Published 1989 | Version v1
Journal article

Implementation of thermal-hydraulic feedback in GRPDQ

  • 1. Union Electric, St. Louis, MO (USA)

Description

A common deficiency exhibited in many conventional PDQ reactor core models is the lack of thermal-hydraulic feedback (THF). Numerous reasons exist for not including THF in hot, full-power PDQ models, and most of these focus on the complexity of using the standard three-dimensional THF option in PDQ7V2, as well as its predecessors. The recently developed computer code GRPDQ greatly simplifies the incorporation of THF in PDQ models. GRPDQ, which is an enhanced version of PDQ7V2, simplifies the implementation of THF through a two-dimensional methodology that includes such features as multiple G factors, two-dimensional fuel temperature rise tables, and significantly reduced processing time, as well as numerous other enhancements. These features allow the user to take advantage of the benefits of modeling THF, while minimizing or eliminating such complexities as three-dimensional input representations and fuel and gap conductance input

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
59
Series
Trans. Am. Nucl. Soc.
Journal Page Range
319-320
ISSN
0003-018X
CODEN
TANSA

Conference

Title
Annual meeting of the American Nuclear Society.
Dates
4-8 Jun 1989.
Place
Atlanta, GA (USA).

Optional Information

Secondary number(s)
CONF-890604--.