RAMONA-4B development for SBWR safety studies

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The Simplified Boiling Water Reactor (SBWR) is a revolutionary design of a boiling-water reactor. The reactor is based on passive safety systems such as natural circulation, gravity flow, pressurized gas, and condensation. SBWR has no active systems, and the flow in the vessel is by natural circulation. There is a large chimney section above the core to provide a buoyancy head for natural circulation. The reactor can be shut down by either of four systems; namely, scram, Fine Motion Control Rod Drive (FMCRD), Alternate Rod Insertion (ARI), and Standby Liquid Control System (SLCS). The safety injection is by gravity drain ... continued below

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26 p.

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Rohatgi, U. S.; Aronson, A. L.; Cheng, H. S.; Khan, H. J. & Mallen, A. N. December 31, 1993.

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Description

The Simplified Boiling Water Reactor (SBWR) is a revolutionary design of a boiling-water reactor. The reactor is based on passive safety systems such as natural circulation, gravity flow, pressurized gas, and condensation. SBWR has no active systems, and the flow in the vessel is by natural circulation. There is a large chimney section above the core to provide a buoyancy head for natural circulation. The reactor can be shut down by either of four systems; namely, scram, Fine Motion Control Rod Drive (FMCRD), Alternate Rod Insertion (ARI), and Standby Liquid Control System (SLCS). The safety injection is by gravity drain from the Gravity Driven Cooling System (GDCS) and Suppression Pool (SP). The heat sink is through two types of heat exchangers submerged in the tank of water. These heat exchangers are the Isolation Condenser (IC) and the Passive Containment Cooling System (PCCS). The RAMONA-4B code has been developed to simulate the normal operation, reactivity transients, and to address the instability issues for SBWR. The code has a three-dimensional neutron kinetics coupled to multiple parallel-channel thermal-hydraulics. The two-phase thermal hydraulics is based on a nonhomogeneous nonequilibrium drift-flux formulation. It employs an explicit integration to solve all state equations (except for neutron kinetics) in order to predict the instability without numerical damping. The objective of this project is to develop a Sun SPARC and IBM RISC 6000 based RAMONA-4B code for applications to SBWR safety analyses, in particular for stability and ATWS studies.

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26 p.

Notes

INIS; OSTI as DE94008999; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov

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  • 21. water reactor safety information meeting,Bethesda, MD (United States),25-27 Oct 1993

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  • Other: DE94008999
  • Report No.: BNL-NUREG--60148
  • Report No.: CONF-931079--23
  • Grant Number: AC02-76CH00016
  • Office of Scientific & Technical Information Report Number: 10136624
  • Archival Resource Key: ark:/67531/metadc1317273

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  • December 31, 1993

Added to The UNT Digital Library

  • Nov. 3, 2018, 11:47 a.m.

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  • March 5, 2019, 12:41 p.m.

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Rohatgi, U. S.; Aronson, A. L.; Cheng, H. S.; Khan, H. J. & Mallen, A. N. RAMONA-4B development for SBWR safety studies, article, December 31, 1993; Upton, New York. (https://digital.library.unt.edu/ark:/67531/metadc1317273/: accessed March 25, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.