Experimental investigation of symmetric and asymmetric heating of pressure tube under accident conditions for Indian PHWR
- 1. Department of Mechanical and Industrial Engineering, Indian Institute of Technology, Roorkee-247667 (India)
- 2. Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai-400085 (India)
Description
Highlights: ► Circumferential temperature gradient for asymmetric heat-up was 400 °C. ► At same pressure ballooning initiates at lower temperature in asymmetrical heat-up. ► At 1 MPa ballooning initiated at 408 °C and with expansion rate of 0.005 mm/s. ► At 2 MPa ballooning initiation at 330 °C and with expansion rate of 0.0056 mm/s. ► For symmetrical heat-up strain rate was 10 times faster than asymmetric heat-up. - Abstract: In pressurized heavy water reactor (PHWR), under postulated scenario of small break Loss of Coolant Accident (LOCA) coincident with the failure of Emergency Core Cooling System (ECCS), a situation may arise under which reduction in mass flow rate of coolant through individual reactor channel can lead to stratified flow. Such stratified flow condition creates partial uncover of fuel bundle, which creates a circumferential temperature gradient over PT. The present investigation has been carried out to study thermo-mechanical behaviour of PT under asymmetric heating conditions for a 220 MWe PHWR. A 19-pin fuel simulator has been developed in which preferential heating of elements could be done by supplying power to the selected pins. The asymmetric heating of PT has been carried out at pressure 2 MPa and 1 MPa, respectively, by supplying power to upper region heating elements thus creating an half filled stratified flow conditions. The temperature difference up to 425 °C has been observed along top to bottom periphery of PT. A comparison is made between thermo-mechanical behaviour of PT under asymmetrical and symmetrical heat-up, expected from a large break LOCA condition. The radial expansion rate during symmetrical heating is found to be much faster as compared to that for asymmetric ballooning of PT at the same internal pressure. Integrity of PT is found to be maintained under both loading conditions. Heat sink around of test section, simulating moderator is found to be helpful in arresting the rise in temperature for both fuel pins and PT, thus establishing moderator as an effective heat sink under accident conditions.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2012.10.007Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2012.10.007;
- PII
- S0029-5493(12)00515-8;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 254
- Journal Page Range
- p. 300-307
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44025390
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- ASYMMETRY; BALLOONING INSTABILITY; COOLANTS; ECCS; EXPANSION; FLOW RATE; FUEL ELEMENT CLUSTERS; FUEL PINS; HEAT SINKS; HEATING; LOSS OF COOLANT; MASS TRANSFER; MODERATORS; PHWR TYPE REACTORS; PRESSURE RANGE MEGA PA; PRESSURE TUBES; STRAIN RATE; TEMPERATURE GRADIENTS
- Descriptors DEC
- ACCIDENTS; ENGINEERED SAFETY SYSTEMS; FUEL ASSEMBLIES; FUEL ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INSTABILITY; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; PRESSURE RANGE; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SINKS; TUBES
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.