Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes

  • Received : 2016.08.09
  • Accepted : 2016.08.17
  • Published : 2016.10.25
Download PDF
⟨ Previous Next ⟩

Abstract

The design of Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) has been developed and the validation and verification (V&V) activities to demonstrate the system performance and safety are in progress. In this paper, the current status of test activities is described briefly and significant results are discussed. The large-scale sodium thermal-hydraulic test program, Sodium Test Loop for Safety Simulation and Assessment-1 (STELLA-1), produced satisfactory results, which were used for the computer codes V&V, and the performance test results of the model pump in sodiumshowed good agreement with those in water. The second phase of the STELLA program with the integral effect tests facility, STELLA-2, is in the detailed design stage of the design process. The sodium thermal-hydraulic experiment loop for finned-tube sodium-to-air heat exchanger performance test, the intermediate heat exchanger test facility, and the test facility for the reactor flow distribution are underway. Flow characteristics test in subchannels of a wire-wrapped rod bundle has been carried out for safety analysis in the core and the dynamic characteristic test of upper internal structure has been performed for the seismic analysis model for the PGSFR. The performance tests for control rod assemblies (CRAs) have been conducted for control rod drive mechanism driving parts and drop tests of the CRA under scram condition were performed. Finally, three types of inspection sensors under development for the safe operation of the PGSFR were explained with significant results.

