The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation

다국어 초록 (Multilingual Abstract)

The CRUD on the fuel cladding under the pressurized water reactor (PWR) operating condition causes several issues. The CRUD can act as thermal resistance and increases the local cladding temperature which accelerate the corrosion process. The hideout of boron inside the CRUD results in axial offset anomaly and reduces the plant's shutdown margin. Recently, there are efforts to revise the acceptance criteria of emergency core cooling systems (ECCS), and additionally require the modeling of the thermal resistance effect of the CRUD during the performance analysis. There is an urgent need for the evaluation of the effect of the CRUD deposition on the cladding heat transfer under PWR operating conditions, but the experimental database is very limited. The experimental facility called DISNY was designed and constructed to analyze the CRUD-related multi-physical phenomena, and the performance analysis of the constructed DISNY facility was conducted. The thermal-hydraulic and water chemistry conditions to simulate the CRUD growth under PWR operating conditions were established. The design characteristics and feasibility of the DISNY facility were validated by the MARS-KS code analysis and separate performance tests. In the current study, detailed design features, design validation results, and future utilization plans of the proposed DISNY facility are presented.

참고문헌 (Reference)

1 김지용 ; 이윤주 ; 함준혁 ; 김지현 ; 방인철, "파울링된 피복관 표면의 가압 경수로 운전환경에서의 미포화 비등 열전달 성능평가를 위한 실험장치 구축 연구" 한국유체기계학회 25 (25): 12-21, 2022

2 J. Lee, "Thermal resistance effects of crud and oxide layers to the safety analysis" 2018

3 G. Wang, "Thermal conductivity measurement for simulated PWR crud" 2013

4 N. Cinosi, "The effective thermal conductivity of crud and heat transfer from crud-coated PWR fuel" Elsevier BV 241 (241): 792-798, 2011

5 W. A. Byers, "Simulation of PWR crud" 2014

6 G. Wang, "Simulated Fuel Crud Thermal Conductivity Measurements under Pressurized Water Reactor Conditions"

7 Muhammad Awais, "Recent advancements in impedance of fouling resistance and particulate depositions in heat exchangers" Elsevier BV 141 : 580-603, 2019

8 J. Deshon, "Pressurized water reactor fuel crud and corrosion modeling" 63 : 64-72, 2011

9 J. Deshon, "PWR Axial Offset Anomaly (AOA) Guidelines, Revision 1" 2004

10 Bassam A. Khuwaileh, "On the performance of nanofluids in APR 1400 PLUS7 assembly: Neutronics" Elsevier BV 144 : 107508-, 2020

11 John H. Lienhard, "On the commonality of equations for natural convection from immersed bodies" Elsevier BV 16 (16): 2121-2123, 1973

12 Miaomiao Jin, "Multiphysics modeling of two-phase film boiling within porous corrosion deposits" Elsevier BV 316 : 504-518, 2016

13 M.P. Short, "Multiphysics modeling of porous CRUD deposits in nuclear reactors" Elsevier BV 443 (443): 579-587, 2013

14 Inam ul Haq, "Modelling heat transfer and dissolved species concentrations within PWR crud" Elsevier BV 241 (241): 155-162, 2011

15 D.Y. Yeo, "Modeling heat transfer through chimney-structured porous deposit formed in pressurized water reactors" Elsevier BV 108 : 868-879, 2017

16 D.Y. Yeo, "Modeling film boiling within chimney-structured porous media and heat pipes" Elsevier BV 124 : 576-585, 2018

17 Y. Lee, "Microstructure change of crud with various heat flux conditions" 2021

18 P. Saha, "Issues and future direction of thermal-hydraulics research and development in nuclear power reactors" Elsevier BV 264 : 3-23, 2013

19 I. Dumnernchanvanit, "Initial experimental evaluation of crud-resistant materials for light water reactors" Elsevier BV 498 : 1-8, 2018

20 G. Wang, "Improved CRUD Heat Transfer Model for Dryout on Fuel Pin Surfaces at PWR Operating Conditions" Pennsylvania State University 2009

