Abstract
The behavior of a VVER-440 nuclear power plant is simulated in postulated loss-of-feedwater accident with two-way coupled 1D-3D simulation. The pressurizer is simulated with Ansys Fluent 3D code, whereas the rest of the plant is modelled with Apros system code. The plant model includes all the main process components and their control automation devices. The coupling is made using Apros Co-simulation tool. The couplings of the 1D and 3D models include the spray line, control of pressurizer heaters, pressure relief line, surge line and water level measurement. The phase change models for the pressurizer have been implemented with user-defined functions of Fluent. In the beginning of the postulated loss-of-feedwater transient the feedwater pumps are assumed to trip during normal operation of the plant. This leads to pressure rise in the primary circuit, which triggers the pressurizer spray system. During the transient, the control rods start to move to decrease reactor power and later SCRAM occurs. Once the pressure has decreased back to normal levels, the spray valves are closed. As the pressure continues to decrease, the heater element groups at the bottom part of the pressurizer are turned on one-by-one to compensate the pressure drop. The results of the coupled simulation are compared with stand-alone Apros simulation to specify differences and possible benefits of coupled simulation compared to system code simulation only. With the simulation the operation of the Apros Co-simulation tool is also tested and demonstrated with relatively complex transient case with several couplings of different kind.
| Original language | English |
|---|---|
| Title of host publication | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 |
| Publisher | American Nuclear Society ANS |
| Pages | 5652-5666 |
| Number of pages | 15 |
| Edition | cd-rom |
| ISBN (Electronic) | 978-0-89448-767-5 |
| Publication status | Published - 1 Jan 2019 |
| MoE publication type | A4 Article in a conference publication |
| Event | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, United States Duration: 18 Aug 2019 → 23 Aug 2019 |
Conference
| Conference | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 |
|---|---|
| Abbreviated title | NURETH-18 |
| Country | United States |
| City | Portland |
| Period | 18/08/19 → 23/08/19 |
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Keywords
- CFD
- Co-simulation
- Coupled simulation
- Pressurizer
- VVER-440
Cite this
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Coupled APROS-CFD simulation of generic VVER-440 loss of feedwater transient. / Rämä, T.; Toppila, T.; Kättö, J.; Hovi, V.; Pättikangas, T.
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019. cd-rom. ed. American Nuclear Society ANS, 2019. p. 5652-5666.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
TY - GEN
T1 - Coupled APROS-CFD simulation of generic VVER-440 loss of feedwater transient
AU - Rämä, T.
AU - Toppila, T.
AU - Kättö, J.
AU - Hovi, V.
AU - Pättikangas, T.
PY - 2019/1/1
Y1 - 2019/1/1
N2 - The behavior of a VVER-440 nuclear power plant is simulated in postulated loss-of-feedwater accident with two-way coupled 1D-3D simulation. The pressurizer is simulated with Ansys Fluent 3D code, whereas the rest of the plant is modelled with Apros system code. The plant model includes all the main process components and their control automation devices. The coupling is made using Apros Co-simulation tool. The couplings of the 1D and 3D models include the spray line, control of pressurizer heaters, pressure relief line, surge line and water level measurement. The phase change models for the pressurizer have been implemented with user-defined functions of Fluent. In the beginning of the postulated loss-of-feedwater transient the feedwater pumps are assumed to trip during normal operation of the plant. This leads to pressure rise in the primary circuit, which triggers the pressurizer spray system. During the transient, the control rods start to move to decrease reactor power and later SCRAM occurs. Once the pressure has decreased back to normal levels, the spray valves are closed. As the pressure continues to decrease, the heater element groups at the bottom part of the pressurizer are turned on one-by-one to compensate the pressure drop. The results of the coupled simulation are compared with stand-alone Apros simulation to specify differences and possible benefits of coupled simulation compared to system code simulation only. With the simulation the operation of the Apros Co-simulation tool is also tested and demonstrated with relatively complex transient case with several couplings of different kind.
AB - The behavior of a VVER-440 nuclear power plant is simulated in postulated loss-of-feedwater accident with two-way coupled 1D-3D simulation. The pressurizer is simulated with Ansys Fluent 3D code, whereas the rest of the plant is modelled with Apros system code. The plant model includes all the main process components and their control automation devices. The coupling is made using Apros Co-simulation tool. The couplings of the 1D and 3D models include the spray line, control of pressurizer heaters, pressure relief line, surge line and water level measurement. The phase change models for the pressurizer have been implemented with user-defined functions of Fluent. In the beginning of the postulated loss-of-feedwater transient the feedwater pumps are assumed to trip during normal operation of the plant. This leads to pressure rise in the primary circuit, which triggers the pressurizer spray system. During the transient, the control rods start to move to decrease reactor power and later SCRAM occurs. Once the pressure has decreased back to normal levels, the spray valves are closed. As the pressure continues to decrease, the heater element groups at the bottom part of the pressurizer are turned on one-by-one to compensate the pressure drop. The results of the coupled simulation are compared with stand-alone Apros simulation to specify differences and possible benefits of coupled simulation compared to system code simulation only. With the simulation the operation of the Apros Co-simulation tool is also tested and demonstrated with relatively complex transient case with several couplings of different kind.
KW - CFD
KW - Co-simulation
KW - Coupled simulation
KW - Pressurizer
KW - VVER-440
UR - http://www.scopus.com/inward/record.url?scp=85073719836&partnerID=8YFLogxK
M3 - Conference article in proceedings
AN - SCOPUS:85073719836
SP - 5652
EP - 5666
BT - 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019
PB - American Nuclear Society ANS
ER -