Skip to main navigation Skip to search Skip to main content

Hot assembly and whole-core thermal-hydraulic analysis of a high power density marine core with neutronic/thermal-hydraulic coupling

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

In this study, 3D coupled neutronic/thermal-hydraulic (TH) methods are used for hot assembly (HA) and whole-core (WC) analysis of a high power density (HPD) 333 MWth PWR marine core. For HA analysis, the power distribution is found using the WIMS and PANTHER reactor physics codes and COBRA-EN performs the steady-state TH analysis. For WC analysis, PANTHER'S inbuilt TH capability is used, with WIMS supplying temperature-dependent cross-section data. To design HPD cores of between 90 and 250 MW/m3, five cases were chosen by optimizing the fuel pin diameter (D), pin pitch (P) and pitch-to-diameter ratio (P/D). Since steady-state calculations are used in the design process, an overpower condition, typically 18%, was applied in order to accommodate all anticipated transients. The analysis shows that, even in the hot channel at 18% overpower, the minimum departure from nucleate boiling ratio (MDNBR) and fuel temperature remain well within TH margins for all the candidate designs. In the COBRA-EN model, the coolant does not begin to boil unless the core-averaged linear power rating exceeds 27 kW/m for standard geometry, which is 155% higher than the design value. MDNBR, surface heat flux, maximum and average fuel, cladding surface and core outlet temperatures, pressure drop and power peaking factors were determined for steady-state operating conditions to determine whether TH safety limits were satisfied. The results show that it is possible to achieve a core power density of 120 MW/m, a ∼90% improvement on the reference design, while meeting the target core lifetime of 15 effective full-power-years and remaining within TH limits.

Original languageEnglish (US)
Title of host publicationPhysics of Reactors 2016, PHYSOR 2016
Subtitle of host publicationUnifying Theory and Experiments in the 21st Century
PublisherAmerican Nuclear Society
Pages3506-3518
Number of pages13
ISBN (Electronic)9781510825734
StatePublished - 2016
Externally publishedYes
EventPhysics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016 - Sun Valley, United States
Duration: May 1 2016May 5 2016

Publication series

NamePhysics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century
Volume5

Other

OtherPhysics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016
Country/TerritoryUnited States
CitySun Valley
Period5/1/165/5/16

Keywords

  • Civil marine propulsion
  • Coupled neutronic/thermal-hydraulic analysis
  • High power density core

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Nuclear and High Energy Physics

Fingerprint

Dive into the research topics of 'Hot assembly and whole-core thermal-hydraulic analysis of a high power density marine core with neutronic/thermal-hydraulic coupling'. Together they form a unique fingerprint.

Cite this