Results 41 to 50 of about 2,093 (208)
Nuclear Engineering and TechnologyWith part-load operation is increasingly becoming important issue for small modular reactors (SMRs), two secondary Rankine cycles for a 500 MWth pressurized-water-reactor small modular reactor were compared under identical thermodynamic constraints: a ...
Gyudong Kim +3 more
doaj +1 more source
Science and Technology of Nuclear Installations, 2014 After emergency shutdown of high-temperature-gas-cooled reactor, the residual heat of the reactor core should be removed. As the natural circulation process spends too long period of time to be utilized, an active residual heat removal procedure is ...
Xingtuan Yang +3 more
doaj +1 more source
Experiment data report for Semiscale Mod-1 test S-28-3 (steam generator tube rupture test). [PWR] [PDF]
, 1977 Recorded test data are presented for Test S-28-3 of the Semiscale Mod-1 steam generator tube rupture test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a ...
Gillins, R.L. +3 more
core +1 more source
Design of Coil-Wound Once-Through Steam Generator System for Concentrating Solar Power Plants
SolarPACES Conference ProceedingsThe viability of solar tower plants is endangered owing to multiple failures, mainly in their steam generators. These failures produce unscheduled shutdowns with significant economic losses that increase the financing costs of this technology due to its
Dario Pardillos-Pobo +3 more
doaj +1 more source
Yuanzineng kexue jishu, 2022 As the fourth generation nuclear power technology, high temperature gas-cooled reactor (HTGR) has good prospects due to its inherent safety and high temperature.
SU Yang;LI Xiaowei;WU Xinxin
doaj
Experiment data report for Semiscale Mod-1 Test S-28-1 (steam generator tube rupture test series) [PDF]
, 1977 Recorded test data are presented for Test S-28-1 of the Semiscale Mod-1 steam generator tube rupture test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a ...
Coppin, C.E. +2 more
core +1 more source
Performance demonstration requirements for eddy current steam generator tube inspection [PDF]
, 1992 This paper describes the methodology used for developing performance demonstration tests for steam generator tube eddy current (ET) inspection systems. The methodology is based on statistical design principles.
Heasler, P. G. +2 more
core +3 more sources
Markov stochastic process modeling for evolution of wear depth in steam generator tubes
Advances in Mechanical Engineering, 2019 Reliability of steam generator is a serious concern in the operation of nuclear power plants, especially for steam generator tubes that experience a variety of degradation mechanisms including wear damage. It is necessary to develop a model to accurately
Xing He +5 more
doaj +1 more source
Sensors, 2017 Measuring the radial collision force between the steam generator tube (SGT) and the tube support plate (TSP) is essential to assess the fretting damage of the SGT. In order to measure the radial collision force, a novel miniaturized force sensor based on
Peijian Huang +4 more
doaj +1 more source
Joint optimization of safety barriers for enhancing business continuity of nuclear power plants against steam generator tube ruptures accidents [PDF]
, 2020 In nuclear power plants (NPPs), different types of safety barriers are designed to ensure the safe and continuous operation of the NPP against disruptive events.
Xing J., Zeng Z., Zio E.
core +1 more source