scispace - formally typeset
Search or ask a question

Showing papers in "Nuclear Engineering and Design in 2020"


Journal ArticleDOI
TL;DR: A review of the research activities which have been carried out for S-CO2 power cycle based nuclear applications worldwide is presented in this article, where the challenges and perspectives are discussed and highlighted in the paper.

83 citations


Journal ArticleDOI
TL;DR: An overview of the fundamentals of artificial intelligence and the state of development of learning-based methods in nuclear science and engineering is presented to identify the risks and opportunities of applying such methods to nuclear applications.

63 citations


Journal ArticleDOI
Wenjie Zeng1, Weicong Zhu1, Tianyu Hui1, Lezhi Chen1, Jinsen Xie1, Tao Yu1 
TL;DR: The core power control of liquid molten salt reactor under step reactivity disturbance and load tracking is studied and the results show that the IMC-PID controller can control the core power well.

37 citations


Journal ArticleDOI
TL;DR: Evaluation of the performance metrics for these two moderated designs has yielded the downselected TCR design: a TRISO-fueled and yttrium hydride moderated gas-cooled reactor.

34 citations


Journal ArticleDOI
TL;DR: In this paper, a review on the UREX and variants of the uREX++processes used for reprocessing of the spent nuclear fuels is presented, where the strategy of nonproliferation resistance using the advanced reprocessed process is described in the present work.

31 citations


Journal ArticleDOI
TL;DR: The as discussed by the authors summarizes the goals and recent progress of the Department of Energy's Gas-Cooled Reactor research and development campaign and how it supports a wide variety of industrial efforts to deploy high temperature reactors to serve modern energy markets.

28 citations


Journal ArticleDOI
TL;DR: In this article, the authors reviewed the research on the generation, distribution, radioactivity, deposition, resuspension and coagulation of graphite dust in a pebble bed high temperature reactor.

27 citations


Journal ArticleDOI
TL;DR: The model considers the dynamics of the reactor core, thermal hydraulics, piping and plenum, pressurizer, steam generator, condenser, and turbine-governor system, in addition to various actuators and sensors, and has the potential to become a benchmark for control design studies in PWR nuclear power plants.

27 citations


Journal ArticleDOI
TL;DR: In this article, the authors describe the accident progression in unit 3 of the Fukushima Daiichi nuclear power station as analyzed in the Phase 2 of the OECD/NEA project “Benchmark Study of the Accident at the Daiichi Nuclear Power Plant” (BSAF).

26 citations


Journal ArticleDOI
TL;DR: A high-level overview of the KP-FHR design, thermal hydraulics R&D strategy, test program, and modeling and simulation activities, including the reactor systems code KP-SAM and applications of computational fluid dynamics methods in design and analysis are presented.

25 citations


Journal ArticleDOI
TL;DR: The Xe-100 is a high temperature, helium-cooled, graphite moderated, pebble bed reactor (HTGR) featuring a 6-times through, multi-pass (MEDUL=MEhrfachDUrchLauf) fuelling scheme as mentioned in this paper.

Journal ArticleDOI
TL;DR: In this article, the effect of tube bundle configuration, tube shape, longitudinal tube pitch, transversal tube pitch and tube row number on natural convection heat transfer was numerically studied.

Journal ArticleDOI
TL;DR: The numerical framework, governing equations and solution strategy behind OFFBEAT are presented, and a brief overview of the material properties and behavioral models already implemented are given and a set of experimental rods are chosen to provide the first validation results for the thermal behavior of low burnup axisymmetric rods.

Journal ArticleDOI
TL;DR: In this article, the configuration of the ALFRED reactor coolant system showing its present state of development and technological innovations is presented, and the current plant architecture provides for a thermal power up to 300 MWth and a coolant temperature range from a minimum of 390°C to a maximum of 520°C.

Journal ArticleDOI
TL;DR: The Severe Accident Test Station at Oak Ridge National Lab as mentioned in this paper provides various temperature profiles, steam, and thermal shock conditions necessary for integral loss of coolant accident testing, defueled oxidation quench testing, and high-temperature beyond design basis accident testing.

