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P

Palash Kumar Bhowmik

seoul national university

H指数:17

被引数:693

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Evaluating thermal-hydraulic energy conversion of water-cooled small modular reactors: Supporting design changes and customer needs

评估水冷小型模块化反应堆的热-水力能量转换：支持设计变更和客户需求

Nuclear Engineering and Design

IF2.1

2026-05-010

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

Impact of surface and physical property on multiphase flow in sealed vessel: Liquid dropdown performance

密封容器中多相流受表面和物理性质影响：液体下落性能

EXPERIMENTAL AND COMPUTATIONAL MULTIPHASE FLOW

IF5.4

2025-05-270

PRE

Porous media model simulates thermal-hydraulics of nuclear research reactors with flat and curved plate fuel assembly

INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER

IF6.4

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 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

Film condensation with high heat fluxes and scaled experiments using pure steam for reactor containment cooling

具有高热通量的薄膜冷凝和使用纯蒸汽进行反应堆安全壳冷却的规模化实验

APPLIED THERMAL ENGINEERING

IF6.9

2023-07-011

OAAI

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

State-of-the-art and review of condensation heat transfer for small modular reactor passive safety: Experimental studies

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

IF5.8

2022-08-0121

OAAI

Multicomponent gas mixture parametric CFD study of condensation heat transfer in small modular reactor system safety

EXPERIMENTAL AND COMPUTATIONAL MULTIPHASE FLOW

IF5.4

2022-05-0426

PRE

Convective heat transfer and friction factor characteristics of helical strip inserted annuli at turbulent flow

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

IF5.8

2021-09-0121

PREAI

CFD validation of condensation heat transfer in scaled-down small modular reactor applications, Part 1: Pure steam

EXPERIMENTAL AND COMPUTATIONAL MULTIPHASE FLOW

IF5.4

2021-08-268

PRE

Thermohydraulic performance of water mixed Al2O3, TiO2 and graphene-oxide nanoparticles for nuclear fuel triangular subchannel

THERMAL SCIENCE AND ENGINEERING PROGRESS

IF5.4

2021-08-0115

PREAI

CFD validation of condensation heat transfer in scaled-down small modular reactor applications, Part 2: Steam and non-conaensable gas

EXPERIMENTAL AND COMPUTATIONAL MULTIPHASE FLOW

IF5.4

2021-07-219

OAAI

Computational assessment of thermo-hydraulic performance of Al2O3-water nanofluid in hexagonal rod-bundles subchannel

PROGRESS IN NUCLEAR ENERGY

IF3.2

2021-05-0119

PREAI

CFD validation with optimized mesh using benchmarking data of pebble-bed high-temperature reactor

使用卵石床高温反应器的基准数据对优化网格进行CFD验证

PROGRESS IN NUCLEAR ENERGY

IF3.2

2021-04-0117

PRE