ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
July 2026
Nuclear Technology
June 2026
Fusion Science and Technology
May 2026
Latest News
Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
Yasunori Iwai, Toshihiko Yamanishi, Akihiro Hiroki, Masao Tamada
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 163-167
Tritium, Safety, and Environment | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8895
Articles are hosted by Taylor and Francis Online.
The combined electrolysis and catalytic exchange process has been selected for the water detritiation system for the ITER. In the front-end process of tritiated water electrolyzer composed of a solid polymer electrode, ion exchange resin beds are installed for processing effluent ions in the enriched tritiated water from the catalytic exchange column to avoid the deterioration of the solid polymer electrode. The tritium concentration in the circulation resin bed is evaluated to reach 1.09x1015Bq/m3. It is thus important to note the radiation-induced degradation in ion exchange resins. We studied the degradation effects in Amberlite[registered] and Diaion[registered] organic ion exchange resins caused by the irradiation with electron beam up to the integrated dose of 1500kGy. The procedures D2187-94 of the American Society for Testing and Materials were adopted for the evaluation of the water retention capacity, the backwashed and settled density, the salt splitting capacity, and the total exchange capacity of particulate ion exchange resins. A 20% decrease of total exchange capacity of the cation exchange resin, when irradiated up to 1500 kGy at room temperature, has been observed.