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Kawano, Takahiro*; Mizuta, Naoki; Ueta, Shohei; Tachibana, Yukio; Yoshida, Katsumi*
JAEA-Technology 2023-014, 37 Pages, 2023/08
JAEA-Technology-2023-014.pdf:2.35MB
Fuel compact for High Temperature Gas-cooled Reactor (HTGR) is fabricated by calcinating a matrix consisting of graphite and binder with the coated fuel particle. The SiC-matrixed fuel compact uses a new matrix made of silicon carbide (SiC) replacing the conventional graphite. Applying the SiC-matrixed fuel compact for HTGRs is expected to improve their performance such as power densities. In this study, the sintering conditions for applying SiC as the matrix of fuel compacts for HTGR are selected, and the density and thermal conductivity of the prototype SiC are measured.
Okita, Shoichiro; Mizuta, Naoki; Takamatsu, Kuniyoshi; Goto, Minoru; Yoshida, Katsumi*; Nishimura, Yosuke*; Okamoto, Koji*
Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 10 Pages, 2023/05
Usuki, Toshiyuki; Yoshida, Katsumi*; Yano, Toyohiko*; Miwa, Shuhei; Osaka, Masahiko
Progress in Nuclear Energy, 53(7), p.1078 - 1081, 2011/09
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)The effects of sintering additives of magnesium silicates, i.e. enstatite (MgSiO
), steatite (MgSiO) and forsterite (Mg
SiO
), on the fabrication properties and characteristics of the silicon nitride ceramics based inert matrix fuels were experimentally investigated. CeO was selected as simulating element of AmO. Sintered pellets were characterized in term of their densities, thermal conductivities and solubility to nitric acid. The densifications of sintered bodies were enhanced by using additives of magnesium silicates at relative low sintering temperature. The relative density of silicon nitride ceramics based inert matrix fuels with forsterite were achieved above 90% at 1723 K. The thermal conductivities of silicon nitride ceramics based inert matrix fuels varied according to sintering temperature, and those sintered at 1923 K were above 34 W/m K. The grain boundary phases in Silicon nitride ceramics based inert matrix fuels found to be dissolved into HNO.
Sakanaka, Shogo*; Akemoto, Mitsuo*; Aoto, Tomohiro*; Arakawa, Dai*; Asaoka, Seiji*; Enomoto, Atsushi*; Fukuda, Shigeki*; Furukawa, Kazuro*; Furuya, Takaaki*; Haga, Kaiichi*; et al.
Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.2338 - 2340, 2010/05
Future synchrotron light source using a 5-GeV energy recovery linac (ERL) is under proposal by our Japanese collaboration team, and we are conducting R&D efforts for that. We are developing high-brightness DC photocathode guns, two types of cryomodules for both injector and main superconducting (SC) linacs, and 1.3 GHz high CW-power RF sources. We are also constructing the Compact ERL (cERL) for demonstrating the recirculation of low-emittance, high-current beams using above-mentioned critical technologies.
