Overview of the ITER TBM Program
LM Giancarli, M Abdou, DJ Campbell… - Fusion Engineering and …, 2012 - Elsevier
The objective of the ITER TBM Program is to provide the first experimental data on the
performance of the breeding blankets in the integrated fusion nuclear environment. Such …
performance of the breeding blankets in the integrated fusion nuclear environment. Such …
Overview of recent ITER TBM Program activities
LM Giancarli, X Bravo, S Cho, M Ferrari… - Fusion Engineering and …, 2020 - Elsevier
Abstract The ITER Test Blanket Module (TBM) Program has significantly evolved since 2018.
The number of equatorial ports allocated for operating the Test Blanket Systems (TBSs) has …
The number of equatorial ports allocated for operating the Test Blanket Systems (TBSs) has …
A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing
The development and demonstration of fusion power plant facilities require advancement of
multiphysics modeling capabilities. These capabilities provide an integrated platform for …
multiphysics modeling capabilities. These capabilities provide an integrated platform for …
Dual-coolant lead–lithium (DCLL) blanket status and R&D needs
S Smolentsev, NB Morley, MA Abdou… - Fusion Engineering and …, 2015 - Elsevier
The DCLL is an attractive breeding blanket concept that leads to a high-temperature (T∼
700° C), high thermal efficiency (η> 40%) blanket system. The key element of the concept is …
700° C), high thermal efficiency (η> 40%) blanket system. The key element of the concept is …
The European Dual Coolant Lithium Lead breeding blanket for DEMO: status and perspectives
D Rapisarda, I Fernández-Berceruelo, A García… - Nuclear …, 2021 - iopscience.iop.org
During the last years CIEMAT has been leading the activities in the European Program to
develop an integral breeding blanket with advanced performances to work in a realistic …
develop an integral breeding blanket with advanced performances to work in a realistic …
Development of the lead lithium (DCLL) blanket concept
S Malang, M Tillack, CPC Wong, N Morley… - Fusion Science and …, 2011 - Taylor & Francis
Liquid metal breeders such as Lithium or the eutectic Lead-Lithium alloy PbLi have the
potential for attractive breeding blankets, especially if the liquid metal serves as breeder and …
potential for attractive breeding blankets, especially if the liquid metal serves as breeder and …
Tritium management and safety issues in ITER and DEMO breeding blankets
B Bornschein, C Day, D Demange, T Pinna - Fusion Engineering and …, 2013 - Elsevier
Safe, reliable and efficient tritium management in the breeder blanket faces unique
technological challenges. Beside the tritium recovery efficiency in the tritium extraction and …
technological challenges. Beside the tritium recovery efficiency in the tritium extraction and …
MHD thermohydraulics analysis and supporting R&D for DCLL blanket in the FNSF
Abstract A Fusion Nuclear Science Facility (FNSF) has been recognized in the fusion
community as a necessary facility to resolve the critical technology issues of in-vessel …
community as a necessary facility to resolve the critical technology issues of in-vessel …
SiC-based sandwich material for Flow Channel Inserts in DCLL blankets: Manufacturing, characterization, corrosion tests
C Soto, C García-Rosales, J Echeberria… - Fusion engineering and …, 2017 - Elsevier
Abstract Flow Channel Inserts (FCIs) are key elements in a DCLL blanket concept for DEMO,
since they provide the required thermal insulation between the He cooled structural steel …
since they provide the required thermal insulation between the He cooled structural steel …
Damage parameters of structural materials in fusion environment compared to fission reactor irradiation
ME Sawan - Fusion Engineering and Design, 2012 - Elsevier
Calculations were performed to quantify the damage parameters in the leading candidate
structural and plasma facing materials when used in magnetic and inertial confinement …
structural and plasma facing materials when used in magnetic and inertial confinement …