Based on results of tritium measurement in the SS316 specimens irradiated up to 5.9 dpa in the SINQ target (580MeV proton) using a thermal desorption (TDS) method, trap site density and trap energy in the materials induced by the high-energy proton irradiation have been evaluated by means of the numerical tritium transport analysis. The results indicate that almost residual tritium in the SS316...

for the KATRIN Collaboration Abstract KATRIN is a very large scale tritium-beta-decay experiment to determine the mass of the neutrino. It is presently under construction at the Karlsruhe Institute of Technology north campus, and makes use of the Karlsruhe Tritium Laboratory built as a prototype for the ITER project. The combination of a large retarding-potential electrostatic-magnetic spectrom...

Tritium is a radioactive form of hydrogen and is a by-product of energy production in Canadian Deuterium Uranium (CANDU) reactors. The release of this radioisotope into the environment is carefully managed at CANDU facilities in order to minimize radiation exposure to the public. However, under some circumstances, small accidental releases to the environment can occur. The radiation doses to hu...

Removing tritium produced by D-D fusion and recycling part of it after it decays to He-3 significantly reduces the fraction of fusion energy carried by neutrons in a D-D system. For a catalyzed D-D system (no tritium removal), the peak dpa rate in candidate structural materials is 25-35% lower than that in an equivalent D-T system with the same fusion power wall loading. The gas production and ...

In this paper the problem of tritium transport in PbLi (Lead-Lithium) blankets has been studied and analyzed by means of our recently developed computational models. Several simulations are performed by incorporating the geometric configurations of the PbLi blankets including both DCLL (Dual Coolant Lead Lithium) and HCLL (Helium Cooled Lead Lithium) blankets. Tritium permeation loss percentage...

The release of crude tritium gas from neutron-irradiated LiAI alloy, and the following purification and the trapping of the gas have been preliminary studied to obtain information necessary for the development of tritium technology. The percentages of the fractions of H2(T) and H20(T) occupying about 99% among gaseous species(T) released were largely influenced by pre-irradiation treatment of t...

A power plant design based on the spherical torus (ST) concept has been developed by the ARIES team. This paper documents the results of the nuclear and radiation protection analyses carried out for the ARIES-ST design. The nuclear analysis addresses the key neutronics issues, such as the neutron wall loading profile, radiation damage to structural components and their lifetimes, tritium breedi...

When dl-1 ,2-propanediol-l-3H is converted to propionaldehyde in the presence of dioldehydrase and cobamide coenzyme, tritium is transferred to the coenzyme. The tritiated coenzyme so obtained transfers tritium to the reaction product when reacted with dl-1,2-propanediol and apoenzyme. The coenzyme is tritiated exclusively at the C-5’ position of the adenosyl moiety. The location of tritium was...

Abstract As a key component of the Chinese Fusion Engineering and Test Reactor (CFETR), blanket is responsible for tritium breeding, neutron shielding energy conversion. Blankets can be classified into solid liquidaccording to form breeder. Among them, utilizes pebble beds as both breeder multiplier, it has been popular scheme due its advantages, such good material compatibility non-magnetohydr...