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The effects of thermal aging on the microstructure and mechanical property changes in high Cr oxide dispersion strengthened (ODS) steels were investigated by using TEM, microhardness and small punch (SP) tests. The materials used were produced by varying Cr contents from 14 to 22 wt% but keeping yittria contents within 0.36–0.38 wt%. Specimens were thermally aged at temperatures between 430 and 475 °C up to 1000 h. SP-ductile to brittle transition temperature and microhardness of thermally aged ODS steels were significantly increased as a function of Cr contents, aging time and temperature. The main cause of embrittlement is the formation of a Cr-rich α′ phase. The hardening appears thermally activated and the apparent activation energy is measured in the range of 214–240 kJ/mol. It is coherent with the activation energy for the diffusion of Cr or Fe in this type of alloys.

Cladding materials development is crucial to realize highly efficient and high-burnup operation over 100GWd/t of so called Generation IV nuclear energy systems, such as supercritical-water-cooled reactor (SCWR) and lead-cooled fast reactor (LFR). Oxide dispersion strengthening (ODS) ferritic/martensitic steels, which contain 9–12%Cr, show rather high resistance to neutron irradiation embrittlement and high strength at elevated temperatures. However, their corrosion resistance is not good enough in SCW and in lead at high temperatures. In order to improve corrosion resistance of the ODS steels in such environment, high-Cr ODS steels have been developed at Kyoto University. An increase in Cr content resulted in a drastic improvement of corrosion resistance in SCW and in lead, while it was expected to cause an enhancement of aging embrittlement as well as irradiation embrittlement. Anisotropy in tensile properties is another issue. In order to overwhelm these issues, surveillance tests of the material perfor...

AIM To compare urinary concentrations of unsaturated ketonic bile acids in preterm and full-term infants. METHODS Urinary unsaturated ketonic bile acids were determined using gas chromatography-mass spectrometry. RESULTS Urinary concentrations of total bile acids in early preterm infants (of less than 29wk gestational age) exceeded concentrations in late preterm (between 30 and 37 wk) and full-term infants (between 38 and 41 wk; p < 0.01). The percentage of ketonic bile acids (7alpha, 12alpha-dihydroxy-3-oxo-4-cholenoic acid and 7alpha-hydroxy-3-oxo-4-cholenoic acid) among total urinary bile acids in full-term infants (20.2 +/- 14.1%) was higher than that in early preterm infants (8.94 +/- 8.1%; p < 0.05). The percentage of unsaturated bile acids (3beta-hydroxy-delta5-bile acids) among total bile acids in urine did not differ greatly between groups. CONCLUSION The percentage of 3-oxo-delta4 bile acids among total bile acids in urine gradually increased from early to late preterm infants, while healthy full-term infants excreted large amounts of 3-oxo-delta4 bile acids in urine at delivery.

Anti-obesity effects of a fermentation product of phytosterols including campestenone in ICR mice were investigated. Five-week-old male ICR mice were fed by the pair-feeding method for 8 wk. Experimental feed was prepared by adding TO-001, a phytostenone mixture produced by fermentation of phytosterols using Nocardioides simplex, at 0.25, 0.5, 1.0, or 2.0% or no additive to a high fat diet (fat 20%). Mice fed a stock feed (fat 5.6%) ad libitum were used as the standard growth group. In animals fed the high fat diet, control (no added TO-001) mice showed a weight gain that was about 10% higher than for the standard growth group. TO-001 reduced body weight dose-dependently. Final body weights of 0.5% and 1.0% TO-001-fed mice were lowered by about 9% and those of 2.0% TO-00 I-fed mice by about 12% compared with the control mice. Visceral and subcutaneous fat weight in mice fed TO-001 was significantly lower than that in mice fed the control diet. The concentrations of serum triglyceride (TG) and total cholesterol (TC) were significantly lower in the 1.0% and/or 2.0% TO-001-fed mice. Furthermore, levels of liver TG and TC were decreased in the TO-001-fed group. Increase of total lipid excretion in the feces was dose dependent. No obvious abnormalities due to consumption of TO-001 were detected by a blood biochemical examination, clinical observations or necropsy. The results suggested that TO-001, a fermentation product of phytosterols, may be a promising component of dietetic functional foods.

Subcutaneous injection of sodium arsenite (NaAs, 12.5 mg/kg) into BALB/c [wild-type (WT)] mice causes acute renal dysfunction characterized by severe hemorrhages, acute tubular necrosis, and cast formation, with increases in serum blood urea nitrogen and creatinine levels. Concomitant enhancement in intrarenal interferon (IFN)-gamma expression prompted us to examine its roles in this pathology. IFN-gamma-deficient (IFN-gamma-/-) mice exhibited higher serum blood urea nitrogen and creatinine levels and exaggerated histopathological changes, compared with WT mice. Eventually, IFN-gamma-/- mice exhibited a high mortality (87.5%) within 24 hours after NaAs challenge, whereas most WT mice survived. The intrarenal arsenic concentration was significantly higher in IFN-gamma-/- mice later than 10 hours after NaAs treatment, with attenuated intrarenal expression of multidrug resistance-associated protein (MRP) 1, a main transporter for NaAs efflux, compared with WT mice. NF-E2-related factor (Nrf) 2 protein, a transcription factor crucial for MRP1 gene expression, was similarly increased in the kidneys of both strains of mice after NaAs treatment. In contrast, the absence of IFN-gamma augmented transforming growth factor-beta-Smad3 signal pathway and eventually enhanced the expression of activating transcription factor 3, which is presumed to repress Nrf2-mediated MRP1 gene expression. Thus, IFN-gamma can protect against NaAs-induced acute renal injury, probably by maintaining Nrf2-mediated intrarenal MRP1 gene expression.

Tensile testing has been performed at 25 and at ∼400 °C on two ferritic/martensitic steels (JFMS and HT-9) after irradiation in FFTF to up to ∼70 dpa at 373–433 °C. As observed in previous studies, this range of irradiation temperatures has a significant effect on hardening. The percent increase in yield stress decreases with increasing irradiation temperature from 373 to 433 °C. The JFMS alloy, which has 0.7 wt% silicon, exhibits approximately a factor of two increase in yield strength between tests at 427 and at 373 °C, and shows an increase in hardening with increasing dose. A comparison of the JFMS tensile properties to the properties of other ferritic/martensitic steels suggests that this hardening is due to precipitation of a Si-rich laves phase in this alloy. The HT-9 alloy, which contains more chromium and more carbon but less silicon (0.2 wt%), less molybdenum and less nickel, hardens during irradiation at 373 °C, but shows less hardening for irradiations performed at 427 °C and no increase in yield stress with increasing dose beyond 10 dpa.

