Thorium-based molten salt SMR as the nuclear technology pathway from a market-oriented perspective

G Zheng, H Wu, J Wang, S Chen, Y Zhang - Annals of Nuclear Energy, 2018 - Elsevier
In this paper, a market guided design approach is exercised to identify the optimal reactor
form in terms of safety, cost, fuel availability, and profitability. Various Gen IV reactor …

Study of tritium in the primary loop of HTR-10: Experiment and theoretical calculations

F **e, J Cao, X Feng, J Tong, Y Dong, Z Zhang… - Progress in Nuclear …, 2018 - Elsevier
An experimental system for the measurement of tritium in the primary loop of HTR-10 has
been established, sampling gas from the helium purification system. After the restart of HTR …

[HTML][HTML] Modeling and predicting total hydrogen adsorption in nanoporous carbon materials for advanced nuclear systems

ST Lam, R Ballinger, C Forsberg - Journal of Nuclear Materials, 2018 - Elsevier
The retention of hydrogen in a variety of disordered carbon materials including graphene
nanoplatelets and amorphous carbon was measured by volumetric adsorption and modeled …

Tritium storage and release mechanism in nuclear graphite using first-principles combined thermal desorption theory

Z Zhou, R Nie, Y Wang, J Guo, L Wei, F **e, J Cao… - Carbon, 2024 - Elsevier
Nuclear graphite (NG) is widely applied in nuclear facilities, and its strong interaction with
tritium is an essential factor for tritium transport behavior in various reactors and the …

Photocatalytic Activity of MWCNT-Reinforced MoS2 Nanosheets

Shweta, V Singh, V Singh, S Yarramaneni… - Journal of Electronic …, 2024 - Springer
Two-dimensional transition metal dichalcogenides, especially MoS2, are widely exploited
for their proficiency owing to the optimum energy band gap required for photocatalytic …

Study on tritium permeation behavior in primary and second circuits of the hydrogen production system by methane steam reforming using HTGR

R Liu, H Li, H Zhang, H Yin, T Ma - Nuclear Engineering and Design, 2024 - Elsevier
Hydrogen production by methane steam reforming (MSR) using the process heat from High-
temperature gas-cooled reactor (HTGR) is one of the most promising technology for …

[PDF][PDF] Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor

KP Dolan - 2021 - dspace.mit.edu
Advanced reactor concepts which use a lithium-or beryllium-bearing primary salt coolant will
require technical solutions to mitigate the environmental release of tritium. One such design …

Summary of tritium source term study in 10 MW high temperature gas-cooled test reactor

X Liu, W Peng, F **e, J Cao, Y Dong… - Fusion Science and …, 2020 - Taylor & Francis
Tritium (3H) has been increasingly researched when assessing the environmental impact of
nuclear reactors and other nuclear facilities because it is widely present in nuclear systems …

STUDY OF OXIDATION EFFECT ON TRITIUM ADSORPTION AT GRAPHENE ZIGZAG EDGE FROM FIRST-PRINCIPLES CALCULATIONS

Z Zhou, Y Wang, J Guo, F **e, Y Wen… - The Proceedings of the …, 2023 - jstage.jst.go.jp
Tritium is one of the most concerned nuclides in nuclear power plants because of its high
mobility and circulation in the environment. The high-temperature gas-cooled reactor …

Functional Requirements for the Modeling and Simulation of Advanced (Non-LWR) Reactor Mechanistic Source Term

S Shahbazi, D Grabaskas - 2020 - osti.gov
A number of industry vendors are leading a resurgence in advanced reactor development.
As the assurance of public safety from the accidental release of radionuclides to the …