Andi S.
%A Widodo, Surip
%A Sudarmono, -
%A Susyadi, -
%A Isnaeni, M. Darwis
%A Dwijayanto, R. Andika P.
%D 2020
%T The Analysis of Loss of Forced Flow Event on the HTGR Type Experimental Power Reactor
%B 2020
%9 experimental power reactor; loss of flow; RELAP5; accident simulation.
%! The Analysis of Loss of Forced Flow Event on the HTGR Type Experimental Power Reactor
%K experimental power reactor; loss of flow; RELAP5; accident simulation.
%X Since 2014, Indonesia's National Atomic Energy Agency (BATAN) has been launching a plan to construct a 10 MWt Experimental Power Reactor (Reaktor Daya Eksperimental / RDE). The RDE design is based on the small-sized pebble-bed high-temperature gas-cooled reactor (HTGR) technology with TRISO fuels. By concept, HTR-10 design, which was developed by the INET of China, is used as the reference design. During the development process, a safety analysis report (SAR) of RDE design has to be prepared to be evaluated by the Indonesia Nuclear Regulatory Agency (BAPETEN). The report contains, among others the description of the RDE accident sequences, which can be only provided by simulations using a certain code. This paper emphasizes the transient analysis, which is simulated using RELAP5/SCDAP/Mod3.4 , which is a thermal-hydraulic code specified for light water coolant systems. The simulated event is the loss of primary coolant mass flow, which is caused by the failure of the primary gas blower motor. The methodology of simulation is first by modelling the RDE nuclear steam supply system to verify steady-state operational parameter of the RDE design. The second step is to simulate the event of loss of flow, which is followed by the failure to shut down the reactor. The simulation results in the decrease of the fuel pebble temperature during the event due to the negative fuel temperature reactivity coefficient and the core heat removal by the cavity cooling. Overall, the RELAP5 code has a limitation in the RDE simulation to define two different non-condensable gases, which reduces the accuracy of the simulation results.
%U http://ijaseit.insightsociety.org/index.php?option=com_content&view=article&id=9&Itemid=1&article_id=10817
%R doi:10.18517/ijaseit.10.5.10817
%J International Journal on Advanced Science, Engineering and Information Technology
%V 10
%N 5
%@ 2088-5334

IEEE

Andi S. Ekariansyah,Surip Widodo,- Sudarmono,- Susyadi,M. Darwis Isnaeni and R. Andika P. Dwijayanto,"The Analysis of Loss of Forced Flow Event on the HTGR Type Experimental Power Reactor," International Journal on Advanced Science, Engineering and Information Technology, vol. 10, no. 5, pp. 1986-1991, 2020. [Online]. Available: http://dx.doi.org/10.18517/ijaseit.10.5.10817.

RefMan/ProCite (RIS)

TY  - JOUR
AU  - Ekariansyah, Andi S.
AU  - Widodo, Surip
AU  - Sudarmono, -
AU  - Susyadi, -
AU  - Isnaeni, M. Darwis
AU  - Dwijayanto, R. Andika P.
PY  - 2020
TI  - The Analysis of Loss of Forced Flow Event on the HTGR Type Experimental Power Reactor
JF  - International Journal on Advanced Science, Engineering and Information Technology; Vol. 10 (2020) No. 5
Y2  - 2020
SP  - 1986
EP  - 1991
SN  - 2088-5334
PB  - INSIGHT - Indonesian Society for Knowledge and Human Development
KW  - experimental power reactor; loss of flow; RELAP5; accident simulation.
N2  - Since 2014, Indonesia's National Atomic Energy Agency (BATAN) has been launching a plan to construct a 10 MWt Experimental Power Reactor (Reaktor Daya Eksperimental / RDE). The RDE design is based on the small-sized pebble-bed high-temperature gas-cooled reactor (HTGR) technology with TRISO fuels. By concept, HTR-10 design, which was developed by the INET of China, is used as the reference design. During the development process, a safety analysis report (SAR) of RDE design has to be prepared to be evaluated by the Indonesia Nuclear Regulatory Agency (BAPETEN). The report contains, among others the description of the RDE accident sequences, which can be only provided by simulations using a certain code. This paper emphasizes the transient analysis, which is simulated using RELAP5/SCDAP/Mod3.4 , which is a thermal-hydraulic code specified for light water coolant systems. The simulated event is the loss of primary coolant mass flow, which is caused by the failure of the primary gas blower motor. The methodology of simulation is first by modelling the RDE nuclear steam supply system to verify steady-state operational parameter of the RDE design. The second step is to simulate the event of loss of flow, which is followed by the failure to shut down the reactor. The simulation results in the decrease of the fuel pebble temperature during the event due to the negative fuel temperature reactivity coefficient and the core heat removal by the cavity cooling. Overall, the RELAP5 code has a limitation in the RDE simulation to define two different non-condensable gases, which reduces the accuracy of the simulation results.
UR  - http://ijaseit.insightsociety.org/index.php?option=com_content&view=article&id=9&Itemid=1&article_id=10817
DO  - 10.18517/ijaseit.10.5.10817

RefWorks

RT Journal Article
ID 10817
A1 Ekariansyah, Andi S.
A1 Widodo, Surip
A1 Sudarmono, -
A1 Susyadi, -
A1 Isnaeni, M. Darwis
A1 Dwijayanto, R. Andika P.
T1 The Analysis of Loss of Forced Flow Event on the HTGR Type Experimental Power Reactor
JF International Journal on Advanced Science, Engineering and Information Technology
VO 10
IS 5
YR 2020
SP 1986
OP 1991
SN 2088-5334
PB INSIGHT - Indonesian Society for Knowledge and Human Development
K1 experimental power reactor; loss of flow; RELAP5; accident simulation.
AB Since 2014, Indonesia's National Atomic Energy Agency (BATAN) has been launching a plan to construct a 10 MWt Experimental Power Reactor (Reaktor Daya Eksperimental / RDE). The RDE design is based on the small-sized pebble-bed high-temperature gas-cooled reactor (HTGR) technology with TRISO fuels. By concept, HTR-10 design, which was developed by the INET of China, is used as the reference design. During the development process, a safety analysis report (SAR) of RDE design has to be prepared to be evaluated by the Indonesia Nuclear Regulatory Agency (BAPETEN). The report contains, among others the description of the RDE accident sequences, which can be only provided by simulations using a certain code. This paper emphasizes the transient analysis, which is simulated using RELAP5/SCDAP/Mod3.4 , which is a thermal-hydraulic code specified for light water coolant systems. The simulated event is the loss of primary coolant mass flow, which is caused by the failure of the primary gas blower motor. The methodology of simulation is first by modelling the RDE nuclear steam supply system to verify steady-state operational parameter of the RDE design. The second step is to simulate the event of loss of flow, which is followed by the failure to shut down the reactor. The simulation results in the decrease of the fuel pebble temperature during the event due to the negative fuel temperature reactivity coefficient and the core heat removal by the cavity cooling. Overall, the RELAP5 code has a limitation in the RDE simulation to define two different non-condensable gases, which reduces the accuracy of the simulation results.
LK http://ijaseit.insightsociety.org/index.php?option=com_content&view=article&id=9&Itemid=1&article_id=10817
DO  - 10.18517/ijaseit.10.5.10817