Intergranular embrittlement due to grain boundary segregation of phosphorus is recognized as one of the potential degradation factors in irradiated reactor low alloy steels at high neutron fluence. In this study, low alloy steels thermally aged at 400-500°C were investigated to evaluate the correlation between phosphorus segregation and intergranular embrittlement. Phosphorus segregation determined using Auger electron spectroscopy increased after thermal aging above 450°C and was in good agreement with the calculated value based on McLean's model. No influence of thermal aging on tensile properties or hardness was observed. The ductile brittle transition temperature determined using a one-third size Charpy impact test increased at a P/Fe peak ratio of 0.14. These results indicated that there is a threshold level of phosphorus segregation for non-hardening embrittlement. The ductile to brittle transition temperature (DBTT) increased with the proportion of intergranular fracture, so this result shows that ...

Neutrophils and macrophages infiltrate after acetaminophen (APAP)-induced liver injury starts to develop. However, their precise roles still remain elusive. In untreated and control IgG-treated wild-type (WT) mice, intraperitoneal APAP administration (750 mg/kg) caused liver injury including centrilobular hepatic necrosis and infiltration of neutrophils and macrophages, with about 50% mortality within 48 h after the injection. APAP injection markedly augmented intrahepatic gene expression of inducible nitric oxide synthase (iNOS) and heme oxygenase (HO)-1. Moreover, neutrophils expressed iNOS, which is presumed to be an aggravating molecule for APAP-induced liver injury, while HO-1 was mainly expressed by macrophages. All anti-granulocyte antibody-treated neutropenic WT and most CXC chemokine receptor 2 (CXCR2)-deficient mice survived the same dose of APAP, with reduced neutrophil infiltration and iNOS expression, indicating the pathogenic roles of neutrophils in APAP-induced liver injury. However, APAP caused more exaggerated liver injury in CXCR2-deficient mice with reduced macrophage infiltration and HO-1 gene expression, compared with neutropenic WT mice. An HO-1 inhibitor, tin-protoporphyrin-IX, significantly increased APAP-induced mortality, implicating HO-1 as a protective molecule for APAP-induced liver injury. Thus, CXCR2 may regulate the infiltration of both iNOS-expressing neutrophils and HO-1-expressing macrophages, and the balance between these two molecules may determine the outcome of APAP-induced liver injury.

It is well known that the intake of paraquat (PQ), an herbicide, causes severe lung injury at chronic phases. We examined the intrapulmonary gene expression of cytokines and growth factors after PQ administration. To induce lung injury, C57BL/6 mice were intraperitoneally injected twice a week with 20 mg/kg of PQ. Histopathologically, at the early phase, lots of alveolar spaces contained edematous fluid. At 3 weeks after PQ challenge, a marked thickening of the alveolar walls with the accumulation of macrophages and T cells was found. Azan staining revealed the patchy distribution of collagen accumulation, indicating pulmonary fibrosis. Consistently, intrapulmonary hydroxyproline contents were significantly elevated, compared with the controls. Semi-quantitative RT-PCR analysis demonstrated that the gene expression of tumor necrosis factor-alpha and monocyte chemoattractant protein-1 were significantly increased at 3 weeks after PQ challenge compared with the controls. The mRNA expression of macrophage inflammatory protein (MIP)-1alpha and MIP-2 was significantly enhanced at 1 and 2 weeks after PQ treatment, respectively. Moreover, PQ-treated mice showed enhanced gene expression of fibrogenic growth factors such as transforming growth factor-beta, platelet-derived growth factor-A, acidic fibroblast growth factor, and hepatoctyte growth factor at 2 and/or 3 weeks after PQ challenge. The synergistic effects of these molecules are presumed to cause pulmonary fibrosis due to PQ challenge.

Fracture toughness of blanket structural materials is one of the important material engineering properties to design structural components and evaluate the degradation during reactor operation. The present study showed that the master curve (MC) methodology to evaluate change in fracture toughness in the cleavage regime of a reduced-activation ferritic (RAF) steel before and after a thermal embrittlement treatment was applied by using sub-sized compact tension (CT) specimens. The reference temperature of MC for the JLF-1LN steel was estimated as −52 °C by using 1/2CT specimens. The shift of the reference temperature obtained by the MC methodology was judged to be somewhat larger than that of the ductile–brittle transition temperature shift obtained by the Charpy impact tests.

Various oxide dispersion strengthened (ODS) steels which have high Cr concentrations with and without Al addition were made by mechanical alloying method. Corrosion measurement was done in the closed system of super critical pressurized water (SCPW) at 783 K with the pressure of 25 MPa. In order to evaluate the mechanical properties and the effect of thermal aging, a miniaturized Charpy V notch (MCVN) test and tensile test were performed before and after aging at 773 K up to 1000 h. The susceptibility to stress corrosion cracking (SCC) of high Cr-ODS steels was evaluated by slow strain rate test (SSRT). The SSRT was performed in a simulated boiling water reactor (BWR) condition with high temperature oxygenated (8–10 ppm) water at 561 K and at a pressure of 7.8 MPa. Strain rates were ranging from 1 × 10 −4 to 3 × 10 −7 s −1 . The high Cr-ODS steels showed a better resistance to corrosion than SUS316L stainless steel in SCPW. The 14Cr and 16Cr-ODS steel did not suffer from aging embrittlement at 773 K for 1000 h. The ODS steels showed no susceptibility to SCC at strain rates from 1 × 10 −4 to 3 × 10 −7 s −1 .

