Multireference nodal GPT approach to rodded constraints in reload optimization

Journal Article · Sat Dec 31 04:00:00 EST 1994 · Transactions of the American Nuclear Society

OSTI ID:89133

Maldonado, G I; Engrand, P R; Beguinet, C

During a reload cycle design, a number of constraints must be considered to ensure that the resulting loading pattern satisfies all operational and safety limits. A pressurized water reactor (PWR) in-core nuclear fuel management optimization tool, such as the FORMOSA-P code, must therefore impose these constraints. Examples of typical constraints that must be satisfied by loading pattern candidates in a FORMOSA-P optimization include limits on power peaking, moderator temperature coefficient, region or local discharge burnup, and cycle length. Equally important, and recently implemented into a prototype version of FORMOSA-P at Electricite de France (EdF-Clamart), is the capability of imposing {open_quotes}rodded constraints.{close_quotes} In essence, along with all other requirements, a given loading pattern candidate must satisfy specific design criteria under the influence of selected control rod configurations. In France, where the load-follow operational mode of PWR plants is prevalent (due to France`s dominant fraction of nuclear-power-generated electricity), a core reload must typically satisfy power peaking design limits under seven different rod configurations, in addition to the all-rods-out (ARO) condition. This study describes the evaluation approach taken to address rodded constraints.

• OSTI ID: 89133
• Report Number(s): CONF-941102--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 71; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
66 PHYSICS
CONFIGURATION
CONSTRAINTS
CONTROL ELEMENTS
FUEL MANAGEMENT
NODAL EXPANSION METHOD
REACTOR FUELING
WATER COOLED REACTORS