Review of the research on the scrubbing of fission products in liquid metal pool

G Jiang, M Wang, K Wang, S Cheng - Nuclear Engineering and Design, 2024 - Elsevier
In recent times, the risk assessment and design optimization of advanced fourth-generation
nuclear reactors have garnered significant global scholarly attention. Specifically …

Experimental study of SRT scrubbing model in water coolant pool

KF Becker, MH Anderson - Nuclear Engineering and Design, 2021 - Elsevier
In pool-type nuclear reactors, a postulated fuel pin failure can result in the release of fission
products into the coolant pool. While the coolant pool itself tends to scrub the majority of …

[PDF][PDF] Development of the Simplified Radionuclide Transport (SRT) Code Version 2.0 for Versatile Test Reactor (VTR) Mechanistic Source Term Calculation

D Grabaskas, M Bucknor… - Proceedings of the 2022 …, 2022 - conferences.iaea.org
Abstract The Versatile Test Reactor (VTR) is a fast spectrum test reactor currently being
developed in the United States under the direction of the US Department of Energy …

[PDF][PDF] Survey and Assessment of Computational Capabilities for Advanced (non-LWR) Reactor Mechanistic Source Term Analysis

S Shahbazi, D Grabaskas, S Thomas, N Andrews… - 2020 - osti.gov
A vital part of the licensing process for advanced (non-LWR) nuclear reactor developers in
the United States is the assessment of the reactor's source term, ie, the potential release of …

[PDF][PDF] The Release of the Simplified Radionuclide Transport (SRT) Code Version 2.1

T Starkus, DH Kam, S Shahbazi, D Grabaskas… - 2024 - osti.gov
Reactor licensing centers on the protection of the public and environment from the
inadvertent release of radioactive material. Therefore, mechanistic source term analysis, or …

Utilization of the LMP Methodology in Support of the VTR Conceptual Safety Design Report

D Grabaskas, B Chen, M Bucknor, J Li, D Henneke… - 2022 - osti.gov
The Versatile Test Reactor (VTR) is a fast spectrum test reactor currently being developed in
the United States under the direction of the US Department of Energy (DOE), Office of …

[DOC][DOC] FAST REACTOR SOURCE TERM MODELING AND SIMULATION FUNCTIONAL REQUIREMENTS AND GAP ASSESSMENT

S SHAHBAZI - conferences.iaea.org
A vital part of the licensing process for advanced (non-LWR) nuclear reactor developers in
the United States is the assessment of the reactor's source term. The source term represents …

Risk-Informed Mechanistic Source Term Calculation (Final CRADA Report)

D Grabaskas, M Bucknor, Y Yu, E Merzari, M Billone… - 2019 - osti.gov
As part of an FY18 US Department of Energy (DOE) Gateway for Accelerated Innovation in
Nuclear (GAIN) award, a CRADA agreement was established between Argonne National …