21 P. Cohen, "Heat and mass transfer for boiling in porous deposits with chimenys" 70 : 71-80, 1972

22 F.W. Dittus, "Heat Transfer in Automobile Radiators of Tubular Type" 13-, 1930

23 T. L. Bergman, "Fundamentals of Heat and Mass Transfer" John Wiley & Sons 2011

24 Khnp, "Final Safety Analysis Report for Shin-Kori Unit 3, 4 (Chapter 4)" 2008

25 Khnp, "Final Safety Analysis Report for Hanbit Unit 5, 6 (Chapter 4)" 1997

26 H. W. Coleman, "Experimentation, Validation, and Uncertainty Analysis for Engineers" John Wiley & Sons 2018

27 Youngjae Park, "Experimental Study about the Effects of CRUD on Quenching Heat Transfer of Simulated Fuel Rod in Single Flow Channel under PWR Reflood Flow Conditions" Kyunghee University 2021

28 J. Deshon, "Evaluation of Fuel Cladding Corrosion and Corrosion Product Deposits from Callaway Cycle"

29 Ali Fguiri, "Estimation of fouling resistance in a phosphoric acid/steam heat exchanger using inverse method" Elsevier BV 192 : 116935-, 2021

30 Donghwi Lee, "Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials" Elsevier BV 185 : 116347-, 2021

31 Seung Heon Baek, "Effects of heat flux on fuel crud deposition and sub-cooled nucleate boiling in simulated PWR primary water at 13 MPa" Elsevier BV 133 : 178-185, 2019

32 Seung Heon Baek, "Effect of chemical etching of fuel cladding surface on crud deposition behavior in simulated primary water of PWRs at 328 °C" Elsevier BV 116 : 69-77, 2018

33 Junhyuk Ham, "Effect of TiN Coating on the Fouling Behavior of Crud on Pressurized Water Reactor Fuel Cladding" Elsevier BV 549 : 152870-, 2021

34 H. K. Forster, "Dynamics of vapor bubbles and boiling heat transfer" 1 : 531-535, 1955

35 J. -J. Jeong, "Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3. 1" 26 : 1611-1642, 1999

36 Ji Kim, "Design Study of CRUD Thermal Properties Characterization Facility DISNY Under Pressurized Water Reactor Normal Operating Condition" American Nuclear Society 563-574, 2022

37 J. B. Lee, "Description Report of ATLAS Facility and Instrumentation" 2020

38 Z. Karoutas, "Critical heat flux and crud WALT loop measurements for westinghouse accident tolerant fuel" 2019

39 J. C. Chen, "Correlation for boiling heat transfer to saturated fluids in convective flow" 5 : 322-329, 1966

40 C. Pan, "Concentration levels of solutes in porous deposits with chimneys under WICK boiling conditions" 99 : 317-327, 1987

41 Y. Lee, "Chemistry change of CRUD with various metal ion concentration conditions in PWR fuel cladding" Springer 2022

42 Jei-Won Yeon, "Chemical analysis of fuel crud obtained from Korean nuclear power plants" Elsevier BV 404 (404): 160-164, 2010

43 J. A. Sawicki, "Characterization of Corrosion Products on the Callaway Cycle 9PWR Core" 2001

44 C. Sauder, "Ceramic Matrix Composites: Materials, Modeling and Technology" 609-646, 2014

45 Jacopo Buongiorno, "Can corrosion and CRUD actually improve safety margins in LWRs?" Elsevier BV 63 : 9-21, 2014

46 R. Hu, "CONSIDERING THE THERMAL RESISTANCE OF CRUD IN LOCA ANALYSIS" 101 : 590-592, 2009

47 J.R.S. Thom, "Boiling in Subcooled Water during Flow up Heated Tubes or Annuli" 1965

48 서승진 ; 박병기 ; 김성중 ; 신호철 ; 이서정 ; 이민호 ; 최성열, "BOTANI: High-fidelity Multiphysics Model for Boron Chemistry in CRUD Deposits" 한국원자력학회 53 (53): 1676-1685, 2021

49 W. H. Jens, "Analysis of Heat Transfer, Burnout, Pressure Drop and Density Date for High-Pressure Water" Argonne National Lab 1951

50 R. v Macbeth, "An Investigation into the Effect of “CRUD” Deposits on Surface Temperature, Dry-Out and Pressure Drop, with Forced Convection Boiling of Water at 69 Bar in an Annular Test Section" UKAEA Reactor Group 1971

51 Jim Henshaw, "A model of chemistry and thermal hydraulics in PWR fuel crud deposits" Elsevier BV 353 (353): 1-11, 2006