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 …

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 …

A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing

SB Seo, R Hernandez, M O'Neal, N Meehan… - Fusion Engineering and …, 2021 - Elsevier
The development and demonstration of fusion power plant facilities require advancement of
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 …

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 …

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 …

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 …

MHD thermohydraulics analysis and supporting R&D for DCLL blanket in the FNSF

S Smolentsev, T Rhodes, G Pulugundla… - Fusion engineering and …, 2018 - Elsevier
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 …

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 …

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 …