Implementation of thermal-hydraulic feedback in GRPDQ
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).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21076196
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNABLE POISONS; BURNUP; CALLAWAY-1 REACTOR; CALLAWAY-2 REACTOR; COMPUTERIZED SIMULATION; CROSS SECTIONS; DATA COVARIANCES; G CODES; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; MESH GENERATION; NEUTRON DIFFUSION EQUATION; POWER DISTRIBUTION; REACTOR CORES; REACTOR KINETICS; REACTOR OPERATION; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- COMPUTER CODES; DISTRIBUTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; KINETICS; MATERIALS; NEUTRON ABSORBERS; NUCLEAR POISONS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890604--.