; ; Yoshida, Eiichi; *; *; *;
PNC TN9450 95-006, 175 Pages, 1995/04
In order to advancement in materials strength standard on elevated temperature design guide of the FBRs and evaluation method of materials strength behavior, this report are presented about the creep properties of FBR grade 316 (Abbreviation 316FR), based on the R&D results obtained through the activities of material tests. Contents of the data sheet are as follows; (1)Material : 316FR (Base Metal) Plate 8 heats (B7, B8, JA, MC,MD, ,ME, MG, MI heat) Tube 2 heats (S6F, B10 heat) (2)Test environment : In air , In sodium (3)Test temperature : 500
C
800C (4)Test method : According to JIS and FBR Metallic Materials Test Method (5)Number of deta : 211 points
; ; Yoshida, Eiichi; *; *;
PNC TN9450 95-003, 98 Pages, 1995/02
In order to advancement in materials strength standard on elevated temperature design guide of the FBRs and evaluation method of materials strength behavior, this report are presented about the tensile properties of FBR grade 316FR on air and sodium environment conditions. Contents of the data sheet are as follows; (1)Material : FBR grade 316FR (Base Metal) (a)B6 heat 25mm
1,000㎜1,000mm (Plate) (b)B7 heat 50mm1,000mm1,000mm (Plate) (c)B8 heat 40mm1,000mm1,000mm (Plate) (d)B9 heat 25mm1,000mm1,000mm (Plate) (d)B11 heat 50mm1,000mm1,000mm (Plate) (2)Pre-test treatment: (a)Argon aged for 5000hr at 500, 550, 600C (B6, B7, B8 Heats) (b)Argon aged for 20000hr at 500, 550, 600C (B7, B8 Heats) (c)Sodium exposed for 5000hr at 500, 550, 600C (B6, B7, B8 Heats) (d)Sodium exposed for 20000hr at 500, 550, 600C (B6, B7, B8 Heats) (e)As-recieved (B6, B7, B8, B9, B11 Heats) (3)Test temperature : R.T.750C (4)Test method : Accoding to JIS and FBR Metallic Materials Test Methods (5)Number of data : 153 points (Including 64 points on the last report)
; ; ; *
PNC TN9410 91-295, 257 Pages, 1991/09
A failure test of a structure model was carried out under cyclic thermal transient stress in the thermal transient test facility for structures(TTS). After the test, destructive examination of the model clarified crackings as planned. Formerly inelastic analysis was applied to creep-fatigue damage evaluation, and good relationship was obtained between creep-fatigue damage and observed cracks. The result showed damage distributions were well corresponding to those of crack depth. The damage was not able to explain the crack propagation behavior, although could describe the crack initiation behavior. It was, therfore, important to assess the crack propagation behavior by fracture mechanics method in order to understand the crack propagation behavior. This report describes the crack analysis results of several cracks observed on the model named Thermal Stress Mitigation Structure Model (1). Axisy㎜etric finite element analyses were carried out for cyclic thermal transient loadings. It has been known that J-integral is path-dependent for thermal transient stress field. Therefore, J^ and J^' integrals for fatigue and creep crack growth, respectively were calculated by the CANIS-J code (Crack Analysis in Structure-J version). As the analysis results, J^ and J^' were almost path-independent, so these parameters were considered to be suitable for assessing the intensity of the crack-tip stress-strain field under thermal transient loadings. The distribution of J^ and J^' along the thickness direction were obtained. It was confirmed that J^ and J^' take the maximum values in nearly middle depth of the thickness and decrease gradually when crack depth exceed that point. Crack propagation behavior was simulated by such a manner that crack propagation rate was calculated from J^ and J^' integrals distributions with material crack growth law. The number of cycles of thermal transient, which was needed for cracks to propagate from the initial length (supposed to be 1mm) ...
; *; Furuhashi, Ichiro*
PNC TN9410 88-147, 215 Pages, 1988/09
The present study includes the analytical work for of the stable crack growth of the finite plate with semi-elliptical surface defect by creep-fatigue loadings, and of the crack opening area for presumed leakage of cloolant to be considered in safety assessment. The objective of this study is to develop the basic inelastic fracture mechanics to the level in which the integrity of basic components, plate, vessel, piping, and so on, with crack would be able to be assessed analytically. CANIS code developed last year was used to analize the J integral for fatigue crack growth and J' integral for creep crack growth of SUS 304 plates with various shapes of semi-elliptical surface cracks at 500 C, then those distributions were arranged from the view point of crack growth assessment. An appricable range of these data is 
1.5 Sm of fatigue cycle and hold time of 108,000 hr creep. 0nly secondary stress including membrane, bending and combination of these stresses were considered in the data base. Evaluation of elbow with 42
diameter and 20.6mm thickness considered in the design of large loop type FBR were achieved based on the data base. Then calculated through wall crack lengths were applied to the calculation of opening areas of 42 elbow subjected of internal pressure of 2 atg and in plane bending moment corresponding to stress level of 1.5Sm. The results are (1)A numbers of cycles at penetration are 6,250 for membrane stress and 30,520 for bending stress in the case of fatigue, and 303 for memberane and 1,534 for bending in the case of creep-fatigue. (2)opening area against internal pressure is larger than that against bending moment, and is about 0.5mm
. (3)maximum leak rate from the opening area is about 23 
/hr. The level up of analytical method for stable crack growth was almost accomplished. In the near future, the experimental study would be needed for validation of this method.