The reduced activation ferritic steel (RAFS) has been selected as structural material for a variety of blanket systems for ITER test blanket modules (TBM). In the evaluation of integrated performance of ferritic steels as structural components of blanket systems, there are unique issues as well as common issues for each blanket system. One of the unique issues for each system is the compatibility of ferritic steels with the coolant materials. The corrosion rate of ferritic steels in hot water, super critical pressurized water (SCPW), humid air, Pb–17Li, lithium and Flibe at various temperatures is reviewed in this work. Efforts to improve corrosion resistance have been made, taking the alloy design into account. A dispersion of yttria was effective to improve corrosion resistance of a RAFS. The compatibilities of RAFSs with hot water, Pb–17Li, lithium and Flibe are considered to be good enough for the TBM applications. The liquid metal embrittlement (LME) is considered to be a critical issue for the utilization of RAFSs for the lithium systems. Several issues towards DEMO and beyond are shown from the compatibility point of view.

The mission of the National Centralized Tokamak (NCT) is to establish high-beta steady-state plasma operation for DEMO and to contribute to ITER. Plasma performance with high-beta conditions is discussed. It is found that near break-even class plasma ( Q DT eq ≥ 0.7 ) with high beta ( β N ≥ 3.5) is achievable with 25 MW of NB power at I P = 4.0 MA and an aspect ratio of 2.6. High beta with steady-state full current drive is possible with 13 MW of NB power at I P = 1.5–1.7 MA. In the engineering design activity of NCT, the strength of the support structure and strength of material for the conductor is confirmed for the superconducting coils, and the successful progress of R&D of boron-loaded resin for neutron shielding is discussed.

A dual-ion irradiation method is one of the most popular techniques for the research of microstructural evolution of materials under fusion environmental conditions. The application of oxide dispersion strengthened (ODS) ferritic steels is anticipated for realization of high temperature operation of fusion reactors above 600 °C. In this research, the investigation of the microstructural evolution of high corrosion resistant ODS steels was performed using the ion irradiation methods. Dual ion-irradiation experiments were performed at the DuET facility, Kyoto University using 6.4 MeV Fe self-ion and 1 MeV helium ion. The irradiation temperatures were 300 and 500 °C. The dose, dose rate, and helium over dpa ratio were 20 dpa, 5 × 10−4 dpa/s, and 15 appm/dpa, respectively. The post-irradiation experiments were performed using SEM, TEM and the nano-indentation methods. Significant microstructural evolution of grains and oxides were not observed after the single-ion irradiation at 20 dpa, 500 °C. Fine helium cavities were observed in the dual-ion irradiated 19Cr–2W–4Al ODS steel. Fine cavities of approximately several nanometers diameter were densely and uniformly formed in dual-ion irradiated range.

Antimicrobial peptides (AMPs) are effector molecules of innate immunity. Dermcidin (DCD), a recently discovered AMP with broad-spectrum activity, is produced constitutively by the eccrine sweat glands and secreted into sweat. In this study, we investigated the proteolytic processing, site-specific expression, and stability of DCD peptides in eccrine sweat. Using surface-enhanced laser desorption ionization time-of-flight mass spectrometry (SELDI-TOF-MS) and reversed-phase high-pressure liquid chromatography analysis, we identified in eccrine sweat 14 proteolytically processed DCD peptides. Semiquantitative SELDI-TOF-MS analysis indicated that processing of DCD-1L is individually different, but generates a few dominant peptides. At body sites with a high probability for contact with pathogenic microorganisms, a high amount of antimicrobial active DCD peptides was detected in sweat. Furthermore, we show that the secretion rate of DCD is constant during a period of prolonged sweating and that DCD peptides are stable in sweat over several hours. Other known AMPs like the human cathelicidin LL-37 and alpha- or beta-defensins were not detected in significant quantity in eccrine sweat. Owing to the durable and abundant presence, DCD-derived peptides contribute to the first line of defense by building a constant barrier that overlies the epithelial skin.

Japan is performing design and technology developments for the purpose of module testing and contribution to the module development and testing under the framework of Test Blanket Working Group (TBWG) with involvements of all of Japan Atomic Energy Research Institute (JAERI) and universities and National Institute for Fusion Science (NIFS). As the primary blanket option, solid breeder test blanket modules (TBMs) with reduced activation ferritic steel structure is being developed and proposed to be delivered on the first day of ITER operation, mainly by JAERI. As for the advanced blanket options, mainly universities and NIFS have been performing R&D of key technologies and design concept development of solid breeder blanket test article made of SiC composite contained inside the ferritic steel box, liquid LiPb breeder blanket TBM cooled by helium and its dual-coolant option, liquid Li self-cooled blanket TBM and molten salt self-cooled TBM. In all necessary fields of the development of the primary blanket option, the element technology development phase has been almost completed and is now stepping further to the engineering test phase. The development of advanced test blankets is also showing steady progress to overcome key issues toward module testing.

腹部鈍的外傷による腸管損傷は穿孔,断裂,出血など急性の発症がほとんどであるが,稀に遅発性に腸管狭窄をきたすことがある.今回われわれは,中でも稀とされる遅発性大腸狭窄を経験した.症例は77歳,女性.移動式階段にて作業中に転落.階段が体幹に落下し,胸腹部を強打,当院へ救急搬送された.臓器損傷,消化管穿孔の所見は認めず,保存的加療にて軽快し,受傷後31日目に退院.その後, 51日目に腸閉塞様症状が出現し,再入院となった.諸検査にて横行結腸肝彎曲寄りに高度の狭窄を認め,遅発性大腸狭窄と診断し,受傷後69日目に開腹手術を行った.右上腹部に右側結腸,腸間膜,大網などが一塊となった炎症性の腫瘤を形成し,横行結腸に高度な狭窄を呈していたため,結腸部分切除術を施行した.組織学的には腸管壁全層の肉芽形成,異物巨細胞の出現も認めており,穿通の存在も示唆された.腹部外傷の診療の際は本疾患も念頭に置く必要があると思われた.

Design studies are shown on the National Centralized Tokamak facility, formerly called JT-60SC. The machine design is carried out to investigate the capability for flexibility in aspect ratio and shape controllability for the demonstration of the high-β steady state operation with nation-wide collaboration, in parallel with ITER towards DEMO. Two designs are proposed and assessed with respect to the physics requirements such as confinement, stability, current drive, divertor and energetic particle confinement. The operation range in the aspect ratio and the plasma shape is widely enhanced consistent with sufficient divertor pumping. Evaluations of the plasma performance towards the determination of the machine design are presented.

