ML20204A764
| ML20204A764 | |
| Person / Time | |
|---|---|
| Issue date: | 07/22/2020 |
| From: | Bavol B NRC/NRR/DNRL/NRLB |
| To: | Advisory Committee on Reactor Safeguards |
| Bavol B | |
| References | |
| Download: ML20204A764 (17) | |
Text
Back-up Slides RES Slides for ACRS Meeting 7/21-22/2020
SET / IET Overview
- Hibiki and Ishii
- Boesmans and Berghmans
- LINX
- CCTF
- SCTF
- PKL
Literature Review
- Hibiki and Ishii summarized findings over many experimental campaigns that internal recirculation occurs near pool boiling conditions in large pipe geometries and bundle geometries
- A key process that affects the 3D flow field is channeling of voids into a central column
- At LINX facility, voiding in adiabatic conditions drove internal recirculation
- At CCTF, radial power differences enhanced internal recirculation
- At PKL facility, internal recirculation homogenized the axial and radial boron distribution
Hibiki-Ishii Review Boesmans and Berghmans LINX CCTF CCTF SCTF SCTF Primrkreislauf Primary Circuit Reactor Coolant System (PKL)
Information Follows
PKL PKL SET/IET References
- Hibiki, T. and Ishii, M., One-dimensional Drift Flux model for Two-phase Flow in a Large Diameter Pipe, Intl. Journal of Heat and Mass Transfer 46 (2003) pp.1773-1790.
- Staedke, H., Franchello, G., Worth, B., Graf, U., Romsedt, P., Kumbaro, A., et al.,
Advanced Three-dimensional Two-phase Flow Simulation Tools for Application to Reactor Safety (ASTAR), Nucl. Engr. And Design, 235 (2005) pp. 379-400.
- Bosemans, B and Berghmans, J., Level swell in pool boiling with liquid circulation, Intl. Journal of Heat and Mass Transfer 38 (1995) pp.989-998.
- NUREG/IA-0127, Reactor Safety Issues Resolved by the 2D/3D Program, July 1993 (ADAMS Accession No. ML062560279)
- "Analysis Report on SCTF Core-I and II Reflood Test," prepared by Japan Atomic Energy Research Institute, JAERI-Memo-01-348.
- TRACE V5.0 Assessment Manual Appendix C: Integral Effects Tests
- PKL III G5.1 Test Report PTCTP-G/2011/en/0004 Rev. B, Investigation on Boron Precipitation following a Large Break LOCA, March 2011 (ADAMS Accession No. ML14099A208).
Monitoring Subcritical Margin
- Similar to startup procedures, ex-core nuclear instrumentation can be used to monitor subcritical margin.
- Subcritical multiplication monitoring is used with 1/M plots typically to predict critical rod position.
1/M Plot (from DOE Fundamentals Handbook)
Timing of Downcomer Dilution Approximate Time of ECCS DC Reactor Time to reach Time to reach Steaming Rate Actuation Concentration Power 100 ppm 10 ppm post-ECCS seconds ppm %RTP kg/sec days days 1700 1000 1.0 0.74 0.96 10.3 2800 900 1.0 0.74 0.86 9.3 3300 800 1.0 0.74 0.77 8.3 1700 1000 0.5 0.37 1.89 20.6 2800 900 0.5 0.37 1.70 18.5 3300 800 0.5 0.37 1.49 16.5 1700 1000 0.2 0.15 4.70 51.5 2800 900 0.2 0.15 4.19 46.3 3300 800 0.2 0.15 3.68 41.1