Analysis of loss of normal feedwater transient using RELAP5/MOD1/NSC; KNU1 plant simulation
- 1. Korea Advanced Energy Research Inst., Daeduk (Republic of Korea)
Description
Simulation of the system thermal-hydraulic parameters was carried out following the KNU1(Korea Nuclear Unit-1) loss of normal feedwater transient sequence occurred on november 14, 1984. Results were compared with the plant transient data, and good agreements were obtained. Some deviations were found in the parameters such as the steam flowrate and the RCS(Reactor Coolant System) average temperature, around the time of reactor trip. It can be expected since the thermal-hydraulic parameters encounter rapid transitions due to the large reduction of the reactor thermal power in a short period of time and, thereby, the plant data involve transient uncertainties. The analysis was performed using the RELAP5/MOD1/NSC developed through some modifications of the interphase drag and the wall heat transfer modeling routines of the RELAP5/MOD1/CY018. (Author)
Additional details
Publishing Information
- Journal Title
- J. Korean Nucl. Soc.
- Journal Volume
- 18
- Journal Issue
- 1
- Series
- J. Korean Nucl. Soc.
- Journal Page Range
- 9-16
- ISSN
- 0372-7327
- CODEN
- WJHKA
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 18031681
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- COMPUTER CODES; FEEDWATER; KORI-1 REACTOR; LOSS OF FLOW; REACTOR COOLING SYSTEMS; SIMULATION
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SOLVENTS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS