Palash Kumar Bhowmik

Dr. Palash Kumar Bhowmik

Irradiation Experiment Thermal Hydraulics Analysis Department, Idaho National Laboratory, Idaho Falls, ID 83415, USA
orcid

Research Focus & Metrics

Academic Career Length

4Years (2023-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

View All Publications
22 December 2023 in Progress in Nuclear Energy
Verified
Journal Article
Closed access
HAHossam H. Abdellatif
Hossam H. Abdellatif
Palash Kumar BhowmikPalash Kumar Bhowmik
Palash Kumar Bhowmik
DADavid Arcilesi
David Arcilesi
PSPiyush Sabharwall
Piyush Sabharwall

2 May 2023 in Progress in Nuclear Energy
Verified
Journal Article
Closed access
Palash Kumar BhowmikPalash Kumar Bhowmik
Palash Kumar Bhowmik
CPCarlos E. Estrada Perez
Carlos E. Estrada Perez
JFJoshua D. Fishler
Joshua D. Fishler
SPSilvino A. Balderrama Prieto
Silvino A. Balderrama Prieto
IRIsaac D. Reichow
Isaac D. Reichow
JOJames E. O'BRien
James E. O'BRien

21 January 2025 in Nuclear Engineering and Design
Verified
Journal Article
Closed access
Palash Kumar BhowmikPalash Kumar Bhowmik
Palash Kumar Bhowmik
DCDebasish Chowdhury
Debasish Chowdhury
HAHossam H. Abdellatif
Hossam H. Abdellatif
SWScott Wahlquist
Scott Wahlquist
SKSunil Kumar
Sunil Kumar
PSPiyush Sabharwall
Piyush Sabharwall

18 January 2024
Verified
Book Chapter
Closed access
JSJoshua P. Schlegel
Joshua P. Schlegel
Palash Kumar BhowmikPalash Kumar Bhowmik
Palash Kumar Bhowmik

21 December 2023 in Processes
Verified
Journal Article
Open access
PDF file
Palash Kumar BhowmikPalash Kumar Bhowmik
Palash Kumar Bhowmik
PSPiyush Sabharwall
Piyush Sabharwall
This study covers the critical concerns related to the sizing, selection, installation, maintenance, and testing of pressure safety valves (PSVs). The aim is to ensure the safety of pressurized systems, hydrostatic transmission systems, and hydraulic plants, including process plants, thermal power plants, and nuclear reactor systems. PSVs are devices that ensure the safety and reliability of pressurized vessels, lines, and systems during overpressure events. The task of selecting which PSV features are of greatest value for a specific purpose is complex—especially in the design of a high-pressure experimental thermal–hydraulic facility for hydrostatic and transient testing of the reactor system—when the systems are in the design and development phases and require qualification and demonstration to prove that they have reached a given level of technological readiness. The present study highlights the required steps for users to follow the associated rules, guidelines, and recommendations. As a part of this research, case studies are presented to help readers better understand the applicable strategy and standards. A discussion and a review of PSV performance degradation and failure are summarized to provide a better understanding of varied process applications and conditions, including fluid flow dynamics, boundary-layer formation and pressure drops, gas bubble formation and collapse, geometric configurations, inlet/outlet piping, abrupt pressure fluctuations, and acoustic resonance. Moreover, this study discusses the servicing and testing of PSVs in a multiphase pressurized system. Overall, it provides a basic overview of how PSVs ensure the safety of pressurized systems, supported by case studies and industrial practices.

12 September 2023 in Progress in Nuclear Energy
Verified
Journal Article
Closed access
Palash Kumar BhowmikPalash Kumar Bhowmik
Palash Kumar Bhowmik
JSJubair A. Shamim
Jubair A. Shamim
PSPiyush Sabharwall
Piyush Sabharwall