Tritium Disposal Research Articles

Overview of Advanced Liquid Process System: Circulation of tritiated water in oceanic environment

The recent Japanese disposal of Advanced Liquid Processing System (ALPS)-treated water is controversial. ALPS does not filter tritium. The objectives of this paper are (a) to examine how anthropogenic tritium triggers biological health impacts and (b) to review the circulation of tritiated water into the oceanic territory of the Republic of Korea. I reviewed the possibility of the bioaccumulation of tritium in the oceanic environment and its overall health impact. To be of significant status, they require complex conditions. I also reviewed the simulation of the possible path that disposed pollutants will take from Fukushima. The simulation was then compared with the measured level of radionuclides around the Republic of Korea's oceanic territory by year. The data is divided into three parts (east, west, and south) and analyzed to check if the trends show any patterns in the level of tritium in the Republic of Korea. The levels checked in three areas showed a partial uniformity, which may be evidence that radionuclides entered the oceanic territory of the Republic of Korea. However, the level of tritium was extremely low compared to the regulations set by the World Health Organization and the Republic of Korea. Thus, the disposal of tritium will be less likely to affect the natural environment. Nevertheless, it is recommended to monitor disposed tritium by a third party, plan for compensation, and conduct intense research on the circulation of tritium to support the prevention of sudden failure of the emission system.

Progress and prospects on tritium safety for fusion energy

<p indent=0mm>Tritium safety is a key safety issue for a fusion reactor, and it is one of the most important problems that should be solved before the construction of a fusion reactor. Progress of tritium safety research including tritium distribution in fusion reactors, tritium confinement, tritium disposal, tritium-induced environmental problems, and human radiation effects, has been discussed in this article. Considering the roadmap of fusion energy development via magnetic confinement, we also propose the roadmap for tritium safety. Key issues related to science, technology, and also engineering are also suggested.

Development of plant concept related to tritium handling in the water-cooling system for JA DEMO

The conceptual design of Japan’s fusion demonstration plant (JA DEMO) is now being developed. In this paper, an overall plant system concept related to tritium handling in the water-cooling system is developed to give a concrete shape to the present JA DEMO concept as an electric power plant. The basic condition of tritium permeation from the in-vessel components to the primary cooling system is evaluated to be 5.7 g-T/day. The tritium concentration of the primary coolant is assumed to be 1 TBq/kg similar to the heavy water reactor condition. The capacity of the water detritiation system (WDS) is assessed, and the bypass feed water from the primary cooling loop is evaluated to be 94 kg/h under the tritium extraction efficiency of 0.96. Based on those specific parameters, the existing WDS in the heavy water reactor is found to be applicable to that of JA DEMO. Configuration of the primary heat transfer system (PHTS) is also discussed. Based on the heavy water reactor experience, tritium permeation through a steam generator (SG) to the secondary cooling system in PHTS is evaluated at 11.77TBq/year/loop (318 Ci/year/loop), which is found to be less than the restricted amount of tritium disposal for a pressurized water reactor in Japan. The key effect of the heavy water reactor experience is reduction of tritium permeation by oxide layer formed on SG pipes. Finally, a confinement concept of tritium release from PHTS is discussed under the condition of ex-vessel loss of coolant accident (LOCA). A pressure suppression system is installed to prevent the upper tokamak hall from pressurizing at the ex-vessel LOCA, and the tritium leakage from the upper tokamak hall is consequently restrained. The resultant early public dose at the plant site boundary can be reduced to 1.8 mSv, which is negligibly smaller than 100 mSv of the no-evacuation limit recommended by IAEA.

Rodents as receptor species at a tritium disposal site

New methods are being employed on the Department of Energy's Savannah River Site to deal with the disposal of tritium, including the irrigation of a hardwood/pine forest with tritiated water from an intercepted contaminant plume to reduce concentrations of tritium outcropping into Fourmile Branch, a tributary of the Savannah River. The use of this system has proven to be an effective means of tritium disposal. To evaluate the impact of this activity on terrestrial biota, rodent species were captured on the tritium disposal site and a control site during two trapping seasons in order to assess tritium exposure resulting from the forest irrigation. Control site mice had background levels of tritium, 0.02 Bq/mL, with disposal site mice having significantly higher tritium concentrations, mean = 34.86 Bq/mL. Whole body tritium concentrations of the mice captured at the disposal site were positively correlated with tritium application and negatively correlated with precipitation at the site.

System Design for Disposal of Tritium at TFTR

The Tokamak Fusion Test Reactor (TFTR) has cleanup systems which convert tritium gas to the oxide form and absorb it on molecular sieve beds. These beds are regenerated by transferring their moistu...

Treatment and disposal of tritium containing waste at mound

First generation fusion machines will burn the hydrogen isotopes deuterium and tritium as fuel. Tritium, which is radioactive, must be handled carefully and any byproducts must be disposed of as radioactive waste. Tritiated waste will fall into one of three categories: gaseous, liquid, or solid. Sources and expected quantities of tritiated waste that are likely to be generated by a fusion machine will be discussed. Strategies, options and processes for dealing with tritium containing wastes will also be presented. Final disposition of each category of tritium contaminated waste is governed by regulations and guidelines. These regulations and guidelines, and how they might apply to a fusion reactor facility, will be outlined.