Results 71 to 80 of about 130 (115)

Study on control rod worth measurement technique under deep subcritical condition

He jishu
BackgroundIn a series of startup physics tests, measuring the control rod worth is a critical means to determine whether the actual worth of the control rods matches the design values. This test ensures that the reactivity of the reactor can be precisely
SI Shengyi, BEI Hua, CHEN Lunshou, QIAN Zhongyou, DU Chao, GAO Mingmin, YANG Gaosheng   +6 more
doaj   +1 more source

Levels, sources, variations, and human health risk assessment of ⁹⁰Sr and ¹³⁷Cs in water and food around Sanmen Nuclear Power Plant (China) from 2011 to 2020. [PDF]

Front Public Health, 2023
Wang P, Yu S, Zou H, Lou X, Ren H, Zhou L, Lai Z, Xuan Z, Gao X, Xu Q, Zhou Z, Zhao Y, Cao Y.   +12 more
europepmc   +1 more source

Impact of silicon on neutronic performance and microstructural evolution of FeCrAl alloys for ATF cladding

EPJ Nuclear Sciences & Technologies
FeCrAl alloys are promising candidate for accident tolerant fuel (ATF) cladding in light water-cooled nuclear reactors (LWRs) due to their excellent high-temperature oxidation resistance and mechanical strength.
Ngarayana I. Wayan, Mulyana Dany, Andryansyah, Saragi Elfrida, Sony Tjahyani Damianus Toersiwi, Citra Amelia Almira, Farihin Parikin, Djuliana Safiya   +7 more
doaj   +1 more source

Study on SCC Propagation Behavior of a Dissimilar Metal Weld Joint of Nuclear Power Squib Valve in PWR Primary Water

Yuanzineng kexue jishu
This study aims to elucidate stress corrosion cracking (SCC) behavior in 316LN stainless steel (SS) and alloy 690 dissimilar metal weld joints of AP1000 pressurized water reactor (PWR) squib valves, critical for ensuring structural integrity in passive ...
PENG Cheng1, ZHANG Xu2, YUAN Xinyu2, WANG Jiamei1, GAO Liangwen3, CHEN Kai1, , ZHANG Lefu1
doaj   +1 more source

Numerical Simulation of Flow Distribution and Transient Thermal Stratification Characteristics of Passive Residual Heat Removal Heat Exchangers

Yuanzineng kexue jishu
The passive residual heat removal heat exchanger (PRHR HX) is a key component of the third-generation advanced pressurized water reactor (PWR) nuclear power plant’s passive safety systems. The PRHR HX has numerous heat transfer tubes with varying lengths
HE Shaopeng1, 2, WANG Mingjun1, 2, TIAN Wenxi1, 2, QIU Suizheng1, 2, SU Guanghui1, 2
doaj   +1 more source

Can Distributed Nuclear Power Address Energy Resilience and Energy Poverty? [PDF]

Joule, 2020
Gilbert AQ, Bazilian MD.
europepmc   +1 more source

Testing and validation of the nuclear data processing code cosRuler

四川大学学报. 自然科学版
The nuclear data processing software cosRuler within the COSINE software package is written in Fortran and currently integrates 14 functional modules. Based on the ENDF/B-VII.1 evaluated nuclear data library， cosRuler was used to generate the multigroup ...
ZHOU Hang, ZENG Qin, ZHAO Yuyang, WU Ming’en   +3 more
doaj  

Advanced Nuclear Reactor AP1000 with ThO₂-UO₂ Fuel

Journal of Physics: Conference Series, 2019
R.F. Baskara, A. Waris, R. Kurniadi, K. Basar, null Widayani, S. Sahin   +5 more
openaire   +1 more source

Comparison and Analysis of AP1000 Nuclear Reactor Waste Treatment Technology in China

Nuclear Science and Technology, 2017
openaire   +1 more source

Prediction of spallation induced transmutation rates for long-lived fission products via proton accelerator. [PDF]

Sci Rep
Tukharyan G, Kendrick WR, Yu J, Danagoulian A, Forget B.   +4 more
europepmc   +1 more source