Abstract
The load-following operation of small modular reactors (SMRs) requires accurate prediction of transient behaviors that can occur in the balance of plants (BOP) and the nuclear steam supply system (NSSS). However, 1-D thermal-hydraulics analysis codes developed for safety and performance analysis have conventionally excluded the BOP from the simulation by assuming ideal boundary conditions for the main steam and feed water (MS/FW) systems, i.e., an open loop. In this study, we introduced a lumped model of BOP fluid system and coupled it with NSSS without any ideal boundary conditions, i.e., in a closed loop. Various methods for coupling boundary conditions at MS/FW were tested to validate their combination in terms of minimizing numerical instability, which mainly arises from the coupled boundaries. The method exhibiting the best performance was selected and applied to a transient simulation of an integrated NSSS and BOP system of a SMART. For a transient event with core power change of 100–20-100%, the simulation exhibited numerical stability throughout the system without any significant perturbation of thermal-hydraulic parameters. Thus, the introduced boundary-condition coupling method and BOP fluid system model can expectedly be employed for the transient simulation and performance analysis of SMRs requiring daily load-following operations.
| Original language | English |
|---|---|
| Pages (from-to) | 1974-1987 |
| Number of pages | 14 |
| Journal | Nuclear Engineering and Technology |
| Volume | 55 |
| Issue number | 6 |
| Early online date | Jun 2023 |
| DOIs | |
| State | Published - Jun 2023 |
| Externally published | Yes |
Keywords
- Balance of plant (BOP)
- Boundary condition coupling
- Dynamic simulation
- Small modular reactor (SMR)
- TASS/SMR-S code
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