Comparison of the PHISICS/RELAP5-3D ring and block model results for phase I of the OECD/NEA MHTGR-350 benchmark

G Strydom, AS Epiney, A Alfonsi, C Rabiti - Nuclear Technology, 2016 - Taylor & Francis
Abstract The Parallel and Highly Innovative Simulation for INL Code System (PHISICS) has
been under development at Idaho National Laboratory since 2010. It consists of several …

Assessment of reactor physics characteristics of prismatic fuel concepts with a hydrogen-based moderator for use in a fluoride salt-cooled small modular reactor

HV Yan, BP Bromley - Journal of Nuclear …, 2024 - asmedigitalcollection.asme.org
Fluoride-salt-cooled high temperature reactor (FHR) effectively combines the solid fuel and
moderator design of high-temperature gas-cooled reactor (HTGR) technology with the …

Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE

F Bostelmann, G Strydom - Annals of Nuclear Energy, 2017 - Elsevier
Abstract The Very High Temperature Critical Assembly (VHTRC) experiment represents one
of the few data sets available for the validation of HTGR lattice physics. Within the framework …

[책][B] A hybrid coarse and fine mesh solution method for prismatic high temperature gas-cooled reactor thermal-fluid analysis

ID Clifford - 2013 - search.proquest.com
Evaluations of the fluid flow and heat transfer in prismatic high temperature gas-cooled
reactors (HTGRs) are critical to ensuring the safety of designs. It is in this area that many …

Criticality calculations of the very high temperature reactor critical assembly benchmark with serpent and SCALE/KENO-VI

F Bostelmann, HR Hammer, J Ortensi, G Strydom… - Annals of Nuclear …, 2016 - Elsevier
Within the framework of the IAEA Coordinated Research Project on HTGR Uncertainty
Analysis in Modeling, criticality calculations of the Very High Temperature Critical Assembly …

Modeling of a Generic Pebble Bed High-temperature Gas-cooled Reactor (PB-HTGR) with SAM

ZJ Ooi, L Zou, T Hua, J Fang, R Hu - 2022 - osti.gov
This report presents the modeling of the core of a generic pebble-bed reactor (PBR) at the
system level using the System Analysis Module (SAM) code. This work is an extension of a …

The IAEA CRP on HTGR uncertainties: Sensitivity study of PHISICS/RELAP5-3D MHTGR-350 core calculations using various SCALE/NEWT cross-section sets for Ex …

P Rouxelin, G Strydom, A Alfonsi, K Ivanov - Nuclear Engineering and …, 2018 - Elsevier
Uncertainty and sensitivity analysis is an indispensable element of any substantial attempt in
reactor simulation validation. A Coordinated Research Program (CRP) supervised by the …

[책][B] Extension of the Reactor Dynamics Code MGT-3D for Pebblebed and Blocktype High-Temperature-Reactors

D Shi - 2015 - juser.fz-juelich.de
The High Temperature Gas cooled Reactor (HTGR) is an improved, gas cooled nuclear
reactor. It was chosen as one of the candidates of generation IV nuclearplants [1]. The …

A multi-scale homogenization and reconstruction approach for solid material temperature calculations in prismatic high temperature reactor cores

I Clifford, KN Ivanov, MN Avramova - Nuclear Engineering and Design, 2013 - Elsevier
Traditional full-core heat transfer analysis of high temperature reactors uses effective coarse
mesh parameters that are typically derived from a priori analysis and/or simplified analytical …

Development of effective thermal conductivity models for Reserve Shutdown Control fuel block of prismatic HTGR for hydrogen production

DH Shin, SJ Yoon, HK Cho, GC Park, T Kim - International Journal of …, 2017 - Elsevier
A hydrogen production system coupled to High Temperature Gas-cooled nuclear Reactor
(HTGR) is considered to be one of the most promising ways for massive hydrogen …