CIPS Index Predictions for Fixed Incore Detection Systems

Benjamin S. Collins, Cole Gentry, Andrew Godfrey, David Kropaczek

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

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 languageEnglish
Title of host publicationProceedings of Advances in Nuclear Fuel Management, ANFM 2025
PublisherAmerican Nuclear Society
Pages954-963
Number of pages10
ISBN (Electronic)9780894482267
StatePublished - 2025
Externally publishedYes
Event2025 Advances in Nuclear Fuel Management, ANFM 2025 - Clearwater Beach, United States
Duration: Jul 20 2025Jul 23 2025

Publication series

NameProceedings of Advances in Nuclear Fuel Management, ANFM 2025

Conference

Conference2025 Advances in Nuclear Fuel Management, ANFM 2025
Country/TerritoryUnited States
CityClearwater Beach
Period07/20/2507/23/25

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

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