Graphite Steel Research Articles

Neutron Environment and Consequences on the Design and Operation of the Laser Fusion Reactor Koyo

The Inertial Fusion Reactor KOYO, proposed by ILE Osaka was completed in its first phase study in 1992, and recent updates including new features have been released up to now. It is based on potentially key achievements in Inertial Fusion Energy (IFE) physics: development to achieve required laser efficiency, implosion stability and gain, pellet fabrication, chamber maintenance, engineering feasibilities, and cost of electricity. Neutron (target) emission profiles are reported assuming direct drive compressed targets (500 g.cm{sup -3}), which have been described with different approaches in stationary transport models. A full three-dimensional description of the reactor has been used to perform the neutronic analysis. Neutron spectra and fluences are calculated, and compared with previous one-dimensional results showing the differences in using both approaches. Some figures indicating the neutron flux expected through deep penetrations impinging on the final optics are also presented, representing its coincidence at long distances with the uncolided flux. The reported consequences are those related to the activation of the materials: shallow land burial (SLB) and recycling. Those radiological responses have been studied for the SiC tubes (components of the blanket), graphite (reflector), and ferritic steel HT-9 (structural wall). 5 refs., 9 figs., 1 tab.

Effect of gamma rays on crystalline materials during irradiation in a reactor

The article presents and discusses the results of experiments to determine the effect of gamma rays on the change in the properties of diamond, graphite, and structural steel. The materials were irradiated in a VVER type reactor. For diamonds, the effect on the annealing of defects was investigated. As gamma ray intensity increased, the crystal lattice expansion and defect concentration increased. Graphite lattice expansion and the mechanical properties of structural steel were also examined. Graphite lattice expansion increased with increased neutron flux and decreased irradiation temperature. Changes in the impact toughness of structural steel correlated precisely to the gamma ray flux in the experiments. 6 refs., 3 figs.

Development and heat load experiments of graphite brazed to stainless steel for the first wall structure of FER

A guard limiter concept with graphite brazed to a stainless steel base plate has been proposed in FER. The bonding of graphite and stainless steel was successfully done by vacuum brazing with an interlayer material of Mo or Cu. Mechanical strengths were measured by tensile and shear tests. Fatigue tests up to approximately 107 cycles were done. Heat load experiments were performed with electron beam equipment. Brazed materials with a Mo interlayer were subjected to a heat load up to 60 MJ/m2 (6 kJ/cm2). No complete failures were observed in every condition, but cracks were generated by heat loads greater than 40 MJ/m2 (4 kJ/cm2). The failures were generated in graphite near to the interface. Mechanical strength and thermal shock resistance were improved by the change from 1 to 3 mm in thickness of Mo interlayer. Residual stresses due to brazing and cool-down were analyzed with an FEM code, and the results were compared with strain measurements on the test specimen. A comparison study on interlayer materials is continuing, and heat load cycle tests are now underway for 10 MJ/m2(1 kJ/cm2), which is a target value based on the FER design.

Fatigue Characteristics of Spheroidal Graphite Cast Iron and Graphite Steel Having Second Phase Surrounding Graphite Nodules

Fatigue Characteristics of Spheroidal Graphite Cast Iron and Graphite Steel Having Second Phase Surrounding Graphite Nodules

りん含有フェライト黒鉛鋼の脆性

りん含有フェライト黒鉛鋼の脆性

The Impact Properties and Fractography of Spheroidal Graphite Cast Iron and Graphite Steel Having a Second Phase Surrounding Graphite Nodules

The Impact Properties and Fractography of Spheroidal Graphite Cast Iron and Graphite Steel Having a Second Phase Surrounding Graphite Nodules

Method for measuring hydrogen in aluminum by vacuum fusion extraction

The characteristics of crucibles made of graphite, mullite, alumina, and stainless steel (SUS 27) were examined for the purpose of retaining a molten aluminum sample in the extraction tube of gas measuring apparatus. The gas volume extracted by these crucibles or blank gas volume was measured, and hydrogen contents of aluminum samples were also measured from vacuum fusion extraction method by using these crucibles.The results showed that a crucible made of SUS 27 was more excellent in characteristics than those of other ones. Then, the following tests were conducted by using the SUS 27 crucible.(1) Reliability of measured values of hydrogen in aluminum obtained by vacuum fusion extraction method.(2) Distribution of hydrogen in the aluminum castings poured into the Ransley's chill mold.(3) Correspondence of the measured values with those by solid extraction method.The results obtained were as follows:(1) Standard deviation of the measured values of hydrogen in extruded aluminum rod was 0.003cc/100g.(2) Distribution of hydrogen in the castings poured into the Ransley's chill mold was not uniform.(3) Measured values by vacuum fusion extraction method corresponded well with those by vacuum solid extraction method.

鍛造圧延黒鉛鋼におけるCaおよびSiの影響

鍛造圧延黒鉛鋼におけるCaおよびSiの影響

鍛造圧延したカルシウム黒鉛鋼におけるMn, Cr, NiおよびCuの影響

鍛造圧延したカルシウム黒鉛鋼におけるMn, Cr, NiおよびCuの影響

鍛造圧延したカルシウム黒鉛鋼におけるMoの影響

Effects of molybdenum on the graphitization and mechanical properties of calcium wrought graphite steel containing about 1.3%C and 0.8%Si were investigated. The suitable annealing temperature for the graphitization has been found to be in the range from 800° to 900°C. Graphitization was considerably suppressed depending upon the amount of molybdenum as the carbide forming element and also the hardness increased. The upper molybdenum limit may be considered as 0.3%, of which this element insures the precipitation of necessary graphite and the strength of the matrix. Mechanical properties of calcium treated Graph-Mo steels were closely related to the microstructures, which in turn depend upon oil quenching, the tempering temperature and the resulting combined carbon.

カルシウム黒鉛鋼の黒鉛析出作用におよぼす硫黄，酸素および硅素の影響

カルシウム黒鉛鋼の黒鉛析出作用におよぼす硫黄，酸素および硅素の影響

カルシウム黒鉛鋼の黒鉛再析出現象

カルシウム黒鉛鋼の黒鉛再析出現象

カルシウム黒鉛鋼の黒鉛化条件ならびに組織変化

カルシウム黒鉛鋼の黒鉛化条件ならびに組織変化

カルシウム黒鉛鋼の黒鉛析出過程について

カルシウム黒鉛鋼の黒鉛析出過程について

球状黒鉛鋼の機械的性質におよぼす熱処理の影響

球状黒鉛鋼の機械的性質におよぼす熱処理の影響

The Permanent Anode in Impressed‐current Cathodic Protection Systems—Part 2

Progress continues in the search for better and more universal permanent anode materials in impressed‐current cathodic protection systems. Last month graphite, silicon iron and scrap steel were discussed in this connection and the concluding part of the article continues by describing the properties, uses and limitations of lead and platinised lead, and platinised titanium. The fundamental principles of connection are also covered.

The Permanent Anode in Impressed‐current Cathodic Protection Systems—Part 1

The radical mitigation of corrosion on external or internal surfaces of pipelines, tank farms, storage tanks, pylon footings and of gasholders, ship's ballast tanks, ship's hulls, condenser end‐boxes, heat exchangers and pasteurisers, has been successfully accomplished by the application of cathodic protection both by galvanic anodes and by the use of the impressed‐current method. The scope of cathodic protection is thus comprehensive. This paper describes in a general way the properties, uses and limitations of the principal materials used as anodes in impressed‐current cathodic protection systems, together with some indication of the effects of different environments upon the various materials. In this first part, graphite, silicone iron and scrap steel are discussed.