Numerical investigations on power ramping procedure for a natural circulation boiling water reactor
Creators
- 1. Department of Mechanical Engineering, Indian Institute of Technology Guwahati, Guwahati 781039, Assam (India)
Description
Startup of a natural circulation boiling water reactor (NCBWR) is studied numerically, using a thermal-hydraulic system code RELAP5. A number of numerical experiments are carried out using various power ramps, and a suitable heat-up rate is identified to pressurize the reactor to the desired operating conditions in a reasonable time without considerable void generation in the core. It is observed that the occurrence of flashing in the riser section is unavoidable. Although flashing helps in steam production, the amplitude of flow oscillations induced by flashing is the event of concern, as in the case of the pressure tube type NCBWR studied here. Therefore, the feasibility of a complete single-phase startup is also examined and found not attractive. A new startup procedure, which completely bypasses the unstable two-phase region, is conceptualized, and the method to take the system to the operating condition without encountering flow oscillations is numerically investigated.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2009.12.011Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2009.12.011;
- PII
- S0029-5493(09)00652-9;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 240
- Journal Issue
- 4
- Journal Page Range
- p. 860-867
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41079757
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- BWR TYPE REACTORS; FLASHING; FLOW RATE; HEAT RATE; NATURAL CONVECTION; OSCILLATIONS; PRESSURE TUBES; R CODES; REACTOR CORES; STEAM; THERMAL HYDRAULICS; VOIDS
- Descriptors DEC
- COMPUTER CODES; CONVECTION; EFFICIENCY; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVAPORATION; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.