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Title: Hybrid analysis of the simplified boiling water reactor using RAMONA-4B and CASMO-3 computer codes

Abstract

An analysis of the simplified boiling water reactor (SBWR) is carried out using the reactor analysis computer program ROMONA-4B in an operational transient scenario, a turbine trip with failure of all the bypass valves. The SBWR model represents the vessel`s internal components, such as flow areas, diameters, and volumes. The one-quarter-core neutron parameters are calculated with the CASMO-3 transport theory lattice physics computer program. The three-dimensional representation of the reactor core uses some standard fuel design parameters, such as a wide central water rod, 8 x 8 lattice, gadolinium rods, etc. The thermal-hydraulic equations are solved with the RAMONA-4B computer program in a closed loop inside the reactor vessel and in 184 parallel channels (including bypass) in the core. Finally, the two-phase coolant and neutronic parameters are calculated in steady state and during the turbine trip transient. The results obtained compare favorably with the standard safety analysis report data.

Authors:
;  [1]
  1. Texas A and M Univ., College Station, TX (United States). Dept. of Nuclear Engineering
Publication Date:
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
687518
Resource Type:
Journal Article
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 127; Journal Issue: 3; Other Information: PBD: Sep 1999
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; REACTOR SAFETY; R CODES; C CODES; TRANSIENTS; REACTOR ACCIDENTS; COMPARATIVE EVALUATIONS; HEAT TRANSFER; HYDRAULICS; NEUTRON TRANSPORT

Citation Formats

Vivas, G.F.C., and Hassan, Y.A. Hybrid analysis of the simplified boiling water reactor using RAMONA-4B and CASMO-3 computer codes. United States: N. p., 1999. Web.
Vivas, G.F.C., & Hassan, Y.A. Hybrid analysis of the simplified boiling water reactor using RAMONA-4B and CASMO-3 computer codes. United States.
Vivas, G.F.C., and Hassan, Y.A. Wed . "Hybrid analysis of the simplified boiling water reactor using RAMONA-4B and CASMO-3 computer codes". United States.
@article{osti_687518,
title = {Hybrid analysis of the simplified boiling water reactor using RAMONA-4B and CASMO-3 computer codes},
author = {Vivas, G.F.C. and Hassan, Y.A.},
abstractNote = {An analysis of the simplified boiling water reactor (SBWR) is carried out using the reactor analysis computer program ROMONA-4B in an operational transient scenario, a turbine trip with failure of all the bypass valves. The SBWR model represents the vessel`s internal components, such as flow areas, diameters, and volumes. The one-quarter-core neutron parameters are calculated with the CASMO-3 transport theory lattice physics computer program. The three-dimensional representation of the reactor core uses some standard fuel design parameters, such as a wide central water rod, 8 x 8 lattice, gadolinium rods, etc. The thermal-hydraulic equations are solved with the RAMONA-4B computer program in a closed loop inside the reactor vessel and in 184 parallel channels (including bypass) in the core. Finally, the two-phase coolant and neutronic parameters are calculated in steady state and during the turbine trip transient. The results obtained compare favorably with the standard safety analysis report data.},
doi = {},
journal = {Nuclear Technology},
number = 3,
volume = 127,
place = {United States},
year = {1999},
month = {9}
}