지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2018.1
- 수록면
- 788 - 793 (6page)
이용수
초록· 키워드
오류제보하기
High-density spent fuel (SF) storage racks have been installed to increase SF pool capacity. In these SFracks, neutron absorber materials were placed between fuel assemblies allowing the storage of fuelassemblies in close proximity to one another. The purpose of the neutron absorber materials is to precludeneutronic coupling between adjacent fuel assemblies and to maintain the fuel in a subcriticalstorage condition. METAMIC neutron absorber has been used in high-density storage racks. But, neutronabsorber materials can be subject to severe conditions including long-term exposure to gamma radiationand neutron radiation. Recently, some of them have experienced degradation, such as white spots on thesurface. Under these conditions, the material must continue to serve its intended function of absorbingneutrons. For the first time in Korea, this article uses a neutron attenuation test to examine the performanceof METAMIC surveillance coupons. Also, scanning electron microscope analysis was carried outto verify the white spots that were detected on the surface of METAMIC. In the neutron attenuation test,there was no significant sign of boron loss in most of the METAMIC coupons, but the coupon with whitespots had relatively less B-10 content than the others. In the scanning electron microscope analysis,corrosion material was detected in all METAMIC coupons. Especially, it was confirmed that the couponwith white spots contains much more corrosion material than the others.
목차
등록된 정보가 없습니다.
참고문헌 (7)
참고문헌 신청
W. Emma / 2009 / Degradation of Neutron-Absorbing Materials in Spent Fuel Pool, NRC Information Notice 2009-2026
A. Machiels / 2010 / Overview of BORAL Performance Based Upon Surveillance Coupon Measurements :1021052
H. Akkurt / 2015 / Overview of Neutron Absorber Materials Used in Spent Fuel Pools / International Conference on Nuclear Criticality Safety
A. Machiels / 2009 / Handbook of Neutron Absorber Materials for Spent Nuclear Fuel Transportation and Storage Applications :1019110
2007 / Ulchin Units 3 and 4 Spent Fuel Pool Region 1 and Region 2 Criticality Evaluation, HI-2073685
A. Machiels / 2010 / Overview of BORAL Performance Based Upon Surveillance Coupon Measurements :1021052
H. Akkurt / 2015 / Overview of Neutron Absorber Materials Used in Spent Fuel Pools / International Conference on Nuclear Criticality Safety
A. Machiels / 2009 / Handbook of Neutron Absorber Materials for Spent Nuclear Fuel Transportation and Storage Applications :1019110
2007 / Ulchin Units 3 and 4 Spent Fuel Pool Region 1 and Region 2 Criticality Evaluation, HI-2073685
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test
방사선방어학회지
2016 .01
-
Fixed neutron absorbers for improved nuclear safety and better economics in nuclear fuel storage, transport and disposal
Nuclear Engineering and Technology
2023 .06
-
Neutron irradiation impact on structural and electrical properties of polycrystalline Al2O3
Nuclear Engineering and Technology
2024 .02
-
Monte Carlo simulation and optimization of neutron ray shielding performance of related materials
Nuclear Engineering and Technology
2024 .09
-
Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants
Nuclear Engineering and Technology
2018 .01
-
A high-stability neutron generator for industrial online elemental analysis
Nuclear Engineering and Technology
2024 .04
-
A high-density gamma white spots-Gaussian mixture noise removal method for neutron images denoising based on Swin Transformer UNet and Monte Carlo calculation
Nuclear Engineering and Technology
2024 .02
-
A feasibility study of the Iranian Sun mather type plasma focus source for neutron capture therapy using MCNP X2.6, Geant4 and FLUKA codes
Nuclear Engineering and Technology
2020 .01
-
Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility
Nuclear Engineering and Technology
2018 .01
-
Electrical characteristics and deep-level transient spectroscopy of a fast-neutron-irradiated 4H–SiC Schottky barrier diode
Nuclear Engineering and Technology
2023 .01
-
Thermal neutron albedo and flux for different geometries neutron guide
Nuclear Engineering and Technology
2019 .01
-
Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source
Nuclear Engineering and Technology
2017 .06
-
Neutron diagnostics using nickel foil activation analysis in the KSTAR
Nuclear Engineering and Technology
2021 .09
-
A REVIEW OF NEUTRON SCATTERING CORRECTION FOR THE CALIBRATION OF NEUTRON SURVEY METERS USING THE SHADOW CONE METHOD
Nuclear Engineering and Technology
2015 .01
-
Characterization of a Neutron Beam Following Reconfi guration of the Neutron Radiography Reactor (NRAD) Core and Addition of New Fuel Elements
Nuclear Engineering and Technology
2016 .01
-
A Study on Electrochemical Characteristics Aluminum Multi Matrix Compound (Al-MMC) of Neutron Absorber Material
한국방사성폐기물학회 학술대회
2018 .01
-
습식 저장시설 내 사용후핵연료 연소도 측정을 위한 감마선/중성자 검출기 개발
방사선산업학회지
2024 .09
-
Current compensation for material consumption of cobalt self-powered neutron detector
Nuclear Engineering and Technology
2020 .01
-
Fast Neutron Detection for Spent PWR Fuel in Dry Storage
한국방사성폐기물학회 학술대회
2017 .01
-
Method of the known cross sections for calibration of the fast neutron spectrometer with a single-crystal stilbene based detector
Nuclear Engineering and Technology
2024 .09
이 논문의 저자 정보
최근 본 자료
댓글(0)
0