Results 101 to 110 of about 9,941 (218)
Release of fission tritium through Zircaloy-4 fuel cladding tubes
In order to analyse a potential fission tritium migration from the fuel to the coolant trough the cladding, two experiments of effusion and permeation types, have been performed on H-3 release from Zry4 claddings. During the tests at 350 degrees C, the 3
Ducros, G +3 more
core
Specific activity models (SA) are often used to estimate tritium concentration in the plants for chronic-release of atmospheric HTO in some regulatory models by some countries and commissions.
Hui-fang, SHEN +3 more
core +1 more source
Tritium retention and release analysis for US-ITER blanket
The US design for the ITER tritium-breeding blanket consists of layers of Be multiplier, stainless steel cladding, and Li{sub 2}O ceramic breeder. Tritium is recovered from the ceramic breeder by purging it with He + 0.2% H{sub 2}.
Attaya, H. +3 more
core
Studies of irradiated two-phase lithium ceramics Li4SiO4/Li2TiO3 by thermal desorption spectroscopy
Two-phase ceramics Li2TiO3-Li4SiO4 are one of the potentially promising materials for creating a ceramic blanket for DEMO reactor. However, until now, a limited number of studies have been carried out on the release of tritium from this material under ...
Yevgen Chikhray +12 more
doaj +1 more source
Tritium content in water bodies in regions of peaceful nuclear explosions
Sites of peaceful nuclear explosions pose a potential radiation hazard to the territories of the Russian Federation, primarily due to the possible release of radioactivity from the explosion cavity into aquifers and onto the earth's surface.
V. S. Repin +5 more
doaj +1 more source
Tritium inventory prediction in a CANDU plant
The flow of tritium in a CANDU nuclear power plant was modeled to predict tritium activity build-up. Predictions were generally in good agreement with field measurements for the period 1983-1994.
M.J. Song +5 more
core +1 more source
BEATRIX-II: In situ tritium test [PDF]
The BEATRIX-II irradiation experiment is an in-situ tritium release experiment being carried out in the Fast Flux Test Facility (FFTF) reactor to evaluate the tritium release characteristics of fusion solid breeder materials.
Baker, D.E. (Westinghouse Hanford Co., Richland, WA (USA)) +3 more
core
Effect of heat treatment of titanium beryllide on tritium/hydrogen release
In the present paper, a homogenization heat treatment at 1473 K for 8 h was carried out with the aim to obtain the single-phase Be12Ti structure in the pebbles of three Be-Ti compositions: Be-7.0Ti, Be-7.3Ti, Be-7.7Ti at.%.
Chakin, V. +15 more
core +1 more source
Release of tritium from tritiated paints
A study of the tritium losses from five tritiated phosphor paints showed that the losses from these paints were generally low. Samples of five different paints which were leach tested six times over a period of 11 months had losses ranging from 0.018 to 0.731% of the initial activity in the samples. Tritium evolved from a paint which had been cured for
openaire +2 more sources
The Impact of Tritium in the Environment
Tritium is a radioisotope that is extremely mobile in the biosphere and that can be transferred to the environment and to humans mainly via tritium oxide or tritiated water.
Viktor Dolin +3 more
doaj +1 more source

