Simulation of SBWR startup transient and stability Metadata

Metadata describes a digital item, providing (if known) such information as creator, publisher, contents, size, relationship to other resources, and more. Metadata may also contain "preservation" components that help us to maintain the integrity of digital files over time.


  • Main Title Simulation of SBWR startup transient and stability


  • Author: Cheng, H.S.
    Creator Type: Personal
  • Author: Khan, H.J.
    Creator Type: Personal
  • Author: Rohatgi, U.S.
    Creator Type: Personal


  • Sponsor: United States. Office of the Assistant Secretary for Nuclear Energy.
    Contributor Type: Organization
    Contributor Info: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)


  • Name: Brookhaven National Laboratory
    Place of Publication: Upton, New York
    Additional Info: Brookhaven National Lab., Upton, NY (United States)


  • Creation: 1998-06-01


  • English


  • Content Description: The Simplified Boiling Water Reactor (SBWR) designed by General Electric is a natural circulation reactor with enhanced safety features for potential accidents. It has a strong coupling between power and flow in the reactor core, hence the neutronic coupling with thermal-hydraulics is specially important. The potential geysering instability during the early part of a SBWR startup at low flow, low power and low pressure is of particular concern. The RAMONA-4B computer code developed at Brookhaven National Laboratory (BNL) for the SBWR has been used to simulate a SBWR startup transient and evaluate its stability, using a simplified four-channel representation of the reactor core for the thermal-hydraulics. This transient was run for 20,000 sec (5.56 hrs) in order to cover the essential aspect of the SBWR startup. The simulation showed that the SBWR startup was a very challenging event to analyze as it required accurate modeling of the thermal-hydraulics at low pressures. This analysis did not show any geysering instability during the startup, following the startup procedure as proposed by GE.
  • Physical Description: 17 p.


  • Keyword: Reactor Start-Up
  • Keyword: Bwr Type Reactors
  • Keyword: Heat Transfer
  • Keyword: Computerized Simulation
  • Keyword: Hydraulics
  • Keyword: Natural Convection
  • Keyword: Transients
  • STI Subject Categories: 22 Nuclear Reactor Technology
  • STI Subject Categories: 21 Nuclear Power Reactors And Associated Plants


  • Conference: 1998 international joint power generation conference, Baltimore, MD (United States), Aug 1998


  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article


  • Text


  • Other: DE98005756
  • Report No.: BNL--65535
  • Report No.: CONF-980816--
  • Grant Number: AC02-98CH10886
  • Office of Scientific & Technical Information Report Number: 663182
  • Archival Resource Key: ark:/67531/metadc702243


  • Display Note: INIS; OSTI as DE98005756