The paper presents some numerical tests for the temperature development around nuclear waste packages stored in vaults. We deal with two simplified models. In the first of them, a single long cylinder of the diameter 1 m is considered. It is filled with radioactive waste and surrounded by rock. The second model presents a long cuboidal package stored in a vault. The computation was carried out ...

Regulations and guidelines for radionuclide waste disposal require detailed information about the characteristics of radioactive waste drums prior to transport to the disposal sites. So it is important to know the accurate radionuclide inventory of radioactive waste. However, estimation of radionuclide concentrations in the drummed radioactive waste is difficult and unreliable. In order to over...

The Paul Scherrer Institut (PSI) is the largest national research centre in Switzerland. Its multidisciplinary research is dedicated to a wide field in natural science and technology as well as particle physics. In this context, PSI is operating, amongst others, a large proton accelerator facility since more than 30 years. In two cyclotrons, protons are accelerated to high speeds and then guide...

Radioactive waste disposal is a very important issue when constructing sustainable society with nuclear energy. To construct facilities, cementitious materials are used for various purposes, such as structural elements, storage cells, tunnel plugs and engineered barriers. This technical report describes the history current status of low-level radioactive (LLW) in Japan, particularly near surfac...

Treatment and disposal of waste radioactive ion exchange resins is one of the most urgent problems for nuclear industries in China. Cement solidification technology has many advantages, such as requiring simple equipment, easy scaling-up, low working temperature, no trouble of gas cleaning and low cost. It is a suitable technology for treatment of waste radioactive resins, and has been widely u...

Abstract Molybdenum-99 ( 99 Mo) is a parent radioisotope of Technetium-99m 99m Tc) widely used in nuclear diagnostics. The production this by PT. INUKI generated radioactive fission waste (RFW) that theoretically contains 239 Pu and 235 U, posing proliferation risk. This paper discusses the determination radionuclides inventory RFW proposed strategy for its management. was calculated using ORIG...

To assess the safety for disposal of radioactive waste-cement composition, the leaching of Co from a waste composite into a surrounding fluid has been studied. Leaching tests were carried out in accordance with a method recommended by IAEA. Determination of retardation factors, KF and coefficients of distribution, kd, using a simplified mathematical model for analyzing the migration of radionuc...

The GEOTHER/VT4 computer code is an improved version of the GEOTHER computer code. The GEOTHER/VT4 code was applied to a two-dimensional simulation of a waste package in a high-level waste repository to predict the thermal-hydraulic environment where steam formation may occur. The thermal-hydraulic environment is important for assessing waste package container corrosion and packing material swe...