Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
-ray irradiation on zirconium in nitric acid solutionIshijima, Yasuhiro; Ueno, Fumiyoshi; Abe, Hitoshi; Sakai, Junichi*; Nojima, Yasuo*; Hashikura, Yasuaki*
no journal, ,
Besause of good corrosion resistance in boiling nitric acid solution, some equipment in the nuclear fuel reprocessing plant has been made of zirconium (Zr). However, it is well known that Zr has susceptibility of hydrogen embrittleent by hydride formation. To evaluate radiolitic hydrogen absorption behavior, radiolytic hydrogen absorption tests and constant load tensile tests under -ray irradiation were carried out. From test results, the maximum value of absorbed hydrogen was 250 wppm. On the other hand, Zr did not failure in constant load tensile test under -ray irradiation until 1000 hr. These results shows that, Zr can absorb radiolytic hydrogen but hydride generation rate into the metal is very slow. And it is considered that it is improtant to evaluate hydride generation behavior under plant operation environment.
-ray irradiationIshijima, Yasuhiro; Ueno, Fumiyoshi
no journal, ,
Explosion-bonded metal joint has been used at the spent nuclear fuel reprocessing plant in Japan. The metal joint is made of zirconium, tantalum and stainless steel. And the radiolytic hydrogen is known to be generated in the spent nuclear fuel solution. Also, tantalum is known to be highly susceptible to hydrogen embrittlement. Therefore, evaluating the radiolytic hydrogen absorption behavior of Tantalum in nitric acid solution (HNO
) is essential. In this study, immersion tests were conducted on tantalum in nitric acid solutions under -ray irradiation to evaluate its radiolytic hydrogen absorption behavior. Results showed that there was no hydrogen absorption of tantalum after immersion. The reason was considered that the passive film generated by immersion in nitric acid solution inhibited hydrogen absorption.
-ray irradiation in nitric acid solutionIshijima, Yasuhiro; Ueno, Fumiyoshi; Abe, Hitoshi
no journal, ,
Explosion-bonded metal joint has been used at the spent nuclear fuel reprocessing plant in Japan. The metal joint is made of zirconium, tantalum and R-SUS304ULC. And the radiolytic hydrogen is known to be generated in the spent nuclear fuel solution. Also, tantalum is known to be highly susceptible to hydrogen embrittlement. Therefore, evaluating the radiolytic hydrogen absorption behavior of metal joint in nitric acid solution (HNO) is essential. In this study, immersion tests were conducted on tantalum in nitric acid solutions under -ray irradiation to evaluate its radiolytic hydrogen adsorption behavior. Results showed that the radiolytic hydrogen absorbed in zirconium near the Zr/Ta interface. But, hydrogen embrittlement was not observed in tensile test under -ray irradiation. The reason was considered that the radiolytic hydrogen was trapped at the surface of the zirconium as hydride.