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Title: Rod bundle blowdown heat transfer tests simulating pressurized water reactor loss of coolant accident conditions. Final report

Abstract

An experimental program has been conducted to investigate transient critical heat flux (CHF) in pressurized water reactor (PWR) cores during a hypothetical loss-of-coolant accident (LOCA). Twenty-seven (27) powered blowdown transients were performed in the test program. Loop and test section parameters were selected to simulate predicted average reactor core blowdown thermal-hydraulic conditions. All experiments were performed with a 25 (5 x 5 square array) rod bundle test section having a uniform axial heat flux profile. The rod bundle had an active heated length of 12.5 feet. The test results are discussed, including the experimentally determined times and locations of CHF.

Authors:
; ;
Publication Date:
Research Org.:
Combustion Engineering, Inc., Windsor, Conn. (USA)
OSTI Identifier:
7292783
Report Number(s):
EPRI-NP-113
TRN: 78-000226
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LOSS OF COOLANT; HEAT TRANSFER; HYDRAULICS; PWR TYPE REACTORS; REACTOR SAFETY; CRITICAL HEAT FLUX; ECCS; FLOW RATE; FUEL ASSEMBLIES; FUEL RODS; MOCKUP; PERFORMANCE TESTING; PRESSURE GRADIENTS; TEST FACILITIES; ACCIDENTS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FUEL ELEMENTS; HEAT FLUX; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; STRUCTURAL MODELS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Hsia, A.H., Hubbard, F.R., and Schneider, R.E. Rod bundle blowdown heat transfer tests simulating pressurized water reactor loss of coolant accident conditions. Final report. United States: N. p., 1977. Web.
Hsia, A.H., Hubbard, F.R., & Schneider, R.E. Rod bundle blowdown heat transfer tests simulating pressurized water reactor loss of coolant accident conditions. Final report. United States.
Hsia, A.H., Hubbard, F.R., and Schneider, R.E. Mon . "Rod bundle blowdown heat transfer tests simulating pressurized water reactor loss of coolant accident conditions. Final report". United States.
@article{osti_7292783,
title = {Rod bundle blowdown heat transfer tests simulating pressurized water reactor loss of coolant accident conditions. Final report},
author = {Hsia, A.H. and Hubbard, F.R. and Schneider, R.E.},
abstractNote = {An experimental program has been conducted to investigate transient critical heat flux (CHF) in pressurized water reactor (PWR) cores during a hypothetical loss-of-coolant accident (LOCA). Twenty-seven (27) powered blowdown transients were performed in the test program. Loop and test section parameters were selected to simulate predicted average reactor core blowdown thermal-hydraulic conditions. All experiments were performed with a 25 (5 x 5 square array) rod bundle test section having a uniform axial heat flux profile. The rod bundle had an active heated length of 12.5 feet. The test results are discussed, including the experimentally determined times and locations of CHF.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1977},
month = {8}
}

Technical Report:
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