Abstract
Crud-Induced Power Shift (CIPS) poses a significant challenge to the efficient operation of pressurized water reactors (PWRs). Traditional methods for calculating the CIPS Index, used to predict flux suppression due to crud buildup, rely on high-resolution data from movable in-core detectors. However, many reactors are equipped with fixed in-core detection systems, which provide limited axial measurements. This paper presents a novel approach for calculating the CIPS Index in fixed in-core systems, using high-fidelity simulations from the Virtual Environment for Reactor Applications (VERA). By leveraging MPACT for reactor physics, CTF for thermal-hydraulics, and MAMBA for crud chemistry, this method compensates for the reduced axial resolution of fixed detectors. The CIPS Index is computed by comparing measured neutron flux values with high-fidelity simulations, capturing localized flux suppression caused by crud, even with limited data points. Results demonstrate that the method achieves accurate CIPS Index predictions with less than 5% uncertainty, enabling early detection of crud-related power shifts with minimal conservatism. This methodology offers a valuable tool for reactor operators to mitigate CIPS risk and optimize core design, leading to cost savings and improved operational efficiency. The approach represents a step forward in applying high-fidelity simulations to fixed detector systems, ensuring that reactors can continue to operate safely and efficiently despite crud buildup.
| Original language | English |
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| Title of host publication | Proceedings of Advances in Nuclear Fuel Management, ANFM 2025 |
| Publisher | American Nuclear Society |
| Pages | 954-963 |
| Number of pages | 10 |
| ISBN (Electronic) | 9780894482267 |
| State | Published - 2025 |
| Externally published | Yes |
| Event | 2025 Advances in Nuclear Fuel Management, ANFM 2025 - Clearwater Beach, United States Duration: Jul 20 2025 → Jul 23 2025 |
Publication series
| Name | Proceedings of Advances in Nuclear Fuel Management, ANFM 2025 |
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Conference
| Conference | 2025 Advances in Nuclear Fuel Management, ANFM 2025 |
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| Country/Territory | United States |
| City | Clearwater Beach |
| Period | 07/20/25 → 07/23/25 |
Funding
This research was funded by the U.S. Department of Energy Small Business Innovative Research (SBIR) program, award number DE-FOA-0002903. This research leveraged existing VERA models and computational resources provided by the VERA Users Group which has been supported by a variety of commercial organizations over the years. This research utilized the high-performance computing resources at Idaho National Laboratory [8] which is supported by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517.
Keywords
- CIPS
- CIPS Index
- VERA