Prospects for reduced activation alloys

Doran, D. G.; Rowcliffe, A.F.; Mann, F.M.

doi:10.1016/0022-3115(86)90145-5

Cited by 9 publications

(4 citation statements)

References 9 publications

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“…Commercial Fe-Cr-Mn steels considered in several other studies have C contents that range from 0.02 to 0.6 wt.%, and our alloys fall within that range. Most of the commercial alloys also contain N contents that range from 0.02 to 0.6% as well, and current FIRD guidelines limit N to much lower levels [24]. Some commercial [2,25].…”

Section: Calculations Of Radiocative Decay Behavior With Time For Thementioning

confidence: 99%

Precipitation Sensitivity to Alloy Composition in Fe-Cr-Mn Austenitic Steels Developed for Reduced Activation for Fusion Application

Maziasz

Klueh

1990

Reduced Activation Materials for Fusion Reactors

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Special austenitic steels are being designed in which alloying elements like Mo, Nb, and Ni are replaced with Mn, W, V, Ti, and/or Ta to reduce the long-term radioactivity induced by fusion reactor irradiation. However, the new steels still need to have properties otherwise similar to commercial steels like type 316. Precipitation strongly affects strength and radiation-resistance in austenitic steels during irradiation at 400-600°C, and precipitation is also usually quite sensitive to alloy composition. The initial stage of development was to define a base Fe-Cr-Mn-C composition that formed stable austenite after annealing and cold-working, and resisted recovery or excessive formation of coarse carbide and intermetallic phases during elevated temperature annealing. These studies produced a Fe-12Cr-20Mn-0.25C base alloy. The next stage was to add the minor alloying elements W, Ti, V, P, and B for more strength and radiation-resistance. One of the goals was to produce fine MC precipitation behavior similar to the Ti-modified Fe-Cr-Ni prime candidate alloy (PCA). Additions of Ti+V+P+B produced fine MC precipitation along network dislocations and recovery/recrystallization resistance in 20% cold worked material aged at 800°C for 166h, whereas W, Ti, W+Ti, or Ti+P+B additions did not. Addition of W+Ti+V+P+B also produced fine MC, but caused some a phase formation and more recrystallization as well. These new alloys, therefore, achieved several of the initial design goals. Their fine MC precipitation and recovery/recrystallization behavior during aging is similar to that of the PCA. Calculations show that the new steels have over 10 s times less long-term radioactivity than type 316.

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Section: Calculations Of Radiocative Decay Behavior With Time For Thementioning

confidence: 99%

Precipitation Sensitivity to Alloy Composition in Fe-Cr-Mn Austenitic Steels Developed for Reduced Activation for Fusion Application

Maziasz

Klueh

1990

Reduced Activation Materials for Fusion Reactors

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“…Figure 16.2-20 shows a comparison of the relative swelling rates of austenitic alloys with those of ferritic steels [78]. Furthermore, ferritic steels have a higher thermal-stress resistance compared to austenitic steels [77]. These characteristics prompted the choice of a ferritic steel as the structural material for the TITAN-N design.…”

Section: Structural Materialsmentioning

confidence: 99%

“…Sections 13.7 and 19.5). Disposal limits of the major alloying elements used in commercial steels such as N, Ni, Nb, Mo, and W are listed inTable 16.2-XI[77].…”

mentioning

confidence: 99%

The TITAN reversed-field-pinch fusion reactor study

1990

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The TITAN Reversed-Field-Pinch (RFP) fusion-reactor study is a multi-institutional research effort to determine the technical feasibility and key developmental issues for an RFP fusion reactor operating at high power density, and to determine the poten tial economic (cost of electricity), operational (maintenance and availability), safety and environmental features of high mass-power-density fusion systems. Mass power density (MPD) is defined as the ratio of net electric output to the mass of the fusion power core (FPC). The fusion power core includes the plasma chamber, first wall, blanket, shield, magnets, and related structure. Two different detailed designs, TITAN-I and TITAN-II, have been produced to demon strate the possibility of multiple engineering-design approaches to high-MPD factors. TITAN-I is a self-cooled lithium design with a vanadium-alloy structure. TITAN-II is a self cooled aqueous loop-in-pool design with 9C fenitic steel as the structural material. Both designs would use RFP plasmas operating with essentially the same parameters. Both conceptual reactors are based on the DT fuel cycle, have a net electric output of about lOOOMWe, are compact, and have a high MPD of 800kWe per tonne of FPC. The inherent physical characteristics of the RFP confinement concept make possible compact fusion reactors with such a high mass power density. The TITAN designs would meet the U. S. criteria for the near-surface disposal of radioactive waste (Class C, 10CFR61) and would achieve a high Level of Safety Assurance with respect to FPC damage by decay afterheat and radioactivity release caused by accidents. Very importantly, a "single-piece" FPC maintenance procedure has been worked out and appears feasible for both designs. Parametric system studies have been used to find cost-optimized designs, to determine the parametric design window associated with each approach, and to assess the sensitivity of the designs to a wide range of physics and engineering requirements and assumptions. The design window for such compact RFP reactors would include machines with neutron wall loadings in the range of 10-20 MW/m 2 with a shallow minimum-COB at about 18 MW/m 2. Even though operation at the lower end of the this range of wall 'oading flO-12 MW/m 2) is possible, and may be preferable, the TITAN study adopted the design point at the upper end (18 MW/m 2) in order to quantify and assess the technical feasibility and physics limits for such high-MPD reactors. From this work, key physics and engineering issues central to achieving reactori, with the features of TITAN-I and TITAN-II have emerged.

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“…1 A specific objective of the U.S. Fusion Materials Program is that all reactor components will meet the requirements for near-surface burial. An additional requirement is that these materials exhibit low-induced longlived radioactivity in order to enhance fusion power's environmental (and economic) attractiveness.…”

Section: Introductionmentioning

confidence: 99%

Reduced Activation Alloy Development for Fusion

Doran¹,

Klueh²

1989

MRS Bull.

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Developing materials that resist degradation when exposed to neutrons is a key element in international programs to demonstrate the engineering and economic viability of fusion power. An additional requirement is that these materials exhibit low-induced long-lived radioactivity in order to enhance fusion power's environmental (and economic) attractiveness. This article briefly overviews current efforts to develop reduced activation structural alloys for fusion reactor applications.A specific objective of the U.S. Fusion Materials Program is that all reactor components will meet the requirements for near-surface burial. Presently, this is interpreted to mean that all radioactive waste should satisfy Part 61 of Title 10 of the U.S. Code of Federal Regulations (10CFR61), prepared by the Nuclear Regulatory Commission (NRC). Specific activity limits are placed on particular long-lived radionuclides, which, when combined with activation calculations for conceptual fusion devices, place constraints on material compositions. Regulation 10CFR61 was prepared to cover low-level waste produced by the fission reactor industry; it has been necessary to extend it, in principle, to include additional radionuclides. Unlike anticipated waste from a fusion industry, only a small fraction of the fission waste stream is activated metals; hence, the applicability of the regulation is questionable. Further analysis of the probable disposal method for fusion wastes is needed, along with consideration of maintenance and decommissioning scenarios.

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Prospects for reduced activation alloys

Cited by 9 publications

References 9 publications

Precipitation Sensitivity to Alloy Composition in Fe-Cr-Mn Austenitic Steels Developed for Reduced Activation for Fusion Application

Precipitation Sensitivity to Alloy Composition in Fe-Cr-Mn Austenitic Steels Developed for Reduced Activation for Fusion Application

The TITAN reversed-field-pinch fusion reactor study

Reduced Activation Alloy Development for Fusion

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