The NLF series of steels are reduced activation ferritic–martensitic (RAFM) steels that are a part of the Japanese program to produce a suitable reduced activation ferritic–martensitic steel for the ITER project. Published reports on the NLF steels after about 35 dpa at 400 °C by Kurishita et al., indicate that these steels have similar strength and better ductility than other RAFM steels such as the JLF steels and F82H irradiated at 400 °C to similar doses. The tensile properties of NLF steels irradiated at ∼400 °C to doses as high as 67 dpa are presented here. Tensile tests were conducted at a strain rate of 5 × 10−4 s−1 at 25, 400 °C, and 500 °C. Variations in irradiation temperature in the range of 390–430 °C had a relatively small, but definite effect on the tensile properties for tests conducted at 25, 400, and 500 °C. The strongest hardening is observed for specimens irradiated at 390 °C, and very little hardening is observed for specimens irradiated at 430 °C. Strain rate jump tests were performed on NLF-0 and NLF-1 at 400 °C after irradiation to 52 dpa. The rate sensitivity, m, is quite low, 0.003–0.005 and does not appear to be affected by irradiation at 52 dpa for an irradiation temperature of 430 °C.

Japanese activities on fusion structural materials R & D have been well organized under the coordination of university programs and JAERI/NIMS programs more than two decades. Where, two categories ...

The Fusion Council of Japan has established the long-term program for the development of blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan, while liquid breeder blankets and high temperature solid breeder blanket have been identified as the attractive advanced blanket. Japan Atomic Energy Research Institute (JAERI) is leading the development of solid breeder blankets, while, universities and National Institute for Fusion Science (NIFS) are developing the advanced blankets for potential options of the fusion power demonstration plant and commercial power plants. ITER blanket module testing is regarded as one of the most important milestones, by which integrity of candidate blanket design is qualified for the fusion power demonstration plant, together with material irradiation data by International Fusion Material Irradiation Facility (IFMIF). Japan is investigating the possibility of testing all types of blankets under TBWG framework with both of JAERI and universities/NIFS involvements. This paper presents a plan and strategy for the development of test blanket modules and ITER blanket module testing in Japan.

For this study, we investigated why cholestasis develops into neonatal intrahepatic cholestasis caused by citrin deficiency (NICCD), and concluded that primary mitochondrial impairment associated with the delayed maturity of bile acid metabolism may contribute to the occurrence of NICCD.

Thermal helium desorption measurements were performed to investigate the difference in the helium trapping and accumulation behavior among a reduced activation ferritic (RAF) steel and oxide dispersion strengthening (ODS) steels after implantation of He + ions at room temperature. Thermal helium desorption spectra (THDS) were obtained during annealing to 1200 °C at a heating rate of 1 °C/s. The THDS of the ODS steels are very similar to that of the RAF steel, except for the presence of the peak in the temperature range from 800 to 1000 °C, where the α–γ transformation related helium desorption from the γ-phase is considered to occur in the 9Cr-ODS martensitic steels. The fraction of helium desorption becomes larger at higher temperatures, and this trend is increased with the amount of implanted helium. In the 9Cr-ODS steels, the fraction of helium desorption by bubble migration mechanism was smaller than that in the RAF steel. This suggests that the bubble formation was suppressed in the ODS steels. In the 12Cr-ODS steel, the fraction of helium desorption by bubble migration reached more than 90%, suggesting that the trapping capacity of martensite phase in the 9Cr-ODS steel is rather large.

To clarify the pathophysiological mechanism underlying acute renal injury caused by acute exposure to arsenic, we subcutaneously injected both BALB/c and C57BL/6 mice with sodium arsenite (NaAs; 13.5 mg/kg). BALB/c mice exhibited exaggerated elevation of serum blood urea nitrogen (BUN) and creatinine (CRE) levels, compared with C57BL/6 mice. Moreover, half of BALB/c mice died by 24 h, whereas all C57BL/6 mice survived. Histopathological examination on kidney revealed severe hemorrhages, acute tubular necrosis, neutrophil infiltration, cast formation, and disappearance of PAS-positive brush borders in BALB/c mice, later than 10 h. These pathological changes were remarkably attenuated in C57BL/6 mice, accompanied with lower intrarenal arsenic concentrations, compared with BALB/c mice. Among heavy metal inducible proteins including multidrug resistance-associated protein (MRP)-1, multidrug resistance gene (MDR)-1, metallothionein (MT)-1, and arsenite inducible, cysteine- and histidine-rich RNA-associated protein (AIRAP), intrarenal MDR-1, MT-1, and AIRAP gene expression was enhanced to a similar extent in both strains, whereas NaAs challenge augmented intrarenal MRP-1 mRNA and protein expression levels in C57BL/6 but not BALB/c mice. Moreover, the administration of a specific inhibitor of MRP-1, MK-571, significantly exaggerated acute renal injury in C57BL/6 mice. Thus, MRP-1 is crucially involved in arsenic efflux and eventually prevention of acute renal injury upon acute exposure to NaAs.

原発巣不明の腺癌腹腔内リンパ節転移例に膵頭部腫瘍との鑑別が困難であったためPDを施行したが原発巣不明のまま再発兆候なく8年経過した症例を経験した.症例は85歳,女性.食欲不振,体重減少のため消化器精査を行った.腹部CT, USで膵頭部に4.2×3.6cmの腫瘤を認めた. ERCPでは膵管に異常なく,腹部血管造影で腫瘍濃染を認めた. USガイド下穿刺細胞診は陽性で術前膵島細胞腫瘍を疑った.手術所見では5×3cmの腫瘍が総肝動脈を巻き込み膵頭部より外方に発育しNo.8リンパ節との鑑別が問題になったがPDを行った.術後の病理組織診断では腫瘍は膵と連続性はなくリンパ節に限局し転移性腺癌と診断された.膵,胆管内に原発巣は認めなかった.原発不明癌でも腹腔内リンパ節転移の場合他臓器の合併切除が必要なこともあり,根治性をどこまで追及するか苦慮する点であるが,本症例ではこの手術でcurative operationを行い得たと考えている.

