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-ray exposure rate from short-lived fission products under criticality accident conditionsYanagisawa, Hiroshi; Ono, Akio; Aizawa, Eiju
Journal of Nuclear Science and Technology, 39(5), p.499 - 505, 2002/05
Times Cited Count：4 Percentile：29.25(Nuclear Science & Technology)no abstracts in English
; ; 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.
*; Akatsuka, Hiroshi*; *; Suzuki, Tatsuya*; *; *;
JNC TY9400 2000-009, 41 Pages, 2000/03
JNC-TY9400-2000-009.pdf:1.22MB
no abstracts in English
; *
JNC TN9450 2000-002, 335 Pages, 1999/10
JNC-TN9450-2000-002.pdf:21.65MB
This report summarizes the material test dala of SUS304 welded joints. Numbers of the data are as follows: [Tensile tests 71 (Post-irradiation: 39, others: 32) [Creep tests 77 (Post-irradiation: 20, others: 57) [Fatigue tests 50 (Post-irradiation: 0) [Creep-fatigue tests 14 (Post-irradiation: 0) This report consists of the printouts from "the structural material data processing system".
Mizuta, Shunji; ;
JNC TN9400 99-082, 60 Pages, 1999/10
The density measurement of the internal creep specimens irradiated in FFTF/MOTA (Fast Flux Test Facility / Material open Test Assembly) was conducted MMF (Materia1 Monitoring Facility) and accurate separation of swelling strain from total strain leaded in the derivation of the irradiation creep coefficients. Irradiation creep coefficients for PNC 316, 15Cr-20Ni base S.S. and 14Cr-25Ni base S.S. were systematically expressed, while thermal creep coefficients K, under irradiation were separately expressed for above three steels. The results obtained are follows, (1)The effect of stress induced swelling was recognized in the temperature range from 405 to 605C. The swelling in high stress specimens have a tendency to increasing swelling. (2)The irradiation creep coefficients derived from PNC316 and l5Cr-20Ni are similar to that of derived from 20%CW316S.S., CW316Ti and CW15-15Ti which were reported by other authors. (3)The irradiation creep coefficient derived from gas pressurized tube irradiation using FFTF/MOTA expressed appropriately irradiation creep strain from fuel pins using FFTF/MFA-2(15Cr-2ONi base S.S.).
Murakami, Hiroyuki; Minami, Kentaro; R.V.Griffith*
Radiation Protection Dosimetry, 54(1), p.19 - 23, 1994/00
Times Cited Count：4 Percentile：42.35(Environmental Sciences)no abstracts in English
; ; ; ; ; Shibahara, Itaru
PNC TN9410 92-321, 30 Pages, 1992/10
Integrity evaluations have been performed for the 2nd Fugen pressure tube test (8 years irradiation, 5.6 10
n/cm (E
1Mev)). Test items mainly consist of tensile test, bending test, corrosion test and hydrogen analysis. It has become clear using these data that the pressure tube material has maintained its integrity during the irradiation by the integrity assessment on both tensile and fracture toughness properties. Besides, both thickness loss by corrosion and absorbed hydrogen content were lower than those of design values.
Nuclear Safety Technology Center*
PNC TJ1545 91-001, 260 Pages, 1991/03
no abstracts in English
Sakamoto, Yukio; Tanaka, Shunichi
JAERI-M 90-110, 95 Pages, 1990/07
no abstracts in English
JAERI-M 85-095, 185 Pages, 1985/07
no abstracts in English
;
JAERI-M 85-058, 40 Pages, 1985/05
no abstracts in English
Miura, Makoto; Narita, Osamu; Shinohara, Kunihiko*; Asano, Tomohiro
PNC TN843 81-08, 240 Pages, 1981/09
None
ioactive Cloud from a Stack;
JAERI-M 8793, 58 Pages, 1980/03
no abstracts in English
-raysNihon Genshiryoku Gakkai-Shi, 21(9), p.705 - 709, 1979/00
Times Cited Count：0no abstracts in English
; *
JAERI-M 8019, 68 Pages, 1978/12
no abstracts in English
*; Kishimoto, Yoichiro; Narita, Osamu; Shinohara, Kunihiko*; *
PNC TN843 77-05, 25 Pages, 1977/06
A computer program has been written to calculate the exposure dose at an arbitrary point in the atmosphere caused by the emission of radioactive materials from a stack. The dispersion of materials in air is expressed by the Gaussian plume model with ground surface and inversion lid reflections. The exposure or absorbed dose in air is calculated by the spatial integration of point-kernels. Several approximate methods, such as homogeneous-infinite-slab approximation, submersion approximation, etc, have been incorporated as well.
