Piyush Sabharwall

united states department of energy (doe)

H指数:31

被引数:4,103

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Digital twin-enabled reinforcement learning for adaptive and degradation-aware control of high-temperature electrolysis

数字孪生赋能的强化学习，用于高温电解的适应性及降级感知控制

Energy and AI

IF9.6

2026-09-160

OAAI

Validation of computational fluid dynamics bypass flow predictions with the Idaho National Laboratory matched index of refraction flow facility

利用爱达荷国家实验室匹配折射率流动装置验证计算流体动力学旁路流预测

Nuclear Engineering and Design

IF2.1

2026-08-010

PRE

Special Issue on Advances in Thermal Hydraulics of Nuclear Power Plants

核电站热工水力学进展专刊

Journal of Nuclear Engineering

IF1.2

2026-04-080

PRE

Foreword Special Issue on Irradiation Experiments Supporting Advanced Nuclear Technologies Guest Editors

先进核技术支持的辐照实验特刊编者前言特刊编辑

Nuclear Science and Engineering

IF1.3

2026-01-020

PRE

Margin to onset of nucleate boiling and flow instability studies for preliminary MITR design-demonstration element thermal-hydraulics

MITR初步设计演示元件的热工水力学研究：核态沸腾起始点裕度与流型不稳定性研究

Nuclear Engineering and Design

IF2.1

2026-01-010

PRE

Non-dimensional performance and safety parameters for heat pipes

热管的非 dimensional 性能和安全参数

Applied Thermal Engineering

IF6.9

2025-12-230

PRE

Accelerated Irradiation Testing and Post-Irradiation Characterization: US-Based Capabilities for Advanced Nuclear Systems and Radioisotope Production

NUCLEAR SCIENCE AND ENGINEERING

IF1.3

2025-11-010

PRE

Phenomena Identification and Ranking Table (PIRT) for heat pipes

热管的现象识别与排序表（PIRT）

Progress in Nuclear Energy

IF3.2

2025-07-240

PRE

Development of novel oval-twisted helical tube once-through steam generator: Part I: Single-phase laminar flow

PROGRESS IN NUCLEAR ENERGY

IF3.2

2025-05-010

PRE

Development and experimental evaluation of an acoustic flow meter prototype for measuring air flow

MEASUREMENT

IF5.6

2025-01-010

PRE

Trace xenon detection in ambient helium by double-pulse laser-induced breakdown spectroscopy

JOURNAL OF ANALYTICAL ATOMIC SPECTROMETRY

IF3.1

2025-01-010

Design of experimental facility for helium gas component testing

PROGRESS IN NUCLEAR ENERGY

IF3.2

2024-12-010

PRE

Technical and economic evaluation of heat transfer fluids for a TES system integrated to an advanced nuclear reactor

集成到先进核反应堆的TES系统的传热流体的技术和经济评估

APPLIED ENERGY

IF11

2024-04-011

PRE

Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review

PROGRESS IN NUCLEAR ENERGY

IF3.2

2024-03-0112

PRE

A comparative study on deep learning models for condition monitoring of advanced reactor piping systems

MECHANICAL SYSTEMS AND SIGNAL PROCESSING

IF8.9

2024-03-010

PRE

A review on the sizing and selection of control valves for thermal hydraulics for reactor system applications

反应堆系统应用热工液压控制阀的尺寸和选择综述

PROGRESS IN NUCLEAR ENERGY

IF3.2

2023-10-012

PRE

Integral and Separate Effects Test Facilities To Support Water Cooled Small Modular Reactors: A Review

PROGRESS IN NUCLEAR ENERGY

IF3.2

2023-06-0112

OAAI

Passive heat removal in horizontally oriented micro-HTGRs

水平定向的微型htgr中的被动除热

PROGRESS IN NUCLEAR ENERGY

IF3.2

2023-02-014

OAAI

Impact of Glass Irradiation on Laser-Induced Breakdown Spectroscopy Data Analysis

玻璃辐照对激光诱导击穿光谱数据分析的影响

SENSORS

IF3.5

2023-01-076

OAAI

Large eddy simulation of flow through an axisymmetric sudden expansion

PHYSICS OF FLUIDS

IF4.3

2022-06-075

Piyush Sabharwall

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