Exercising the AETNA02 natural circulation loop model for ESBWR

Atul A. Karve, Jose A. Lamas, Andrew T. Godfrey, Brian R. Moore

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

1 Scopus citations

Abstract

The ESBWR initial core design submitted to the U.S. Nuclear Regulatory Commission (NRC) as part of the Design Control Document is studied with GNF's advanced lattice-physics core-simulator system LANCR02 / AETNA02. Previous simulation results submitted to the NRC, use the NRC approved TGBLA06 / PANAC11 lattice-physics core-simulator system. The PANAC11 core simulator does not explicitly model the ESBWR natural circulation loop; instead, the core inlet flow is specified and maintained constant for the entire 100% rated power core burn. The advanced core simulator AETNA02 incorporates a steady-state lumped-parameter natural circulation loop model resolving loop effect explicitly, and is therefore suitable for ESBWR vessel / core simulations. In this study, the validity of the approach used in the PANAC11 simulations is confirmed by conducting simulations using AETNA02 (where the core inlet flow is calculated based on its natural circulation loop model). Two sets of simulations are performed with AETNA02, one with natural circulation loop model turned off and one with the loop model turned on. When the effect of the loop model is turned off, the simulation is consistent with PANAC11. For the simulation in which the loop model turned on, the core inlet flow changes very little through the core burn, in comparison to the flow specified in the PANAC11 simulations. Furthermore, the critical power ratio margin and the linear heat generation rate margin are essentially the same as the simulation with the loop model turned off. These results further substantiate the applicability of AETNA02's natural circulation loop model.

Original languageEnglish
Title of host publicationAmerican Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
Pages487-493
Number of pages7
StatePublished - 2009
Externally publishedYes
EventAmerican Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV - Hilton Head Island, SC, United States
Duration: Apr 12 2009Apr 15 2009

Publication series

NameAmerican Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
Volume1

Conference

ConferenceAmerican Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
Country/TerritoryUnited States
CityHilton Head Island, SC
Period04/12/0904/15/09

Keywords

  • Core design
  • ESBWR
  • Fuel cycle
  • Hot excess
  • Reactivity

Fingerprint

Dive into the research topics of 'Exercising the AETNA02 natural circulation loop model for ESBWR'. Together they form a unique fingerprint.

Cite this