Reduced-activation ferritic/martensitic (RAF/M) steels have been considered to be the prime candidate for the fusion blanket structural material. The irradiation data obtained up to now indicates rather high feasibility of the steels for application to fusion reactors because of their high resistance to degradation of material performance caused by both the irradiation-induced displacement damage and transmutation helium atoms. The martensitic structure of RAF/M steels consists of a large number of lattice defects before the irradiation, which strongly retards the formation of displacement damage through absorption and annihilation of the point defects generated by irradiation. Transmutation helium can be also trapped at those defects in the martensitic stricture so that the growth of helium bubbles at grain boundaries is suppressed. The major properties of the steels are well within our knowledge, and processing technologies are mostly developed for fusion application. RAF/M steels are now certainly ready to proceed to the next stage, that is, the construction of International Thermo-nuclear Experimental Reactor Test Blanket Modules (ITER-TBM). Oxide dispersion strengthening (ODS) steels have been developed for higher thermal efficiency of fusion power plants. Recent irradiation experiments indicated that the steels were quite highly resistant to neutron irradiation embrittlement, showing hardening accompanied by no loss of ductility. High-Cr ODS steels whose chromium concentration was in the range from 14 to 19 mass% showed high resistance to corrosion in supercritical pressurized water. It is shown that the 14Cr-ODS steel is susceptible to neither hydrogen nor helium embrittlement. A combined utilization of ODS steels with RAF/M steels will be effective to realize fusion power early at a reasonable thermal efficiency.

Validity of nickel isotope tailoring (NIT) method to be able to generate a large amount of transmutation helium in 9%Cr-2%W reduced activation ferritic (RAF) steel for fusion reactor structural material was investigated and discussed through mechanical properties and microstructural evolution after fission neutron irradiation. Miniature tensile and Charpy impact specimens of RAF steels and 1% nickel added RAF steel were irradiated in the ATR-A1 to evaluate irradiation hardening and shift in ductile-brittle transition temperature (� DBTT). The amount of transmutation helium in all the RAF steels with and without nickel addition was calculated as only about 0.6 appm. After irradiation at 621 K, theDBTT for the 1% nickel added steel was similar for the JLF-1. After irradiation at 543 K, however, theDBTT for the 1% nickel added steel was significantly larger than that for the JLF-1. Microstructure observations revealed that irradiation-induced dislocation loops in the 1% nickel added steel were finer and denser than in the RAF steel without nickel addition, suggesting that the nickel addition to the RAF steels directly affected nucleation and growth processes of dislocation loops and enhanced irradiation hardening and embrittlement. Therefore, there is a limit in the NIT method as a simulation method for understanding effects of helium on irradiation embrittlement of RAF steels. The RAF steels used in the present study were JLF-1, Mod.JLF-1/LSM and Mod.JLF-1/LSM/Ni. (The ''LSM'' means low concentration of Si and Mn compared with the JLF-1.) The chemical compositions and the heat treatments of these steels are shown in Table 1. Mod.JLF-1/LSM/Ni contained 1 weight percentage of natural nickel. Neutron irradiation was carried out in the two sub-capsules of the ATR-A1, AS4 and AS16, in the Advanced Test Reactor (ATR) at Idaho National Engineering and Environ- mental Laboratory for 132.9 Effective Full Power Days (EFPDs). 11) Irradiation temperature and displacement dam- age were estimated for the two sub-capsules as at 543 K to 2.2 dpa and 621 K to 3.4 dpa. These sub-capsules were equipped with gadolinium shields of 1.7 mm in thickness to reduce the thermal neutron flux in order to suppress trans- mutation effects. The amount of transmutation helium was also suppressed due to the thermal shields. Greenwood et al. calculated the concentration of transmutation helium as 0.6 appm in Mod.JLF-1/LSM/Ni and 0.5 appm in the other RAF steels without nickel addition, respectively. 12)

The degradation of mechanical properties in RPV clad by the presence of σ-phase and neutron irradiation was investigated using small punch (SP) tests. The irradiation doses at 290 °C ranged from 5.01 × 10 18 to 5.79 × 10 19 n/cm 2 (>1 MeV). After irradiation, the increase in SP ductile-to-brittle transition temperature (SP-ΔDBTT) was ≈14 K, independent of the fluence. However, it was more strongly affected by the amount of brittle σ-phase. The cracking appearances in the SP specimens gradually changed from circumferential to radial cracking as a function of test temperature, content of σ-phase and neutron irradiation. These results are discussed in terms of the different fracture stress of each phase as well as the irradiation-induced hardening combined with the changes of governing stress components for crack initiation during deformation by means of finite element stress analysis.

Oxide dispersion strengthened (ODS) ferritic and martensitic steels are promising materials for fuel cladding in fast reactors and for structural materials in fusion reactors. ODS steels for fuel cladding in fast reactors have been developed by Japan Nuclear Cycle Development Institute (JNC). The first generation ODS steels had a serious problem from anisotropy in their mechanical properties. Recently, this problem has been solved by controlling grain shape as equiaxed grains. Three types of modified ODS steels were irradiated in the experimental fast reactor JOYO for investigation of the irradiation-induced microstructural changes. The dispersed oxide particles were very stable when irradiated. In addition, dislocation structure development was minor. The high resistance to irradiation-induced microstructural changes in the ODS steels was attributed to oxide particles which acted as sinks for point defects.

Thermal desorption spectra (TDS) analysis and transmission electron microscopy (TEM) observation were performed to investigate microstructural evolution in Fe and Fe–X at.% Cr (X=5.0, 15) model alloys during thermal annealing after irradiation with 8 keV He+ ions at room temperature. TDS analysis showed that there is not so much difference in He desorption during post-irradiation annealing between Fe and Fe–Cr alloys, but the amount of He desorption depended on the Cr concentration of the samples. As for TEM observation, a number of interstitial dislocation loops was observed in all the samples even before post-irradiation annealing, while He bubbles were observed in all the samples only after annealing at temperatures greater than 773 K. Microstructural evolution observed by TEM also depended on Cr concentration. The effect of solute Cr addition on the mobility of interstitial loop and He bubbles is discussed.

The effects of hydrogen on the mechanical properties of oxide dispersion strengthened (ODS) steels were investigated by means of tensile tests at room temperature. Cathodic hydrogen charging was carried out before and during deformation in a sulfuric acid solution by imposing a constant current density in the range of 100 to −520 A/m 2 . With increasing charging current density, the loss of ductility increased accompanied by a change in fracture mode from ductile to intergranular fracture. The critical hydrogen concentration in ODS steels required to transition from ductile to brittle fracture was in the range of 10–12 wppm, which approximately 10 times larger than that of a 9Cr–2W martensitic steel. In addition, the susceptibility to hydrogen embrittlement of ODS steels strongly depended on specimen sampling orientation.