; *; Imazu, Akira
PNC TN9410 87-171, 135 Pages, 1987/10
The objective of this report is to develop non-linear fracture mechanics applicable to the calculation of creep-fatigue crack growth relating to postulated sodium leak. The procedure adopted here is (1) survey and selection of creep-fatigue fracture mechanics parameters, (2) development of analytical method and computer code, (3) analyses of plates with semi-eliptical surface crack, (4) calculation of growth and (5) assessment of crack opening area. CANIS code (Crack ANalysis in Structures) was initially developed for only fatigue crack parameters J and J^ and was extended to creep crack parameters J' and J'^. Fracture mechanics parameters of plate with semi-eliptical surface crack (b/a = 0.167, a/t = 0.25, 0.4, 0.6, 0.8, 0.9) were calculated. Then crack growth under creep-fatigue condition, namely hold time up to 8000 hr. at 500C, was calculated. The crack growth calculation method based on elastic-plastic-creep analysis is described in this report. The preliminary analyses showed that crack opening area seemed to be less than 1 cm, but additional analytical data and creep crack growth data at lower crack growth rate region were needed for more accurate assessment of crack opening area in the future.
; Asano, Masaharu; Kaetsu, Isao; *; *; *; *; *; *; *
Polym.J., 18(4), p.287 - 296, 1986/00
Times Cited Count：9 Percentile：51.86(Polymer Science)no abstracts in English
Kaetsu, Isao; ; Asano, Masaharu; *; *; *; *; *; *; *; et al.
Jinko Zoki, 13(3), p.1168 - 1171, 1984/00
no abstracts in English
He proportional counters; *;
IEEE Transactions on Nuclear Science, NS-27(1), p.776 - 782, 1980/00
no abstracts in English
N-based fuelsYano, Toyohiko*; Yoshida, Katsumi*; Imai, Masamitsu*; Miwa, Shuhei; Osaka, Masahiko
no journal, ,
no abstracts in English
Usuki, Toshiyuki*; Yoshida, Katsumi*; Imai, Masamitsu*; Yano, Toyohiko*; Miwa, Shuhei; Osaka, Masahiko
no journal, ,
no abstracts in English
Usuki, Toshiyuki; Yoshida, Katsumi*; Yano, Toyohiko*; Miwa, Shuhei; Osaka, Masahiko
no journal, ,
Minor actinides (MA) have lasting radio-toxicity. One of the possible ways to reduce radio-toxicity is transmutation of MA using nuclear reactors. Inert matrix (IM) is applied to host material for MA in transmutation. Silicon nitride (SiN) ceramics considered to be a candidate material of IM since it has a high thermal conductivity and shows good resistance to neutron irradiation. In this study, We proposed fabrication of silicon nitride ceramics based IMFs with Ce as simulating element and with magnesium silicates, i.e. enstatite (MgSiO), steatite (MgSiO) and forsterite (MgSiO), as additives. The sintered densities of SiN-based IMFs with forsterite was above 96 % theoretical 1723 K. Furthermore, The thermal conductivities of IMFs sintered at 1923 K were above 34 W/mK.
Maeda, Shigetaka; Itagaki, Wataru; Maeda, Koji; Maki, Ryosuke*; Yoshida, Katsumi*
no journal, ,
Highly microstructure-controlled ceramic neutron absorbers were developed for improving safety of fast reactors. The control rod worth was evaluated using several compositions as parameter. It was confirmed that the effect of additives on control rod worth was negligible.
C absorber material for fast reactor after irradiationShizukawa, Yuta; Sekio, Yoshihiro; Inoue, Toshihiko; Maeda, Koji; Yoshida, Katsumi*
no journal, ,
no abstracts in English
C control materialsShizukawa, Yuta; Sekio, Yoshihiro; Inoue, Toshihiko; Maeda, Koji; Yoshida, Katsumi*
no journal, ,
no abstracts in English
Yoshida, Katsumi*; Gubarevich, A.*; Tachibana, Yukio; Takamatsu, Kuniyoshi; Okita, Shoichiro; Nishimura, Yosuke*; Okamoto, Koji*
no journal, ,
