Abstract
One fuel pin filled with hyperstoichiometric uranium-plutonium mixed carbide pellets was encapsulated in 87F-2A and irradiated in JMTR up to 4.4 %FIMA at an average linear power of 60 kW/m. The capsule cooled for {approx}4 months was transported to Reactor Fuel Examination Facility and subjected to non-destructive and destructive post irradiation examinations. It was found from the radial cross section of fuel pin that the helium gap between the pellets and the cladding tube was completely closed. Compared with the results obtained so far, very low open porosity and fission gas release rate as well as mild restructuring was observed owing to the adoption of thermally stable pellets. The diametric increase of fuel pin reached {approx}0.06mm at the position of maximum reading, although it might not affect the fuel performance itself. The inner surface of cladding tube did not show signs of carburization. (author).
Arai, Yasuo;
Iwai, Takashi;
Sasayama, Tatsuo;
Nakajima, Kunihisa;
Nomura, Isamu;
Yoshida, Takeshi;
Suzuki, Yasufumi
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Arai, Yasuo, Iwai, Takashi, Sasayama, Tatsuo, Nakajima, Kunihisa, Nomura, Isamu, Yoshida, Takeshi, and Suzuki, Yasufumi.
Post irradiation examinations of 87F-2A capsule containing uranium-plutonium mixed carbide fuels.
Japan: N. p.,
1994.
Web.
Arai, Yasuo, Iwai, Takashi, Sasayama, Tatsuo, Nakajima, Kunihisa, Nomura, Isamu, Yoshida, Takeshi, & Suzuki, Yasufumi.
Post irradiation examinations of 87F-2A capsule containing uranium-plutonium mixed carbide fuels.
Japan.
Arai, Yasuo, Iwai, Takashi, Sasayama, Tatsuo, Nakajima, Kunihisa, Nomura, Isamu, Yoshida, Takeshi, and Suzuki, Yasufumi.
1994.
"Post irradiation examinations of 87F-2A capsule containing uranium-plutonium mixed carbide fuels."
Japan.
@misc{etde_10121646,
title = {Post irradiation examinations of 87F-2A capsule containing uranium-plutonium mixed carbide fuels}
author = {Arai, Yasuo, Iwai, Takashi, Sasayama, Tatsuo, Nakajima, Kunihisa, Nomura, Isamu, Yoshida, Takeshi, and Suzuki, Yasufumi}
abstractNote = {One fuel pin filled with hyperstoichiometric uranium-plutonium mixed carbide pellets was encapsulated in 87F-2A and irradiated in JMTR up to 4.4 %FIMA at an average linear power of 60 kW/m. The capsule cooled for {approx}4 months was transported to Reactor Fuel Examination Facility and subjected to non-destructive and destructive post irradiation examinations. It was found from the radial cross section of fuel pin that the helium gap between the pellets and the cladding tube was completely closed. Compared with the results obtained so far, very low open porosity and fission gas release rate as well as mild restructuring was observed owing to the adoption of thermally stable pellets. The diametric increase of fuel pin reached {approx}0.06mm at the position of maximum reading, although it might not affect the fuel performance itself. The inner surface of cladding tube did not show signs of carburization. (author).}
place = {Japan}
year = {1994}
month = {Nov}
}
title = {Post irradiation examinations of 87F-2A capsule containing uranium-plutonium mixed carbide fuels}
author = {Arai, Yasuo, Iwai, Takashi, Sasayama, Tatsuo, Nakajima, Kunihisa, Nomura, Isamu, Yoshida, Takeshi, and Suzuki, Yasufumi}
abstractNote = {One fuel pin filled with hyperstoichiometric uranium-plutonium mixed carbide pellets was encapsulated in 87F-2A and irradiated in JMTR up to 4.4 %FIMA at an average linear power of 60 kW/m. The capsule cooled for {approx}4 months was transported to Reactor Fuel Examination Facility and subjected to non-destructive and destructive post irradiation examinations. It was found from the radial cross section of fuel pin that the helium gap between the pellets and the cladding tube was completely closed. Compared with the results obtained so far, very low open porosity and fission gas release rate as well as mild restructuring was observed owing to the adoption of thermally stable pellets. The diametric increase of fuel pin reached {approx}0.06mm at the position of maximum reading, although it might not affect the fuel performance itself. The inner surface of cladding tube did not show signs of carburization. (author).}
place = {Japan}
year = {1994}
month = {Nov}
}