Experimental investigation of natural circulation instability in a BWR-type small modular reactor
Creators
- 1. School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907 (United States)
- 2. Department of Mining and Nuclear Engineering, Missouri University of Science and Technology, 301 W 14th St., Rolla, MO 65409 (United States)
- 3. Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois, 104 South Wright St., Urbana, IL 61801 (United States)
- 4. Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)
- 5. Institute of Nuclear and New Energy Technology, Tsinghua University, Haidian District, Beijing 10084 (China)
- 6. Department of Mechanical Engineering, Virginia Tech, 460 Old Turner St., Randolph Hall, Blacksburg, VA 24061 (United States)
Description
Highlights: •Overview of typical flow instabilities occur during NCBWR startup. •Introduction of a new well scaled natural circulation test facility. •Evaluation of scaling distortions by RELAP5 analysis and characteristic tests. •Identification of flow instabilities during low pressure startup transients of NMR. •Testing of pressurized startup procedures to eliminate flow instability. -- Abstract: The Purdue NMR (Novel Modular Reactor) represents a BWR-type small modular reactor with a significantly reduced reactor pressure vessel (RPV). Specifically, the NMR is one third the height and area of a conventional BWR RPV with an electrical output of 50 MWe. Experiments are performed in a well-scaled test facility to investigate the thermal hydraulic flow instabilities during the startup transients for the NMR. The scaling analysis for the design of natural circulation test facility uses a three-level scaling methodology. Scaling criteria are derived from non-dimensional field and constitutive equations. Important thermal hydraulic parameters, e.g. system pressure, inlet coolant flow velocity and local void fraction, are analyzed for slow and fast normal startup transients. Flashing instability and density wave oscillation are the main flow instabilities observed when system pressure is below 0.5 MPa. And the flashing instability and density wave oscillation show different type of oscillations in void fraction profile. Finally, the pressurized startup procedure is recommended and tested in current research to effectively eliminate the flow instabilities during the NMR startup transients.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2015.06.014Additional details
Additional titles
- Augmented title (English)
- Flow instability;NMR;Natural circulation test facility;Startup tests;Pressurized startup procedures
Identifiers
- DOI
- 10.1016/j.pnucene.2015.06.014;
- PII
- S0149197015300202;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 85
- Journal Page Range
- p. 96-107
- ISSN
- 0149-1970
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51027565
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; FIELD EQUATIONS; FUEL STORAGE POOLS; INSTABILITY; NATURAL CONVECTION; OSCILLATIONS; PRESSURE VESSELS; REACTIVITY; SCALING; SPENT FUEL STORAGE; TEST FACILITIES; TESTING; THERMAL HYDRAULICS; TRANSIENTS; VOID FRACTION
- Descriptors DEC
- CONTAINERS; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUATIONS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; POWER REACTORS; REACTORS; STORAGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Copyright © 2015 Elsevier Ltd. All rights reserved.