Comparison of the effects of irradiation on iso-molded, fine grain nuclear graphites: ETU-10, IG-110 and NBG-25
1
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
Selecting graphite grades with superior irradiation characteristics is important task for designers of graphite moderation reactors. To provide reference information and data for graphite selection, the effects of irradiation on three fine-grained, iso-molded nuclear grade graphites, ETU-10, IG-110, and NBG25, were compared based on irradiation-induced changes in volume, thermal conductivity, dynamic Young's modulus, and coefficient of thermal expansion. Data employed in this study were obtained from reported irradiation test results in the high flux isotope reactor (HFIR)(ORNL) (ETU-10, IG-110) and high flux reactor (HFR)(NRL) (IG-110, NBG-25). Comparisons were made based on the irradiation dose and irradiation temperature. Overall, the three grades showed similar irradiation-induced property change behaviors, which followed the historic data. More or less grade-sensitive behaviors were observed for the changes in volume and thermal conductivity, and, in contrast, grade-insensitive behaviors were observed for dynamic Young's modulus and coefficient of thermal expansion changes. The ETU-10 of the smallest grain size appeared to show a relatively smaller VC to IG-110 and NBG-25. Drastic decrease in the difference in thermal conductivity was observed for ETU-10 and IG-110 after irradiation. The similar irradiation-induced properties changing behaviors observed in this study especially in the DYM and CTE may be attributed to the assumed similar microstructures that evolved from the similar size coke particles and the same forming method
Abstract
Selecting graphite grades with superior irradiation characteristics is important task for designers of graphite moderation reactors. To provide reference information and data for graphite selection, the effects of irradiation on three fine-grained, iso-molded nuclear grade graphites, ETU-10, IG-110, and NBG25, were compared based on irradiation-induced changes in volume, thermal conductivity, dynamic Young's modulus, and coefficient of thermal expansion. Data employed in this study were obtained from reported irradiation test results in the high flux isotope reactor (HFIR)(ORNL) (ETU-10, IG-110) and high flux reactor (HFR)(NRL) (IG-110, NBG-25). Comparisons were made based on the irradiation dose and irradiation temperature. Overall, the three grades showed similar irradiation-induced property change behaviors, which followed the historic data. More or less grade-sensitive behaviors were observed for the changes in volume and thermal conductivity, and, in contrast, grade-insensitive behaviors were observed for dynamic Young's modulus and coefficient of thermal expansion changes. The ETU-10 of the smallest grain size appeared to show a relatively smaller VC to IG-110 and NBG-25. Drastic decrease in the difference in thermal conductivity was observed for ETU-10 and IG-110 after irradiation. The similar irradiation-induced properties changing behaviors observed in this study especially in the DYM and CTE may be attributed to the assumed similar microstructures that evolved from the similar size coke particles and the same forming method
참고문헌 (20)
- Advances in Small Modular Reactor Technology Developments, , IAEA, ~ (2020)
- Overview of Small Modular Reactor Technology Development, Frederik Reitsma, , IAEA, ~ (2020)
- T.D. Burchell, "Carbon Materials for Advanced Technologies, Chapter 13", 429~484 (1999)
- S. Ishiyama, , J. Nucl. Mater, 230, pp.1~7 (1996)
- A. A. Campbell, "High Dose Irradiation Behavior of IG-110, INGSM-18", ~ (2017)
- A. A. Campbell, "Effects of Neutron Irradiation at Elevated Temperatures on the Materials Properties of IG-110", ~
- Report on Effects of Irradiation on Material IG-110, "A.A. Campbell", ORNL, ~, pp.ORNL (2017), TM-2017[DOI]
- Y. Katoh, "Results of High eFluence Neutron Irradiation on Ibiden Nuclear Graphite ETU-10, INGSM-18", ~ (2017)
- A. A. Campbell, "Materials Property Changes in ETU-10 Due to Neutron Irradiation at Elevated Temperatures", ~
- M. C. R. Heijna, , J. Nucl. Mater, 402, pp.148~156 (2017)
- "ASTM D 7219-08, Standard Specification for Isotropic and Near Isotropic Nuclear Graphite", ASTM, ~ (2008)
- Gerd Haag, "Thermal Conductivity of Graphite at High Fast Neutron Fluences", 3rd International Nuclear Graphite Specialist Meeting (2002)
- "NGNP High Temperature Materials White Paper", INL, 2012
- T. D. Burchell, "Comprehensive Nuclear Materials, vol. 4", pp.299~324 (2012), Elsevier Ltd
- T.D. Burchell, , J. Nucl. Mater, 179-181, pp.205~208 (1991)
- R. E. Nightingale, "Nuclear Graphite", pp.117~186 (1962), Academic Press
- Mike Davies, "Assessment of Candidate Graphites for Future High Temperature Reactors, INGSM-13", 23~26 (2012)
- M. C. R. Heijna, "Comparison of Irradiation Behavior of HTR Graphite Grades, INGSM-18", 18~21 (2017)
- L. L. Snead, , J. Nucl. Mater, 381, pp.76~82 (2008)
- Pergamon, LondonT.D., "Carbon Materials for Advanced Technologies", 205~208 (1999)