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
- 1,037 - 1,042 (6page)
이용수
초록· 키워드
오류제보하기
The present study aims to assess the excess induced reactivity in a Miniature Neutron Source Reactor(MNSR) for a Beyond Design Basis Accident (BDBA) scenario. The BDBA scenario as defined in the SafetyAnalysis Report (SAR) of the reactor involves sticking of the control rod and filling of the inner and outerirradiation sites with water. At the end of the MNSR core life, 10.95 cm of Beryllium is added to the top ofthe core as a reflector which affects some neutronic parameters such as effective delayed neutronsfraction (beff), the reactivity worth of inner and outer irradiation sites that are filled with water and thereactivity worth of the control rod. Given those influences and changes, new neutronic calculations arerequired to be able to demonstrate the reactor safety. Therefore, a validated MCNPX model is used tocalculate all neutronic parameters at the end of the reactor core life. The calculations show that theinduced reactivity in the BDBA scenario increases at the end of core life to 7.90 ± 0.01 mk which issignificantly higher than the induced reactivity of 6.80 mk given in the SAR of MNSR for the samescenario but at the beginning of the core's life. Also this value is 3.90 mk higher than the maximumallowable operational limit (i.e. 4.00 mk).
목차
등록된 정보가 없습니다.
참고문헌 (23)
참고문헌 신청
2004 / Code of Conduct on the Safety and Security of Radioactive Sources
2016 / IAEA Safety of Research Reactors
G. Chengzhan / 1992 / The Iranian MNSR Safety Analysis Report (SAR)
J. Mokhtari / 2017 / Design and optimization of the new LEU MNSR for neutron radiography using thermal column to upgrade thermal flux / Progress Nuclear Energy 100:221~232
J. Mokhtari / 2017 / Conceptual design study of the low power and LEU medical reactor for BNCT using in-tank fission converter to increase epithermal flux / Progress in Nuclear Energy 95:70~77
2016 / IAEA Safety of Research Reactors
G. Chengzhan / 1992 / The Iranian MNSR Safety Analysis Report (SAR)
J. Mokhtari / 2017 / Design and optimization of the new LEU MNSR for neutron radiography using thermal column to upgrade thermal flux / Progress Nuclear Energy 100:221~232
J. Mokhtari / 2017 / Conceptual design study of the low power and LEU medical reactor for BNCT using in-tank fission converter to increase epithermal flux / Progress in Nuclear Energy 95:70~77
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
MNSR transient analysis using the RELAP5/Mod3.2 code
Nuclear Engineering and Technology
2020 .09
-
Development of a 3D thermohydraulic-neutronic coupling model for accident analysis in research miniature neutron source reactor (MNSR)
Nuclear Engineering and Technology
2019 .01
-
Neutronic analysis of control rod effect on safety parameters in Tehran Research Reactor
Nuclear Engineering and Technology
2018 .01
-
Supercritical CO2-cooled fast reactor and cold shutdown system for ship propulsion
Nuclear Engineering and Technology
2024 .03
-
Measurement of Safety rods reactivity worth by advanced source jerk method in HWZPR
Nuclear Engineering and Technology
2019 .01
-
Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Nuclear Engineering and Technology
2021 .02
-
Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method
Nuclear Engineering and Technology
2024 .06
-
무제어봉 원자로의 고유안전 개념을 지니는 Density Lock 내부 열성층화 불안정성에 대한 고찰
한국유체기계학회 논문집
2023 .12
-
Diagnostic methods applied to Esfahan light water subcritical reactor (ELWSCR)
Nuclear Engineering and Technology
2021 .07
-
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
-
Reactivity balance for a soluble boron-free small modular reactor
Nuclear Engineering and Technology
2018 .01
-
Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS
Nuclear Engineering and Technology
2021 .03
-
Conceptual design of a high neutron fl ux research reactor core with low enriched uranium fuel and low plutonium production
Nuclear Engineering and Technology
2020 .01
-
Reactor core design with practical gadolinia burnable absorbers for soluble boron-free operation in the innovative SMR
Nuclear Engineering and Technology
2024 .08
-
Transient Analysis of a Subcritical Reactor Core with a MOX-Fuel using the Birth-and-Death Model
Nuclear Engineering and Technology
2021 .06
-
Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis
Nuclear Engineering and Technology
2023 .06
-
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
-
JSI TRIGA fuel rod reactivity worth experiments for validation of Serpent-2 and RAPID fuel burnup calculations
Nuclear Engineering and Technology
2024 .08
-
State-Space Model Predictive Control Method for Core Power Control in Pressurized Water Reactor Nuclear Power Stations
Nuclear Engineering and Technology
2017 .01
-
근골격 해부학에 근거한 텐던 매커니즘 기반 다자유도 로봇 핸드(SSP Mk.1, SSP Mk.2)의 기구학적 설계 및 분석
제어로봇시스템학회 국내학술대회 논문집
2021 .06
이 논문의 저자 정보
최근 본 자료
댓글(0)
0