Bile Duct Carcinoma in Association with a Choledochal Cyst : Report of a Case

A case of bile duct carcinoma associated with a pre-existing type I-A choledochal cyst is reported here. A 38-year-old man who had received a Roux-en-Y hepaticojejunostomy for a cyst of the common bile duct 11 years earlier was revealed to have metastatic carcinoma in the lungs. The primary site of the carcinoma was clinically undetermined, but was found by autopsy to be in the bile duct. Although the relation between these two lesions was unclear, circumstantial evidence suggested that they were related to each other. A persistent chronic inflammatory irritation in this area was considered to be responsible for development of the tumor

Onycholysis Associated with Graves\u27 Disease

This paper presents a case of onycholysis associated with Graves\u27 disease. Onycholysis in association with Graves\u27 disease is rarely seen in Japan. The patient is a twenty-two-year-old female with a half year history of receiving antithyroid treatment for Graves\u27 disease. An initial physical examination revealed onycholysis in the right ring finger, although she achieved euthyroid state

The influence of the long-term heating under H2 atmosphere on the tritium release behavior from the neutron-irradiated Li2TiO3

Solid tritium breeding materials are expected to be used in high-temperature conditions for a long time in a fusion DEMO reactor. Thus, it is important to understand how bred tritium releases from the long-term heated material under the environment as close to a DEMO condition as possible to establish a tritium fuel cycle and keep it safe. In this work, the tritium release behavior from the irradiated Li2TiO3 pebbles that was preheated for 720 h at most was observed by heating at 1000 °C under 1000 Pa H2/Ar gas flow. The release peaks of HTO and HT were observed around 300 °C due to the desorption of the chemisorbed water. Also, the broad HTO peak was observed in a higher temperature region despite purging H2/Ar gas. This result suggests that this tritium was released without exchanging with H2 but with combining with oxygen in the pebbles. Moreover, the released tritium amount decreased as the pre-heating time. Finally, the amount of tritium that could not be released by the heating experiment was quantified by dissolving samples with an acid solution. Besides, the total tritium release ratio was discussed

Li mass loss and structure change due to long time heating in hydrogen atmosphere from Li2TiO3 with excess Li

Solid tritium breeding materials are used in a high temperature condition for a long time in a fusion reactor blanket. It is expected that a certain amount of Li will be evaporated and the pebble structure will be changed. Understanding of Li mass transfer behavior in the blanket is an important issue from viewpoints of establishment of tritium cycle and tritium safety. In this work the pebbles of Li2TiO3 with excess Li were heated at 900 °C in 1000 Pa H2/Ar flow for a long time (72, 240, 720, 1200 h). The amount of Li mass loss under the hydrogen atmosphere was 0.665 wt% which was less than that under the water vapor atmosphere observed in the previous study. No significant Li mass loss was observed after 240 h. By heating for 240 h, the grain diameter increased from 1.8 to 3.1 μm and the specific surface area decreased from 0.72 to 0.20 m2/g. After 240 h, no significant grain growth and no significant decrease in the specific surface area were observed. From these results, it seems that there is a relation between Li mass loss and grain growth

Influence of Lithium Mass Transfer on Tritium Behavior in Pebbles of Li2TiO3 with Excess Lithium

Tritium breeding ceramic materials are placed at high temperatures for a long period in a fusion DEMO reactor. Therefore, the understanding of Li mass loss phenomena and its influence on tritium behavior are important. In this study, the pebbles of Li2TiO3 with excess Li were heated at 900 °C for 30 days in a 1000 Pa H2/Ar flow and tritium sorption and recovery experiments were carried out. Li mass loss by the heating was evaluated to be 0.7 wt%. The value of Li mass loss was almost same as that for 3 days heating at the same condition. Tritium sorption capacity for the heated pebbles at 600 °C and 900 °C were almost same as that for the pebbles as received. Tritium sorbed in the pebbles could not be recovered effectively by the 1000 Pa H2/Ar purge at room temperature and 300 °C but it could be recovered at 600 °C and 900 °C. The influence of the long-time heating on the behavior of tritium sorbed in the pebbles was not large