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; ; Sakamoto, Naoki; *; Akasaka, Naoaki;
JNC TN9400 2000-095, 110 Pages, 2000/07
JNC-TN9400-2000-095.pdf:13.57MB
The effects of high fluence irradiation and swelling on the transient burst properties of austenitic steel fuel claddings; PNC316 and 15Cr-20Ni stcel, which were irradiated as the MONJU type fuel assemblies (MFA-1&MFA-2) in the FFTF reactor, were investigated. The temperature-transient-to-burst tests were conducted on a total of eight irradiation conditions. Fractographic examination and TEM observation were performed in order to evaluate the effect of high dose irradiation on the transient burst property and the relation between failure mechanism and microstructural change during rapid (ramp) heating. The results of the PIE showed that there was no significant effect of irradiation on the transient burst properties of these fuel claddings under the irradiation conditions examined. the results obtained in this study are as follows; (1)The rupture temperature of the irradiated PNC316 fuel cladding of MFA-1 was as same as that of our previous works for the fluence range up to 2.13
10
n/m
. There was no noticeable decrease in rupture temperature with increasing fluence in lower hoop stress region(
100MPa). (2)The rupture temperature of the irradiated 15Cr-20Ni fuel cladding of MFA-2 was almost as same as that of as-received cladding for the hoop stress range up to about 200MPa. The rupture temperature did not decrease significantly with fluence. (3)The rupture temperature of the irradiated PNC316 cladding tested at hoop stress 69MPa, which was the design hoop stress for MONJU fuel, was 1055.6
C. This suggested that the design cladding maximum temperature limit for MONJU (830C) was conservative. (4)There was no obvious relation between rupture temperature, swelling and microstructural change during transient heating under the irradiation conditions examined.
Seshimo, Ichiro; Ukai, Shigeharu; Nomura, Shigeo; Shikakura, Sakae
PNC TN9410 89-122, 47 Pages, 1989/08
Fuel cladding integrity must be confirmed even at the anticipated transient event in LMFBR. In case of loss of coolant accident, cladding highest temperature is limited to 830
for Monju design from a view point of preventing the cladding creep rupture failure by increasing internal gas pressure. In this study, using the recent thermal transient test results of modified SUS316 stainless steel, Larson-Miller Parameter Life Fraction method was applied for predicting the optimum failure temperature. With this method, different thermal transient data can be evaluated systematically, and the effect of irradiation on cladding failure temperature was analyzed. Through this analysis, the Monju design limit temperature of 830 for cladding failure can be changed to 966, and alternative limiting temperature of 920 defined for preventing the coolant sodium boiling becomes a critical factor. This results shows the possibility of improvement for the design limit of this event.
; ; ; ; Yoshida, Kenzo
EIM-81-94, p.39 - 46, 1981/00
no abstracts in English
; Yoshida, Kenzo; ; ; ; Machi, Sueo
EIM-80-98, p.57 - 64, 1980/00
no abstracts in English
Inoue, Toshihiko; Sekio, Yoshihiro; Otsuka, Satoshi; Yano, Yasuhide; Tanno, Takashi; Oka, Hiroshi; Furukawa, Tomohiro; Kaito, Takeji; Torimaru, Tadahiko*; Hayashi, Shigenari*; et al.
no journal, ,
In order to evaluate the strength and deformation in severe accident, the transient burst tests were carried out with various heating rates (from 0.1 to 10 K/s) and hoop stresses (from 50 to 200 MPa) to provide more evaluation data. The test materials were core materials in fast reactors, 9-18Cr-ODS and accident tolerant fuel cladding tube in the light water reactors, FeCrAl-added ODS ferritic steels. Result, the rupture strength dropped with increasing hoop stress and decreasing heating rate. The burst strength of Al-added ODS steels was lower than other ODS steels, Al and Zr-added ODS steels show good transient burst strength.