The effects of alloying elements on corrosion resistance in super critical pressurized water (SCPW) have been investigated to develop corrosion resistant oxide dispersion strengthened (ODS) steels. Corrosion tests were performed in a SCPW (783 K, 25 MPa) environment. Weight gain was measured after exposure to the SCPW. For the improvement of corrosion-resistance, the effects of chromium, aluminum, and yttrium on the corrosion behavior were investigated. The 9–12 wt%Cr ODS steels showed almost similar corrosion behavior with the ordinary ferritic/martensitic steel in the SCPW. However, the addition of high chromium (>13 wt%) and aluminum (4.5 wt%) are very effective to suppress the corrosion in the SCPW. Anodic polarization experiments revealed that the passive current of the ODS steels are lower than the ordinary ferritic/martensitic steels. Addition of aluminum improves the Charpy impact property of the ODS steels.

Significant progress has been achieved in the international research effort on reduced-activation steels. Extensive tensile, fracture toughness, fatigue, and creep properties in unirradiated and irradiated conditions have been performed and evaluated. Since it is not possible to include all work in this limited review, selected areas will be presented to indicate the scope and progress of recent international efforts. These include (1) results from mechanical properties studies that have been combined in databases to determine materials design limits for the preliminary design of an ITER blanket module. (2) Results indicate that the effect of transmutation-produced helium on fracture toughness is smaller than indicated previously. (3) Further efforts to reduce irradiation-induced degradation of fracture toughness. (4) The introduction of a post-irradiation constitutive equation for plastic deformation. (5) The production of ODS steels that have been used to improve high-temperature strength. (6) The method developed to improve fracture toughness of ODS steels.

Four different sizes of compact tension (CT) specimens of a reduced activation ferritic steel, JLF-1 steel, were fabricated and the fracture toughness was measured at room temperature by means of the unloading compliance method referring to in the ASTM E1820-99a. The J Q values obtained for the 1T–1CT and 1/2T–1CT specimens were 404 and 623 kJ/m 2 , respectively, indicating that the J Q value increased with decreasing the specimen thickness. On the other hand, the J Q value decreased when specimens were miniaturized while maintaining the similar proportions. The J Q values for the 1/2CT and 1/4CT specimens were 371 and 321 kJ/m 2 , respectively. Specimen size effects are interpreted in terms of an increase in the plain stress state region and plastic zone size at the crack tip in the specimen.

The effects of fast neutron irradiation on ring-tensile properties of the oxide dispersion strengthened (ODS) ferritic/martensitic steel claddings with improved microstructural isotropy from recrystallization and α–γ phase transformation were investigated. The samples were irradiated in the experimental fast reactor JOYO using the material irradiation rig at temperatures between 670 and 807 K to fast neutron fluences ranging from 5.0 × 1025 to 3.0 × 1026 n/m2 (E>0.1 MeV). The post-irradiation ring-tensile tests were carried out on samples with five sets of irradiation conditions. The experimental results showed that strengths were increased by 10% due to irradiation. Microstructural improvement considerably increased elongations for these samples and specimens retained respectable elongation after irradiation. The ring-tensile properties of these ODS steel claddings remain excellent within the fluence level achieved in this study.

Death-associated protein kinase (DAPK) is a calcium/calmodulin-dependent serine/threonine kinase localized to renal tubular epithelial cells. To elucidate the contribution of DAPK activity to apoptosis in renal ischemia-reperfusion (IR) injury, wild-type (WT) mice and DAPK-mutant mice, which express a DAPK deletion mutant that lacks a portion of the kinase domain, were subjected to renal pedicle clamping and reperfusion. After IR, DAPK activity was elevated in WT kidneys but not in mutant kidneys (1785.7 +/- 54.1 pmol/min/mg versus 160.7 +/- 60.6 pmol/min/mg). Furthermore, there were more TUNEL-positive nuclei and activated caspase 3-positive cells in WT kidneys than in mutant kidneys after IR (24.0 +/- 5.9 nuclei or 9.4 +/- 0.6 cells per high-power field [HPF] versus 6.3 +/- 2.2 nuclei or 4.4 +/- 0.7 cells/HPF at 40 h after ischemia). In addition, the increase in p53-positive tubule cells after IR was greater in WT kidney than in mutant kidneys (9.9 +/- 1.4 cells/HPF versus 0.8 +/- 0.4 cells/HPF), which is consistent with the theory that DAPK activity stabilizes p53 protein. Finally, serum creatinine levels after IR were higher in WT mice than in mutant mice (2.54 +/- 0.34 mg/dl versus 0.87 +/- 0.24 mg/dl at 40 h after ischemia). Thus, these results indicate that deletion of the kinase domain from DAPK molecule can attenuate tubular cell apoptosis and renal dysfunction after IR injury.

Clostridium difficile has emerged as the important causative agent of antibiotics-associated pesudomembranous colitis; especially its toxin A is presumed to be responsible for the colitis. We examined the pathophysiological roles of IFN-γ in toxin A-induced enteritis using IFN-γ knockout (KO) mice. When toxin A of C. difficile was injected into the ileal loops of BALB/c wild-type (WT) mice, massive fluid secretion, disruption of intestinal epithelial structure, and massive neutrophil infiltration developed within 4 h after the injection. IFN-γ protein was faintly detected in some CD3-positive lymphocytes in the lamina propria and submucosa of the ileum of untreated WT mice. On the contrary, at 2 and 4 h after toxin A injection, IFN-γ protein was detected in infiltrating neutrophils and to a lesser degree in CD3-positive lymphocytes. In the ileum of WT mice, toxin A treatment markedly enhanced the gene expression of TNF-α, macrophage inflammatory protein-1α and -2, KC, and ICAM-1 >2 h after treatment. In contrast, the histopathological changes were marginal, without enhanced fluid secretion in the ileum of toxin A-treated IFN-γ KO mice. Moreover, toxin A-induced gene expression of TNF-α, neutrophil chemotactic chemokines, and ICMA-1 was remarkably attenuated in IFN-γ KO mice. Furthermore, pretreatment of WT mice with a neutralizing anti-IFN-γ Ab prevented toxin A-induced enteritis. These observations indicate that IFN-γ is the crucial mediator of toxin A-induced acute enteritis and suggest that IFN-γ is an important molecular target for the control of C. difficile-associated pseudomembranous colitis.

