A new core loading pattern scheme has been developed with the objective of significantly reducing both the maximum and cycle average RCS (Reactor Cooling System) soluble boron requirements for a typical PWR (Pressurized Water Reactor) plant with 18 month cycle. This strategy has several advantages including reduced operational costs due to boron addition and subsequent dilution, less challenging coolant chemistry adjustments and decreased tritium production over the cycles. The core design utilizes a typical Westinghouse 4-Loop core with assemblies containing both ZrB2 Integral Fuel burnable Absorber (IFBA) and high concentration Gadolinium (Gd) burnable absorbers (BAs) in the same assembly. This combination achieves the boron reduction objectives while still maintaining good power margins and good fuel cycle economics. This paper describes the major characteristics of these cycles and compares these to a reference cycle design typical of those used in current Westinghouse 4-Loop type plants.
Skip Nav Destination
16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4814-0
PROCEEDINGS PAPER
Low Boron Level Loading Pattern Available to Purchase
Cenk Gu¨ler,
Cenk Gu¨ler
Westinghouse Electric Company, Monroeville, PA
Search for other works by this author on:
Jeffery A. Brown
Jeffery A. Brown
Westinghouse Electric Company, Monroeville, PA
Search for other works by this author on:
Cenk Gu¨ler
Westinghouse Electric Company, Monroeville, PA
Jeffery A. Brown
Westinghouse Electric Company, Monroeville, PA
Paper No:
ICONE16-48473, pp. 171-175; 5 pages
Published Online:
June 24, 2009
Citation
Gu¨ler, C, & Brown, JA. "Low Boron Level Loading Pattern." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues. Orlando, Florida, USA. May 11–15, 2008. pp. 171-175. ASME. https://doi.org/10.1115/ICONE16-48473
Download citation file:
14
Views
Related Proceedings Papers
Related Articles
In Memoriam: Jan Kysela
ASME J of Nuclear Rad Sci (April,2016)
Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria
ASME J of Nuclear Rad Sci (April,2017)
Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2
ASME J of Nuclear Rad Sci (October,2022)
Related Chapters
Nuclear Fuel Cycle
Non-Proliferation Nuclear Forensics: Canadian Perspective
Development of New Process and Product Monitoring Technologies for the Manufacturing of High Value Alloy Steels for Use in Critical Applications
Bearing and Transmission Steels Technology
LOCA Frequencies Estimated from Operating Experience (PSAM-0282)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)