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Title: Posttest analysis of MIST Test 3109AA using TRAC-PF1/MOD1

Abstract

This document discusses a posttest calculation and analysis of Multi-loop Integral System Test (MIST) 3109AA as the nominal test for the MIST program. It is a test of a small-break loss-of-coolant accident (SBLOCA) with a scaled 10-cm[sup 2] break in the B1 cold leg. The test exhibited the major post-SBLOCA phenomena, as expected, including depressurization to saturation, intermittent and interrupted loop flow, boiler-condenser mode cooling, refill, and postrefill cooldown. Full high-pressure injection and auxiliary feedwater were available, reactor coolant pumps were not available, and reactor-vessel vent valves and guard heaters were automatically controlled. Constant level control in the steam-generator secondaries was used after steam-generator secondary refill and symmetric steam-generator pressure control was used. We performed the calculation using TRAC-PF1/MODI. Agreement between test data and the calculation was generally reasonable. All major trends and phenomena were correctly predicted. It is believed that the correct conclusions about trends and phenomena will be reached if the code is used in similar applications.

Authors:
; ;  [1]
  1. (Los Alamos National Lab., NM (United States))
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Los Alamos National Lab., NM (United States)
Sponsoring Org.:
NRC; Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
6926303
Alternate Identifier(s):
OSTI ID: 6926303; Legacy ID: TI93003212
Report Number(s):
NUREG/CR-5887; LA-UR--89-2158
ON: TI93003212
DOE Contract Number:  
W-7405-ENG-36
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HEAT TRANSFER; T CODES; HYDRAULICS; PWR TYPE REACTORS; LOSS OF COOLANT; COMPUTER CALCULATIONS; REACTOR SAFETY; TEST FACILITIES; TESTING; ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 990200 -- Mathematics & Computers; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Steiner, J.L., Siebe, D.A., and Boyack, B.E. Posttest analysis of MIST Test 3109AA using TRAC-PF1/MOD1. United States: N. p., 1992. Web.
Steiner, J.L., Siebe, D.A., & Boyack, B.E. Posttest analysis of MIST Test 3109AA using TRAC-PF1/MOD1. United States.
Steiner, J.L., Siebe, D.A., and Boyack, B.E. Tue . "Posttest analysis of MIST Test 3109AA using TRAC-PF1/MOD1". United States.
@article{osti_6926303,
title = {Posttest analysis of MIST Test 3109AA using TRAC-PF1/MOD1},
author = {Steiner, J.L. and Siebe, D.A. and Boyack, B.E.},
abstractNote = {This document discusses a posttest calculation and analysis of Multi-loop Integral System Test (MIST) 3109AA as the nominal test for the MIST program. It is a test of a small-break loss-of-coolant accident (SBLOCA) with a scaled 10-cm[sup 2] break in the B1 cold leg. The test exhibited the major post-SBLOCA phenomena, as expected, including depressurization to saturation, intermittent and interrupted loop flow, boiler-condenser mode cooling, refill, and postrefill cooldown. Full high-pressure injection and auxiliary feedwater were available, reactor coolant pumps were not available, and reactor-vessel vent valves and guard heaters were automatically controlled. Constant level control in the steam-generator secondaries was used after steam-generator secondary refill and symmetric steam-generator pressure control was used. We performed the calculation using TRAC-PF1/MODI. Agreement between test data and the calculation was generally reasonable. All major trends and phenomena were correctly predicted. It is believed that the correct conclusions about trends and phenomena will be reached if the code is used in similar applications.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Sep 01 00:00:00 EDT 1992},
month = {Tue Sep 01 00:00:00 EDT 1992}
}

Technical Report:
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