Abstract
Two fuel pins filled with uranium-plutonium mixed carbide pellets having different stoichiometry, (U,Pu)C{sub 1.0} and (U,Pu)C{sub 1.1}, were encapsulated in 84F-10A and irradiated in JMTR up to 3.0%FIMA at a peak linear power of 59kW/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 sections of fuel pins that the helium gap between the pellets and the cladding tube was completely closed. At the central part of the fuel pellets the number of small pores was decreased and the grain growth was observed compared with the outer zone. (U,Pu)C{sub 1.1} pellets showed higher fission gas release ratio than (U,Pu)C{sub 1.0} pellets because the former had relatively high open porosity. Although slight carburization was observed near the inner surface of cladding tube the interaction did not affect the fuel performance itself. (author).
Arai, Yasuo;
Suzuki, Yasufumi;
Sasayama, Tatsuo;
Iwai, Takashi;
Sekita, Noriaki;
Ohwada, Isao;
Ohmichi, Toshihiko;
[1]
Niimi, Motoji
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Arai, Yasuo, Suzuki, Yasufumi, Sasayama, Tatsuo, Iwai, Takashi, Sekita, Noriaki, Ohwada, Isao, Ohmichi, Toshihiko, and Niimi, Motoji.
Post irradiation examinations of 84F-10A capsule containing uranium-plutonium mixed carbide fuels.
Japan: N. p.,
1991.
Web.
Arai, Yasuo, Suzuki, Yasufumi, Sasayama, Tatsuo, Iwai, Takashi, Sekita, Noriaki, Ohwada, Isao, Ohmichi, Toshihiko, & Niimi, Motoji.
Post irradiation examinations of 84F-10A capsule containing uranium-plutonium mixed carbide fuels.
Japan.
Arai, Yasuo, Suzuki, Yasufumi, Sasayama, Tatsuo, Iwai, Takashi, Sekita, Noriaki, Ohwada, Isao, Ohmichi, Toshihiko, and Niimi, Motoji.
1991.
"Post irradiation examinations of 84F-10A capsule containing uranium-plutonium mixed carbide fuels."
Japan.
@misc{etde_10127225,
title = {Post irradiation examinations of 84F-10A capsule containing uranium-plutonium mixed carbide fuels}
author = {Arai, Yasuo, Suzuki, Yasufumi, Sasayama, Tatsuo, Iwai, Takashi, Sekita, Noriaki, Ohwada, Isao, Ohmichi, Toshihiko, and Niimi, Motoji}
abstractNote = {Two fuel pins filled with uranium-plutonium mixed carbide pellets having different stoichiometry, (U,Pu)C{sub 1.0} and (U,Pu)C{sub 1.1}, were encapsulated in 84F-10A and irradiated in JMTR up to 3.0%FIMA at a peak linear power of 59kW/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 sections of fuel pins that the helium gap between the pellets and the cladding tube was completely closed. At the central part of the fuel pellets the number of small pores was decreased and the grain growth was observed compared with the outer zone. (U,Pu)C{sub 1.1} pellets showed higher fission gas release ratio than (U,Pu)C{sub 1.0} pellets because the former had relatively high open porosity. Although slight carburization was observed near the inner surface of cladding tube the interaction did not affect the fuel performance itself. (author).}
place = {Japan}
year = {1991}
month = {Nov}
}
title = {Post irradiation examinations of 84F-10A capsule containing uranium-plutonium mixed carbide fuels}
author = {Arai, Yasuo, Suzuki, Yasufumi, Sasayama, Tatsuo, Iwai, Takashi, Sekita, Noriaki, Ohwada, Isao, Ohmichi, Toshihiko, and Niimi, Motoji}
abstractNote = {Two fuel pins filled with uranium-plutonium mixed carbide pellets having different stoichiometry, (U,Pu)C{sub 1.0} and (U,Pu)C{sub 1.1}, were encapsulated in 84F-10A and irradiated in JMTR up to 3.0%FIMA at a peak linear power of 59kW/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 sections of fuel pins that the helium gap between the pellets and the cladding tube was completely closed. At the central part of the fuel pellets the number of small pores was decreased and the grain growth was observed compared with the outer zone. (U,Pu)C{sub 1.1} pellets showed higher fission gas release ratio than (U,Pu)C{sub 1.0} pellets because the former had relatively high open porosity. Although slight carburization was observed near the inner surface of cladding tube the interaction did not affect the fuel performance itself. (author).}
place = {Japan}
year = {1991}
month = {Nov}
}