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.
이 논문의 연구 히스토리 (6)
- 이 논문의 후속연구가 궁금하신가요?
- 연관 학술논문 또는 학술발표를 통해 보다 발전된 연구결과를 확인하실 수 있습니다.
- 이 논문의 연구 히스토리 확인하기
초록· 키워드
오류제보하기
Self-powered neutron detector (SPND) is a sensor to monitor a neutron flux proportional to a reactor power of the nuclear powerplants. Since an SPND is usually installed in the reactor core and does not require additional outside power, it generates electrons itselffrom interaction between neutrons and a neutron-sensitive material called an emitter, such as rhodium and vanadium. This paper presentsthe simulations of the depletion sensitivity evaluations based on MCNP models of rhodium and vanadium SPNDs and light water reac-tor fuel assembly. The evaluations include the detail geometries of the detectors and fuel assembly, and the modeling of rhodium andvanadium emitter depletion using MCNP and ORIGEN-S codes, and the realistic energy spectrum of beta rays using BETA-S code.The results of the simulations show that the lifetime of an SPND can be prolonged by using vanadium SPND than rhodiumSPND. Also, the methods presented here can be used to analyze a life-time of those SPNDs using various emitter materials.
목차
등록된 정보가 없습니다.
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Monte Carlo 방법을 이용한 바나듐 자발 중성자계측기 초기 민감도 계산
센서학회지
2016 .01
-
코발트 SPND의 중성자 조사 즉발 응답 특성 확인
한국에너지학회 학술발표회
2023 .10
-
Simulation, design optimization, and experimental validation of a silver SPND for neutron flux mapping in the Tehran MTR
Nuclear Engineering and Technology
2020 .12
-
Current compensation for material consumption of cobalt self-powered neutron detector
Nuclear Engineering and Technology
2020 .01
-
코발트 중성자 검출기의 아날로그 신호보상 방법에 관한 논고
한국정밀공학회 학술발표대회 논문집
2021 .05
-
즉발 응답형 중성자 검출기의 신호보상을 위한 최적 필터의 적용에 관한 연구
한국정밀공학회 학술발표대회 논문집
2022 .05
-
확장형 칼만 필터를 이용한 즉발 응답형 중성자 검출기의 신호 보상에 관한 연구
한국정밀공학회 학술발표대회 논문집
2022 .10
-
Design of High-Gain Signal Amplifier Circuit for Prompt-Response Self-Powered Neutron Detector
Journal of the Korean Society for Precision Engineering
2022 .05
-
A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test
방사선방어학회지
2016 .01
-
Applicability of the Kr ? ko nuclear power plant core Monte Carlo model for the determination of the neutron source term
Nuclear Engineering and Technology
2021 .11
-
Monte Carlo simulation and optimization of neutron ray shielding performance of related materials
Nuclear Engineering and Technology
2024 .09
-
고정형 노내핵계측기 신호증폭 계통용 아날로그 신호보상회로를 이용한 즉발응답형 중성자 검출기의 신호분석
한국정밀공학회 학술발표대회 논문집
2023 .05
-
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
-
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 irradiation impact on structural and electrical properties of polycrystalline Al2O3
Nuclear Engineering and Technology
2024 .02
-
Assessment of neutron-induced activation of irradiated samples in a research reactor
Nuclear Engineering and Technology
2023 .03
-
An Assessment of the Secondary Neutron Dose in the Passive Scattering Proton Beam Facility of the National Cancer Center
Nuclear Engineering and Technology
2017 .06
-
Analysis of fluctuations in ex-core neutron detector signal in Krško NPP during an earthquake
Nuclear Engineering and Technology
2024 .02
-
Overcoming the challenges of Monte Carlo depletion: Application to a material-testing reactor with the MCS code
Nuclear Engineering and Technology
2020 .09
이 논문의 저자 정보
최근 본 자료
댓글(0)
0