The effects of neutron irradiation on the microstructural features and mechanical properties of 309L stainless steel RPV clad were investigated using TEM, SEM, small tensile, microhardness and small punch (SP) tests. The neutron irradiations were performed at 290 °C up to the fluences of 5.1 × 1018 and 1.02 × 1019 n/cm2 (>1 MeV) in Japan Materials Testing Reactor (JMTR). The microstructure of the clad before and after irradiation was composed of main part of fcc austenite, a few percent of bcc δ-ferrite and small amount of brittle σ phase. After irradiation, not only the yield stress and microhardness, but SP ductile to brittle transition temperature (SP-DBTT) were increased. However, the increase in SP-DBTT is almost saturated, independent of the neutron fluence. Based on the TEM observation, the origin of irradiation hardening was accounted for by the irradiation-produced defect clusters of invisible fine size (

The factors controlling irradiation hardening and their contributions to the hardening in electron irradiated pure-iron and Fe-0.15 mass%Cu alloy were determined by means of post-irradiation annealing experiments, such ashardness measurements, positron annihilation spectroscopy (PAS) measurements, transmission electron inl rottope (TMM) observations and three dimensional atom probe (3DAP) analyses, In pure-iron, almost complete recovering of the hardness was obterved after the annealing to 773 K, which was accompanied by disapearing of the interstitial type dislocation loops (1-loops) that were observed in as-irradiated specimen. In contrast, the hardening of Fe-0.15 mas %Cu alloy recovered in a two-step mode; about a half of the hardening recovered by the 773 K annealing, and a complete recovety was observed after annealing to 973 K. Most of the I-loops observed in as-irradiated specimen again elisappeared after the annealing to 773 K. These clearly show that the 1-loops are one of the main factors controlling irradiation hardening in iron-copper alloy. The residual hardening in the Fe-0.15 mass%Cu alloy after the annealing to 773 K, which is about a half of the irradiation hardening, was attributed to the copper-rich precipitates (CRP) through the direct observation by 3DAP analysis. PAS measurements revealed the disagreement between the recovery behaviors of the hardness and lifetime parameters. Based on the quantitative data analysis, it was concluded that the factor controlling the irradiation hardening of pure-iron is the I-loops, and those in Fe-0.15 mass%Cu alloy are both the I-loops and CRP of which the contributions to the hardening are almost same.

The Japanese reduced activation ferritic steels (RAFSs) R&D road map towards DEMO is shown. The important steps include high-dose irradiation in fission reactors such as the high flux isotope reactor at Oak Ridge National Laboratory, irradiation tests with 14 MeV neutrons in the International Fusion Materials Irradiation Facility and application to ITER test blanket modules to provide an adequate database of RAFSs for the design of DEMO. The current status of RAFS development is also introduced. The major properties of concern are well-known, and process technologies are mostly ready for fusion application. RAFSs are now certainly ready to proceed to the next stage. A materials database is already in hand, and further progress is anticipated with the design of the ITER test blanket. Oxide dispersion strengthening steels are quite promising for high temperature operation of the blanket system, with potential improvements in radiation resistance and in corrosion resistance.

(2003). Genocide and the modern mind: intention and structure. Journal of Genocide Research: Vol. 5, No. 3, pp. 405-420.

The Varying Temperature Irradiation Experiment in the High Flux Isotope Reactor (HFIR) was carried out in the framework of the Japan-USA fusion cooperation program (JUPITER). The objective of the experiment is to investigate the performance of fusion structural materials subject to temperature variation during operation. The experiment will also contribute to re-examining the available fission reactor irradiation data including temperature transient. The irradiation for the experiment was performed from July 1998 to May 1999. Some results of the Post-Irradiation Examination are now available. This paper summarizes the highlights of the experimental results and insights obtained through the experiment about the temperature variation effects on materials performance under irradiation.

The influence of σphase on mechanical properties in type ER309L stainless steel has been investigated by small punch test. The SA508 cl.3 reactor pressure vessel steel plates were overlay-cladded with the type ER309L welding consumable with different heat input rates. The microstructure of the clad was composed of fcc γ-austenite, a few percent of bcc δ-ferrite and bct σ-phase. Area fraction of σ-phase was ranging approximately 2–8% depending on the welding condition. Ductile to brittle transition behavior was observed in the clad, and it was strongly affected by the amount of brittle σ-phase. When the σ-phase content was about 8 percent, the transition behavior almost disappeared due to severe cracking. Fracture appearance gradually changed from circumferential to radial cracking not only as test temperature became low but as the volume fraction of σ-phase increased. The results are manifested in terms of fracture stress of σ-phase and δ-ferrite combined with the roles of radial and circumferential stres...

Reduced Activation Ferritic/Martensitic steels (RAFs) are leading candidates for blanket and first wall structures of the D-T fusion reactors. Recently, in order to achieve better efficiency of energy conversion by using RAFs in advanced blanket systems, improvement of high temperature mechanical property of RAFs is desired. In this work, experimental alloys, FETA-series (Fe-Ta-C or N) steels, were prepared to observe precipitation hardening mechanism by MX-type particles at elevated temperatures in detail. According to the results, innovative improvement of creep property can be achieved by applying of precipitation hardening by very fine TaX (X=C, N) particles. With increasing tantalum content, finer dispersion of MX-type particles, dislocation structures and sub-grain structures were observed by TEM (Transmission Electron Microscopy). These fine structures contributed to the improvement of creep property.

