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Title: Evaluation of the effects of initial conditions on transients in PUMA

Abstract

Major differences between the SBWR and the currently operating BWRs include the use of passive gravity-driven systems in the SBWR for emergency cooling of the vessel and containment. In order to investigate the phenomena expected during a Loss of Coolant Accident (LOCA), NRC has sponsored an integral scaled-test facility, called Purdue, University Multidimensional Integral Test Assembly (PUMA). The facility models all the major safety-related components of SBWR. Two PUMA initialization calculations were performed to assist the Purdue University in establishing test initialization procedures. Both calculations were based on the initial conditions obtained from SBWR LOCA simulation. In the base case, a complete separation between vapor and liquid was assumed, with all the water in the lower part of the Reactor Pressure Vessel (RPV) and all the vapor above it. In the sensitivity case, the water inventory was distributed in the vessel in the same way as in the SBWR at 1.034 MPa, which is the initial pressure for PUMA facility. Purdue University plans to initialize the PUMA tests as in the base case. The sensitivity calculation is performed to provide assurance that this mode of initialization is adequate. It also provides information on possible differences in the progress of transients.more » The conditions outside of the vessel were identical for both cases prior to initiation of the accident. The paper will discuss the differences in the early part of the transient. The conclusion from this study will also apply to many integral facilities which simulate the reactor transients from the middle of the transient.« less

Authors:
; ;  [1]
  1. Brookhaven National Lab., Upton, NY (United States). Dept. of Advanced Technology
Publication Date:
OSTI Identifier:
248189
Report Number(s):
CONF-960306-
ISBN 0-7918-1226-X; TRN: 96:014873
Resource Type:
Conference
Resource Relation:
Conference: ICONE 4: ASME/JSME international conference on nuclear engineering, New Orleans, LA (United States), 10-13 Mar 1996; Other Information: PBD: 1996; Related Information: Is Part Of ICONE-4: Proceedings. Volume 2: Advanced reactors; Rao, A.S. [ed.] [General Electric Nuclear Engineering, San Jose, CA (United States)]; Duffey, R.B. [ed.] [Brookhaven National Lab., Upton, NY (United States)]; Elias, D. [ed.] [Commonwealth Edison, Downers Grove, IL (United States)]; PB: 637 p.
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; LOSS OF COOLANT; ENGINEERED SAFETY SYSTEMS; TEST FACILITIES; CALIBRATION; PERFORMANCE TESTING; SENSITIVITY ANALYSIS; COMPUTERIZED SIMULATION; SCALE MODELS

Citation Formats

Parlatan, Y, Jo, J, and Rohatgi, U S. Evaluation of the effects of initial conditions on transients in PUMA. United States: N. p., 1996. Web.
Parlatan, Y, Jo, J, & Rohatgi, U S. Evaluation of the effects of initial conditions on transients in PUMA. United States.
Parlatan, Y, Jo, J, and Rohatgi, U S. 1996. "Evaluation of the effects of initial conditions on transients in PUMA". United States.
@article{osti_248189,
title = {Evaluation of the effects of initial conditions on transients in PUMA},
author = {Parlatan, Y and Jo, J and Rohatgi, U S},
abstractNote = {Major differences between the SBWR and the currently operating BWRs include the use of passive gravity-driven systems in the SBWR for emergency cooling of the vessel and containment. In order to investigate the phenomena expected during a Loss of Coolant Accident (LOCA), NRC has sponsored an integral scaled-test facility, called Purdue, University Multidimensional Integral Test Assembly (PUMA). The facility models all the major safety-related components of SBWR. Two PUMA initialization calculations were performed to assist the Purdue University in establishing test initialization procedures. Both calculations were based on the initial conditions obtained from SBWR LOCA simulation. In the base case, a complete separation between vapor and liquid was assumed, with all the water in the lower part of the Reactor Pressure Vessel (RPV) and all the vapor above it. In the sensitivity case, the water inventory was distributed in the vessel in the same way as in the SBWR at 1.034 MPa, which is the initial pressure for PUMA facility. Purdue University plans to initialize the PUMA tests as in the base case. The sensitivity calculation is performed to provide assurance that this mode of initialization is adequate. It also provides information on possible differences in the progress of transients. The conditions outside of the vessel were identical for both cases prior to initiation of the accident. The paper will discuss the differences in the early part of the transient. The conclusion from this study will also apply to many integral facilities which simulate the reactor transients from the middle of the transient.},
doi = {},
url = {https://www.osti.gov/biblio/248189}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jul 01 00:00:00 EDT 1996},
month = {Mon Jul 01 00:00:00 EDT 1996}
}

Conference:
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