Abstract
Experimental study was made to evaluate the FGR (Fission Product Gas Release) from high burned PWR type fuel rods by means of non-destructive method through measurement of the gamma activity of {sup 85}Kr isotope which was accumulated in the fuel top plenum. Experimental result shows that it is possible to know the amounts of FGR at fuel plenum by the equations given in the followings. FGR = 0.28C/V{sub f} or FGR = 0.07C where, FGR (%) is the amounts of Xe and Kr released from UO{sub 2} fuel, C (counts/h) the radioactivity of {sup 85}Kr at plenum of the tested fuel rod and V{sub f} (ml) the plenum volume of the tested fuel rod, respectively. The present study was made by using 14 x 14 PWR type fuel rods preirradiated up to the burn-up of 42.1 MWd/kgU, followed by the pulse irradiation at Nuclear Safety Research Reactor of Japan Atomic Energy Research Institute (JAERI). The FGR of the tested segmented fuel rods were measured by puncturing and found to range from 0.6% to 12% according to the magnitude of the deposited energy given by pulse. Estimated experimental error bands against the above equations were within plus minus 30%. (author).
Citation Formats
Yanagisawa, Kazuaki, Miyanishi, Hideyuki, Kitagawa, Isamu, Iida, Shozo, Ito, Tadaharu, and Amano, Hidetoshi.
Study of development of non-destructive method for determining FGR from high burned PWR type fuel rod.
Japan: N. p.,
1991.
Web.
Yanagisawa, Kazuaki, Miyanishi, Hideyuki, Kitagawa, Isamu, Iida, Shozo, Ito, Tadaharu, & Amano, Hidetoshi.
Study of development of non-destructive method for determining FGR from high burned PWR type fuel rod.
Japan.
Yanagisawa, Kazuaki, Miyanishi, Hideyuki, Kitagawa, Isamu, Iida, Shozo, Ito, Tadaharu, and Amano, Hidetoshi.
1991.
"Study of development of non-destructive method for determining FGR from high burned PWR type fuel rod."
Japan.
@misc{etde_10127220,
title = {Study of development of non-destructive method for determining FGR from high burned PWR type fuel rod}
author = {Yanagisawa, Kazuaki, Miyanishi, Hideyuki, Kitagawa, Isamu, Iida, Shozo, Ito, Tadaharu, and Amano, Hidetoshi}
abstractNote = {Experimental study was made to evaluate the FGR (Fission Product Gas Release) from high burned PWR type fuel rods by means of non-destructive method through measurement of the gamma activity of {sup 85}Kr isotope which was accumulated in the fuel top plenum. Experimental result shows that it is possible to know the amounts of FGR at fuel plenum by the equations given in the followings. FGR = 0.28C/V{sub f} or FGR = 0.07C where, FGR (%) is the amounts of Xe and Kr released from UO{sub 2} fuel, C (counts/h) the radioactivity of {sup 85}Kr at plenum of the tested fuel rod and V{sub f} (ml) the plenum volume of the tested fuel rod, respectively. The present study was made by using 14 x 14 PWR type fuel rods preirradiated up to the burn-up of 42.1 MWd/kgU, followed by the pulse irradiation at Nuclear Safety Research Reactor of Japan Atomic Energy Research Institute (JAERI). The FGR of the tested segmented fuel rods were measured by puncturing and found to range from 0.6% to 12% according to the magnitude of the deposited energy given by pulse. Estimated experimental error bands against the above equations were within plus minus 30%. (author).}
place = {Japan}
year = {1991}
month = {Nov}
}
title = {Study of development of non-destructive method for determining FGR from high burned PWR type fuel rod}
author = {Yanagisawa, Kazuaki, Miyanishi, Hideyuki, Kitagawa, Isamu, Iida, Shozo, Ito, Tadaharu, and Amano, Hidetoshi}
abstractNote = {Experimental study was made to evaluate the FGR (Fission Product Gas Release) from high burned PWR type fuel rods by means of non-destructive method through measurement of the gamma activity of {sup 85}Kr isotope which was accumulated in the fuel top plenum. Experimental result shows that it is possible to know the amounts of FGR at fuel plenum by the equations given in the followings. FGR = 0.28C/V{sub f} or FGR = 0.07C where, FGR (%) is the amounts of Xe and Kr released from UO{sub 2} fuel, C (counts/h) the radioactivity of {sup 85}Kr at plenum of the tested fuel rod and V{sub f} (ml) the plenum volume of the tested fuel rod, respectively. The present study was made by using 14 x 14 PWR type fuel rods preirradiated up to the burn-up of 42.1 MWd/kgU, followed by the pulse irradiation at Nuclear Safety Research Reactor of Japan Atomic Energy Research Institute (JAERI). The FGR of the tested segmented fuel rods were measured by puncturing and found to range from 0.6% to 12% according to the magnitude of the deposited energy given by pulse. Estimated experimental error bands against the above equations were within plus minus 30%. (author).}
place = {Japan}
year = {1991}
month = {Nov}
}