Identification of body fluids is a common task in medico-legal practice, but specific markers for sweat have not been identified to date. To develop a method for identification of sweat, we identified a sweat-specific protein and produced monoclonal antibodies by immunizing mice with sweat proteins fractionated by anion-exchange chromatography. Among many sweat-reactive monoclonal antibodies obtained, one monoclonal antibody (G-81) was selected because of its unique specificity. G-81 reacted to sweat but not to other body fluids (e.g. serum, saliva, semen, milk, urine and tears) in ELISA. G-81 specifically stained the eccrine sweat gland and did not stain any other tissue including the apocrine sweat gland. In western blotting, G-81 reacted strongly to a 7 kDa band and faintly to 20, 27 and 33 kDa bands of sweat protein. The N-terminal amino acid sequence (18 amino acids) of G-81-reactive peptides was determined, and an identical sequence was found in an antibiotic peptide dermcidin (110 amino acids) reported recently, suggesting that G-81 recognized a fragment of dermcidin. The G-81-reactive peptide could be detected in 8,192-fold dilutions of sweat by ELISA and could be detected in 200-fold diluted sweat samples ( n=26) independent of the protein concentration. The G-81-reactive peptide was very stable and was able to detect sweat stains left for at least 11 weeks at room temperature without substantial loss of reactivity. These facts suggest that G-81 is a very useful tool for sweat identification in medico-legal practice.

Fermented fresh coffee bean, soybean and rice bran extracts (FCSRE, GuardoxTM) is a mixture of aqueous extract of fresh coffee beans, rice bran, and soybeans fermented with Bacillus subtilis Natto. Superoxide anion and hydroxy radical were effectively trapped by FCSRE, as shown by electron spin resonance experiments. Thiobarbituric acid reacting substance (TBARS) formation in human low-density lipoprotein (LDL) induced by copper ion was inhibited by adding FCSRE (0.1 mg/dl) in vitro. Male New Zealand white rabbits were assigned to two groups, control rabbits (n=8) were fed a diet containing 1% cholesterol for 12 weeks, and experimental rabbits (n=8) were fed a 1% cholesterol diet with added 5% FCSRE (2 g/kg body weight/day). Although plasma cholesterol levels rapidly increased after initiation of the high cholesterol diet, no statistical difference was observed between the control and experimental groups. After 12 weeks, sera were sampled, rabbits were sacrificed, and aortas were removed. TBARS formation in LDL induced by copper ion was significantly lower in the experimental group compared with the control group. Lag time of LDL oxidation was also significantly longer in the experimental group. FCSRE administration significantly inhibited the TBARS formation in the aorta compared with the control animals. There was a significant difference in the aortic area covered with atherosclerotic lesions between the experimental and the control groups (53.7±16.3% vs. 36.2±8.18%, p

In forensic practices, cases of sudden unexpected death are often encountered, and the clarification of the cause of death is always required. Ischemic heart disease such as acute myocardial infarction is the most frequent as the cause of sudden unexpected internal death [1]. Moreover, endocrinological disorder is closely related with sudden unexpected death [1–3]. In particular, thyrotoxicosis is well known as the cause of sudden unexpected death [4–8]. Recently, several lines of accumulating evidence demonstrated that thyroid dysfunction increased the risk of cerebral vascular diseases [9] and ischemic heart diseases [10–12]. Herewith, we report a case of acute myocardial infarction in a young female with untreated hyperthyroidism. In the morning of one day, a 25-year-old female consulted to a neighbor clinic, because of her pericardial pain about 9:00 AM. There were no significant findings in both electrocardiogram and blood chemistry. Shewasmedicated with analgesics and sedatives (pentazocine and diazepam) at 9:15 and 9:30 AM and her condition seemed to be better, under the observation in the clinic. However, at 10:40 AM, she suddenly suffered cardiopulmonary arrest, and then shewas immediately intubated and then conveyed to an emergency hospital by an ambulance (arrival at 11:08 AM). Despite intensive care treatment, her death was confirmed at 0:35 PM. According to her mother, she had suffered from hyperthyroidism, and been medicated with propylthiouracil (an antithyroid). However, she often forgot to take the medicine, and never consulted to her thyroidologist for the past two

Reduced activation martensitic steels (RAMSs) are the prime candidate structural material for the DEMO reactor and beyond where the material has been considered to suffer severe embrittlement caused by high-dose neutron irradiation and several thousands appm of transmutated helium. However, recent several works show high resistance to helium embrittlement of RAMS. Good performance of RAMS in the presence of rather high concentration of helium is considered to be due to high trapping capacity for helium atoms in the martensitic structure that consists of dislocations, lath boundaries, grain boundaries and carbide/matrix interfaces. To make clear the role of dislocations in trapping helium, thermal helium desorption spectra were measured for iron specimens annealed at different temperatures after cold work. A desorption peak, which increased its height with increasing dislocation density, was observed at around 550 °C, suggesting that dislocations trap helium atoms. A molecular dynamics simulation study for investigating the helium trapping behavior at helium–vacancy complexes suggests that helium is rather strongly bound to the complexes and increases the binding energy of vacancy to the complex, resulting in increasing stability of the complexes at elevated temperatures by reducing thermal emission of vacancies.

A monoclonal antibody (2D11, IgG2b) obtained by immunizing mice with a mucin fraction of the human gastric mucosa reacted specifically to intestinal metaplasia of human gastric mucosa and fetal intestinal mucosa but not to normal adult gastric, small intestinal or colonic mucosa in immunohistochemical staining. The results of Western blotting indicated that 2D11 recognized the high molecular weight glycoprotein(s) (mucin) of the stomach. Treatment of the antigens with sodium periodate abolished their reactivity to 2D11, and digestion of the antigens with β-galactosidase reduced their reactivity to 2D11. Digestion of the antigens with pronase had no effect, however, suggesting that 2D11 recognizes the oligosugar moiety but not the peptide moiety of the antigens. Further immunohistochemical investigation showed that the reactivity of 2D11 was restricted to the Type III intestinal metaplasia that is identified by a characteristic staining pattern with the high iron diamine-Alcian blue stain. 2D11 also reacted in high frequency to adenocarcinomas of the stomach (66.7%), pancreas (66.7%) and gallbladder (50.0%), but in low frequency to those in lung (8.3%) and colon (11.1%). It is of interest that 2D11 reacted to very restricted regions of the gastric adenocarcinomas. All monoclonal antibodies to mucin polypeptides (MUC1, 2, 3, 5AC and 6) examined stained intestinal metaplasia and carcinomas in a different pattern from 2D11 in immunohistochemistry. These facts indicate that Type III intestinal metaplasia and carcinomas express carbohydrate chains identical to those expressed in the fetal intestinal mucosa, suggesting that both of them are closely related to fetal intestinal mucosa. © 2002 Wiley-Liss, Inc.