Journal ArticleDOI
TL;DR: In this article, a thermodynamic model of sCO2 recompression cycle based on sodium-cooled fast reactor was established and the sensitivity analysis of inlet conditions at turbomachinery and cycle pressure ratio (PR) was conducted in combination with the flow split ratio (FSR).

Journal ArticleDOI
Gen Li1, Panpan Wen1, Feng Haobo1, Jun Zhang1, Junjie Yan1 
TL;DR: In this article, the MPS method was applied to analyze melt stratification and migration in debris bed by including the models of radiation heat transfer among debris, melt phase change and surface tension.

Journal ArticleDOI
TL;DR: In this article, the authors discuss the current state-of-the-art in liquid metal thermal hydraulics and also its future perspectives, including liquid metal heat transfer, fluid-structure interaction, fuel assembly thermal hydraulic, coolant solidification, efficient 3-d system modelling, and validation at large.

Journal ArticleDOI
TL;DR: In this article, a comparative analysis of the results of a combined experimental, theoretical, and computational study of phase distribution around and downstream from complex-geometry spacer grids with split-vane type mixing devices is presented.

Journal ArticleDOI
TL;DR: A recurrent neural network-based approach is proposed to tackle anomaly detection issues by effectively utilizing historical data obtained during both normal and abnormal operations, demonstrating much improved detection accuracy and practicality of the proposed method over conventional approaches.

Journal ArticleDOI
Zesi Tang1, Jialin Li1, Jin Guo1, Su Zhang1, Zaipeng Duan1 
TL;DR: In this article, the effects of vent size on the internal overpressure and flame behavior within and outside a 1m3 cuboid test chamber with 30vol% hydrogen-air mixtures were investigated.

Journal ArticleDOI
TL;DR: In this paper, beryllium-and hydride-based graphite-based moderators have been evaluated for high temperature gas-cooled (mHTGR) systems.

Journal ArticleDOI
TL;DR: A RBF-based adaptive sliding mode control strategy with extended state observer (ESO) for load following of nuclear power plants in the presence of disturbances is proposed, which consists of a dual closed-loop integral slide mode control scheme while taking into account disturbances simultaneously.

Journal ArticleDOI
TL;DR: A procedure compliance check (PCC) system to monitor operator action and detect procedural deviation is proposed, which employs a deep learning algorithm to predict operator judgement.

Journal ArticleDOI
Zeguang Li1, Jun Sun1, Malin Liu1, Minggang Lang1, Lei Shi1 
TL;DR: In this article, a concept of integrated gas-cooled space nuclear reactor named IGCR-200 is introduced, which is designed based on the TRISO particle fuel and could achieve 200 kWe output combined with highly efficient He/Xe CBC generator.

Journal ArticleDOI
TL;DR: In this article, the authors examined the effects of nuclear-renewables mix on the electricity generation industry and determined that the addition of some nuclear generating capacity decreases by approximately 3 the required wind capacity and by a factor of 6 the required solar installed capacity, and the contributions of nuclear energy also result in reductions of the dissipated energy in the storage-regeneration processes and the needed utility level storage capacity.

Journal ArticleDOI
TL;DR: The results show the capabilities of DMD to extract and surrogate the dynamics of the MSFR following perturbation, including the initial non-linear dynamics and the final steady-state.

Journal ArticleDOI
TL;DR: In this paper, the authors analyzed three station blackout (SBO) scenarios for a representative U.S. operating Boiling Water Reactor (BWR) based on Peach Bottom Atomic Power Station using system thermal-hydraulics code TRACE.

Journal ArticleDOI
TL;DR: In this paper, the authors present an outline and results of hydrogen production tests by using the test facility and reliability improvements by developing a strength estimation method for heat-resistant and corrosion-resistant ceramics components made of silicon carbide.

Journal ArticleDOI
TL;DR: In this article, the authors reviewed various stages involved in the structural integrity assessment of Reactor Pressure Vessel (RPV) subjected to Pressurised Thermal Shock (PTS), where focus is given to fracture analysis.