Simulation of SBWR startup transient and stability Metadata

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Title

  • Main Title Simulation of SBWR startup transient and stability

Creator

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

Contributor

  • 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)

Publisher

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

Date

  • Creation: 1998-06-01

Language

  • English

Description

  • 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.

Subject

  • 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

Source

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

Collection

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

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article

Format

  • Text

Identifier

  • 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

Note

  • Display Note: INIS; OSTI as DE98005756