The determination of the thermal reactor power is traditionally done by establishing the heat balance: • for a boiling water reactor (BWR) at the interface of reactor control volume and heat cycle; • for a pressurized water reactor (PWR) at the interface of the steam generator control volume and turbine island on the secondary side. The uncertainty of these traditional methods is not easy to determine and it can be in the range of several percent. Technical and legal regulations (e.g. 10CFR50) cover an estimated instrumentation error of up to 2% by increasing the design thermal reactor power for emergency analysis to 102% of the licensed thermal reactor power. Basically, the licensee has the duty to warrant at any time operation inside the analysed region for thermal reactor power. This is normally done by keeping the indicated reactor power at the licensed 100% value. A better way is to use a method which allows a continuous warranty evaluation. The quantification of the level of fulfilment of this warranty is only achievable by a method which: • is independent of single measurements accuracies; • results in a certified quality of single process values and for the total heat cycle analysis; • leads to complete results including 2-sigma deviation especially for thermal reactor power. This method, which is called ‘process data reconciliation based on VDI 2048 guideline’, is presented here [1, 2]. The method allows to determine the true process parameters with a statistical probability of 95%, by considering closed material, mass- and energy balances following the Gaussian correction principle. The amount of redundant process information and complexity of the process improves the final results. This represents the most probable state of the process with minimized uncertainty according to VDI 2048. Hence, calibration and control of the thermal reactor power are possible with low effort but high accuracy and independent of single measurement accuracies. Furthermore, VDI 2048 describes the quality control of important process parameters. Applied to the thermal reactor power, the statistical certainty of warranting the allowable value can be quantified. This quantification allows keeping a safety margin in agreement with the authority. This paper presents the operational application of this method at an operating plant and describes the additional use of process data reconciliation for acceptance tests, power recapture and system and component diagnosis.
Skip Nav Destination
14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4242-8
PROCEEDINGS PAPER
Power Recapture and Power Uprate in NPPs With Process Data Reconciliation in Accordance With VDI 2048
Magnus Langenstein
Magnus Langenstein
BTB-Jansky GmbH, Leonberg, Germany
Search for other works by this author on:
Magnus Langenstein
BTB-Jansky GmbH, Leonberg, Germany
Paper No:
ICONE14-89025, pp. 7-14; 8 pages
Published Online:
September 17, 2008
Citation
Langenstein, M. "Power Recapture and Power Uprate in NPPs With Process Data Reconciliation in Accordance With VDI 2048." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management. Miami, Florida, USA. July 17–20, 2006. pp. 7-14. ASME. https://doi.org/10.1115/ICONE14-89025
Download citation file:
9
Views
0
Citations
Related Proceedings Papers
Related Articles
External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET
ASME J of Nuclear Rad Sci (April,2020)
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
An Experimental Study of Assessment of Weld Quality on Fatigue Reliability Analysis of a Nuclear Pressure Vessel
J. Pressure Vessel Technol (November,1993)
Related Chapters
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
LOCA Frequencies Estimated from Operating Experience (PSAM-0282)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)