Graphite dust is the important contents of source term for safety analysis of high temperature
gas-cooled reactors (HTGR). The spherical fuel element circulation in a pebble bed reactor …

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 …

Presence of radioactive dust, and also potential for its release, are considered important
issues as regards the safety of high temperature gas cooled reactors, especially the pebble …

With previously developed experimental methods which include the preparation and
measurement process for the graphite sample, two new irradiated graphite spheres with …

Abstract The Very High Temperature Reactor (VHTR) is one of the six proposed Generation
IV reactor concepts. The HTR-10, a 10 MW high temperature gas-cooled reactor was a …

An irradiated graphite sphere of the 10 MW high temperature gas-cooled reactor (HTR-10)
has been studied experimentally with a mechanical disintegration way and a suite of …

The radioactive dust in the primary loop of high-temperature gas-cooled reactors (HTGRs) is
one of the key challenges to operational safety, particularly in the event of depressurization …

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 …

The very high temperature reactor (VHTR) is a development of the high-temperature gas-
cooled reactors (HTGRs) and one of the six proposed Generation IV reactor concept …

The process and effluent radiation monitoring system can provide information about kinds of
the radionuclide and activity concentrations, which is indispensable, important, and peculiar …