Keywords

References

  1. H.K. Koo, Status of the fast reactor technology development in Korea, in: 48th TWG-FR Meeting, Obninsk, Russia, May 25-29, 2015.
  2. J. Yoo, J. Chang, H. Joo, Overall reactor system description of prototype gen-IV sodium cooled fast reactor, in: Transactions of 2016 ANS Annual Meeting, New Orleans, USA, June 12-16, 2016.
  3. P. Dufour, Sodium fast reactor, in: 2015 GIF Symposium (Session II), Makuhari Messe, Japan, May 19-20, 2015.
  4. P. Chellapandi, Overviews of SFR safety in India, in: Second Joint GIF-IAEA/INPRO Consultancy Meeting on Safety Aspects of SFRs, IAEA, Vienna, Austria, November 30-December 1, 2011.
  5. H. Kamide, A. Ono, N. Kimura, J. Endoh, O. Watanabe, Sodium experiments on natural circulation decay heat removal and 3D simulation of plenum thermal hydraulics, in: International Conference on Fast Reactors and Related Fuel Cycles (FR13), Paris, France, March 4-7, 2013.
  6. J. Eoh, J. Hong, S. Eeom, J.-Y. Jeong, Computer codes V&V tests with a large-scale sodium thermal-hydraulic test facility (STELLA), in: Transactions of 2016 ANS Annual Meeting, New Orleans, June 12-16, 2016.
  7. J.W. Yoo, Verification and Validation Test Plan for a Prototype SFR, KAERI, Daejeon, Korea, 2015.
  8. J. Hong, S. Yeom, J.H. Eoh, T.H. Lee, J.Y. Jeong, Heat transfer performance test of PDHRS heat exchangers of PGSFR using STELLA-1 facility. (submitted to Nucl. Eng. Des., August 2016).
  9. C. Choi, T. Jeong, J. Hong, S. Yeom, J.M. Kim, J.Y. Jeong, Y. Lee, K. Ha, Validation of MARS-LMR code for heat transfer models in the DHRS of the PGSFR, in: The 16th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-16), Chicago, IL, USA, August 30-September 4, 2015.
  10. M. Ishii, S.T. Revankar, T. Leonardi, R. Dowlati, M.L. Bertodano, I. Babelli, W. Wang, H. Pokharna, V.H. Ransom, R. Viskanta, J.T. Han, The three level scaling approach with application to the Purdue University multi-dimensional integral test facility, Nucl. Eng. Des. 186 (1998) 177-211. https://doi.org/10.1016/S0029-5493(98)00222-2
  11. J.-W. Han, J. Eoh, Y. Lee, Y. Joo, J. Lee, J. Choi, J. Kim, B. Kim, T. Kim, H. Lee, B. Choi, H. Nam, J. Jeong, D. So, I. Hwang, Design Report of Mechanical Sodium Pump for STELLA-1, Rep. No. KAERI/TR-4513/2011, KAERI, Daejeon, Korea, 2011.
  12. C. Cho, J. Kim, Y. Ko, B. Kim, Y. Cho, M. Jung, D. Gam, Y. Lee, J. Jeong, J. Kim, Performance tests of a mechanical pump in sodium environment, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 12-13, 2016.
  13. C. Cho, J. Kim, Y. Ko, B. Ko, S. Park, Y. Lee, J. Jeong, J. Kim, The performance tests of mechanical sodium pump with water environment, in: Transactions of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea, October 29-30, 2015.
  14. J. Kim, H. Kim, K. Park, H. Kim, J. Jeong, D. Kim, M. Cho, W. Huh, Sanjar, S. Jeon, D. Kim, K. Han, H. Chang, J. Kim, J. Park, Construction of Hydraulic Performance Test Facility for PHTS Pump of Sodium-Cooled Fast Reactor Final Report, Rep. No. KAERI CM-2275/2015, KAERI, Daejeon, Korea, 2016.
  15. H. Kim, B. Kim, Y. Ko, Y. Cho, J. Kim, S. Son, Y. Jo, B. Kang, M. Jung, J. Eoh, H. Lee, J. Jeong, Design evaluation of thermal-hydraulic test facility for a finned-tube sodium-to-air heat exchanger, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 12-13, 2015.
  16. J.-H. Eoh, J. Han, Y. Yoo, S. Kim, Thermal sizing of a forced draft sodium-to air heat exchanger and its operation strategy in KALIMER, in: Transactions of the Korean Nuclear Society Autumn Meeting, Pyungchang, Korea, October 30-31, 2008.
  17. D. Euh, PGSFR design review: thermal-fluid validation tests, in: PGSFR Design Review Meeting, Daejeon, Korea, January 11-13, 2016.
  18. H. Kim, H. Bae, S. Chang, S. Choi, D. Lee, Y. Ko, H. Choi, D. Euh, H. Lee, Measurement of flow distribution at subchannels in a wire-wrapped 37-rod bundle for a sodium cooled fast reactor, in: Transactions of the Korean Nuclear Society Autumn Meeting, Pyeongchang, Korea, October 30-31, 2014.
  19. S.-K. Chang, D.-J. Euh, H.S. Choi, H. Kim, S.R. Choi, H.-Y. Lee, Flow distribution and pressure loss in subchannels of a wire-wrapped 37-pin rod bundle for a sodium-cooled fast reactor, Nucl. Eng. Technol. 48 (2016) 376-385. https://doi.org/10.1016/j.net.2015.12.013
  20. S.-K. Chang, D. Euh, S. Kim, H. Choi, H. Kim, Y. Ko, S. Choi, H. Lee, Measurements of flow rates and pressure drop in subchannels of an SFR type 61-pin rod bundle, in: Specialist Workshop on Advanced Instrumentation and Measurement Technology for Nuclear Reactor Thermal Hydraulics (SWINTH-2016), Livomo, Italy, June 15-17, 2016.
  21. C.-G. Park, Y. Lee, H. Kim, J. Kim, Dynamic characteristic tests for a submerged cantilevered cylindrical structure, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 29-30, 2014.
  22. C.-G. Park, Y. Lee, H. Kim, J. Kim, Dynamic characteristic tests for a cylindrical structure with flow holes submerged in water, in: Transactions of the Korean Nuclear Society Autumn Meeting, Pyeongchang, Korea, October 30-31, 2014.
  23. J.-H. Lee, G.-H. Koo, Design improvement study for passive shutdown system of the SFR, in: Transactions of the Korean Nuclear Society Autumn Meeting, Pyeongchang, Korea, October 30-31, 2014.
  24. J.-H. Lee, G.-H. Koo, Electromagnet response time tests on primary CRDM of a prototype Gen-IV reactor, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 12-13, 2015.
  25. J.-H. Lee, S.-K. Kim, Performance tests on the electromagnet of secondary CRA gripper system of the PGSFR, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 12-13, 2016.
  26. Y.-K. Lee, J. Lee, H. Kim, S. Choi, S. Park, G. Koo, S. Kim, J. Kim, Drop Performance Test of Control Rod Assembly (CRA) of Sodium-cooled Fat Reactor, Rep. No. KAERI TR-6417/2016, KAERI, Daejeon, Korea, 2016.
  27. Y.S. Joo, C.-G. Park, J.-H. Lee, J.-B. Kim, S.-H. Lim, Development of ultrasonic waveguide sensor for under-sodium inspection in a sodium-cooled fast reactor, NDT E Int. 44 (2011) 239-246. https://doi.org/10.1016/j.ndteint.2010.10.008
  28. H.W. Kim, Y.-S. Joo, C.-G. Park, J.-B. Kim, J.-H. Bae, Ultrasonic imaging in hot liquid sodium using a plate-type ultrasonic waveguide sensor, J. Nondestruct. Eval. 33 (2014) 676-683. https://doi.org/10.1007/s10921-014-0262-8
  29. H.W. Kim, S. Park, Y. Lee, Y. Joo, S. Kim, Development and performance test of the combined inspection system for inservice inspection of PGSFR steam generator tubes, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 12-13, 2016.

Cited by

  1. Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor vol.49, pp.4, 2016, https://doi.org/10.1016/j.net.2016.12.004
  2. Ultrasonic ranging technique for obstacle monitoring above reactor core in prototype generation IV sodium-cooled fast reactor vol.52, pp.4, 2020, https://doi.org/10.1016/j.net.2019.09.013
  3. Scaling Methodology for Integral Effects Tests in Support of Fluoride Salt-Cooled High-Temperature Reactor Technology vol.194, pp.8, 2016, https://doi.org/10.1080/00295639.2019.1710976