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
- 2019.1
- 수록면
- 963 - 967 (5page)
이용수
초록· 키워드
오류제보하기
Accurate measurement of the reactivity worth of safety rods is very important for the safe reactoroperation, in normal and emergency conditions. In this paper, the reactivity worth of safety rods in HeavyWater Zero Power Reactor (HWZPR) in the new lattice pitch is measured by advanced source jerkmethod. The average of the results related to two different detectors is equal to 29.88 mk. In order toverify the result, this parameter was compared to the previously measured value by subcritical to criticalapproach. Different experiment results are finally compared with corresponding calculated result. Differencebetween the average experimental and calculated results is equal to2.2%
목차
등록된 정보가 없습니다.
참고문헌 (9)
참고문헌 신청
Zahra Nasrazadani / 2017 / Investigating Heavy Water Zero Power Reactors with a New Core Configuration Based on Experiment and Calculation Results / Nuclear Engineering and Technology 49(1):1~5
Z. Nasr / 2017 / Study about effective photoneutron coefficient in HWZPR / Anu. Of Nuc. Eng 107:37~41
2017 / Safety Analysis Report on Heavy Water Zero Power Reactor
CIAE / 1993 / HWR Advanced Source Jerk Experiment Technique and Data Processing
Zahra Nasrazadani / 2016 / Investigating Dynamic Parameters in HWZPR Based on the Experimental and Calculated Results / Nuclear Engineering and Technology 48(5):1120~1125
Z. Nasr / 2017 / Study about effective photoneutron coefficient in HWZPR / Anu. Of Nuc. Eng 107:37~41
2017 / Safety Analysis Report on Heavy Water Zero Power Reactor
CIAE / 1993 / HWR Advanced Source Jerk Experiment Technique and Data Processing
Zahra Nasrazadani / 2016 / Investigating Dynamic Parameters in HWZPR Based on the Experimental and Calculated Results / Nuclear Engineering and Technology 48(5):1120~1125
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
A practical subcritical rod worth measurement technique based on the improved neutron source multiplication method
Nuclear Engineering and Technology
2024 .04
-
Sensitivity of a control rod worth estimate to neutron detector position by time-dependent Monte Carlo simulations of the rod drop experiment
Nuclear Engineering and Technology
2024 .03
-
JSI TRIGA fuel rod reactivity worth experiments for validation of Serpent-2 and RAPID fuel burnup calculations
Nuclear Engineering and Technology
2024 .08
-
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
-
Investigating Heavy Water Zero Power Reactors with a New Core Configuration Based on Experiment and Calculation Results
Nuclear Engineering and Technology
2017 .01
-
Reactivity balance for a soluble boron-free small modular reactor
Nuclear Engineering and Technology
2018 .01
-
Neutronic analysis of control rod effect on safety parameters in Tehran Research Reactor
Nuclear Engineering and Technology
2018 .01
-
Investigating Dynamic Parameters in HWZPR Based on the Experimental and Calculated Results
Nuclear Engineering and Technology
2016 .01
-
Reactor core design with practical gadolinia burnable absorbers for soluble boron-free operation in the innovative SMR
Nuclear Engineering and Technology
2024 .08
-
무제어봉 원자로의 고유안전 개념을 지니는 Density Lock 내부 열성층화 불안정성에 대한 고찰
한국유체기계학회 논문집
2023 .12
-
The reactivity of SO₂ and NO₂ on different mineral oxides
한국에너지학회 학술발표회
2018 .04
-
Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life
Nuclear Engineering and Technology
2018 .01
-
Performance of different absorber materials and move-in/out strategies for the control rod in small rod-controlled pressurized water reactor: A study based on KLT-40 model
Nuclear Engineering and Technology
2024 .07
-
Analysis of the CREOLE experiment on the reactivity temperature coefficient of the UO2 light water moderated lattices using Monte Carlo transport calculations and ENDF/B-VII.1 nuclear data library
Nuclear Engineering and Technology
2020 .01
-
Numerical simulation and experimental study of quasi-periodic large-scale vortex structures in rod bundle lattices
Nuclear Engineering and Technology
2024 .02
-
연료 성분 변화에 따른 저 반응성 연료 점화 지연 특성 연구
KOSCO SYMPOSIUM 논문집
2021 .05
-
Performance evaluation of the Floating Absorber for Safety at Transient (FAST) in the innovative Sodium-cooled Fast Reactor (iSFR) under a single control rod withdrawal accident
Nuclear Engineering and Technology
2020 .01
-
A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments
Nuclear Engineering and Technology
2022 .05
-
Diagnostic methods applied to Esfahan light water subcritical reactor (ELWSCR)
Nuclear Engineering and Technology
2021 .07
-
표면처리방법에 따른 CFRP Rod와 콘크리트간 부착 성능
한국콘크리트학회 학술대회 논문집
2019 .05
이 논문의 저자 정보
최근 본 자료
댓글(0)
0