Nuclear Materials and Energy

Title Publication Date Language Citations
Spectroscopic investigations of divertor detachment in TCV2017/08/01English41
IFMIF, the European–Japanese efforts under the Broader Approach agreement towards a Li(d,xn) neutron source: Current status and future options2016/12/01English40
Recent advances towards a lithium vapor box divertor2017/08/01English40
Suppression of tungsten accumulation during ELMy H-mode by lower hybrid wave heating in the EAST tokamak2017/08/01English39
Studies of dust from JET with the ITER-Like Wall: Composition and internal structure2017/08/01English39
Beryllium global erosion and deposition at JET-ILW simulated with ERO2.02019/01/01English38
Improvement of reduced activation 9%Cr steels by ausforming2016/01/01English38
A growth/annealing equilibrium model for helium-induced nanostructure with application to ITER2019/05/01English37
Impact of wall materials and seeding gases on the pedestal and on core plasma performance2017/08/01English36
Detachment evolution on the TCV tokamak2017/08/01English36
Improved pseudo-ductile behavior of powder metallurgical tungsten short fiber-reinforced tungsten (W/W)2018/05/01English35
Influence of the presence of deuterium on displacement damage in tungsten2018/12/01English35
Pebble fabrication of super advanced tritium breeders using a solid solution of Li 2+ x TiO 3+ y with Li 2 ZrO 32016/12/01English34
Real-time wall conditioning by controlled injection of boron and boron nitride powder in full tungsten wall ASDEX Upgrade2019/05/01English34
Retention in tungsten resulting from extremely high fluence plasma exposure2016/12/01English34
Power handling of a liquid-metal based CPS structure under high steady-state heat and particle fluxes2017/08/01English34
Effect of Cr/Al contents on the 475 º C age-hardening in oxide dispersion strengthened ferritic steels2016/12/01English34
Deuterium retention in tin (Sn) and lithium–tin (Li–Sn) samples exposed to ISTTOK plasmas2017/08/01English32
Deuterium retention in W and W-Re alloy irradiated with high energy Fe and W ions: Effects of irradiation temperature2016/12/01English32
Precipitation of carbides in F82H steels and its impact on mechanical strength2016/12/01English31
Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency2019/01/01English30
Role of molecular effects in divertor plasma recombination2017/08/01English30
Determination of deuterium depth profiles in fusion-relevant wall materials by nanosecond LIBS2017/08/01English29
Oxidation resistance of bulk plasma-facing tungsten alloys2018/05/01English29
Crystallization and deuterium permeation behaviors of yttrium oxide coating prepared by metal organic decomposition2016/12/01English29
Ion orbit modelling of ELM heat loads on ITER divertor vertical targets2017/08/01English29
ODS-materials for high temperature applications in advanced nuclear systems2016/12/01English29
Simulation of neutron irradiation damage in tungsten using higher energy protons2016/12/01English28
Comparing N versus Ne as divertor radiators in ASDEX-upgrade and ITER2019/05/01English28
Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data2017/08/01English28