Development of a MELCOR self-initialization algorithm for boiling water reactors
Creators
- 1. Inst. of Nuclear Energy Research, Taoyuan (Taiwan, Province of China)
Description
The MELCOR code, developed by Sandia National Laboratories, is suitable for calculating source terms and simulating severe accident phenomena of nuclear power plants. Prior to simulating a severe accident transient with MELCOR, the initial steady-state conditions must be generated in advance. The current MELCOR users' manuals do not provide a self-initialization procedure; this is the reason users have to adjust the initial conditions by themselves through a trial-and-error approach. A MELCOR self-initialization algorithm for boiling water reactor plants has been developed, which eliminates the tedious trial-and-error procedures and improves the simulation accuracy. This algorithm adjusts the important plant variable such as the dome pressure, downcomer level, and core flow rate to the desired conditions automatically. It is implemented through input with control functions provided in MELCOR. The reactor power and feedwater temperature are fed as input data. The initialization work of full-power conditions of the Kuosheng nuclear power station is cited as an example. These initial conditions are generated successfully with the developed algorithm. The generated initial conditions can be stored in a restart file and used for transient analysis. The methodology in this study improves the accuracy and consistency of transient calculations. Meanwhile, the algorithm provides all MELCOR users an easy and correct method for establishing the initial conditions
Additional details
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 113
- Journal Issue
- 1
- Journal Page Range
- p. 21-28.
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27045227
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; KUOSHENG-1 REACTOR; KUOSHENG-2 REACTOR; M CODES; MODIFICATIONS; REACTOR ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS