Multicomponent Alloys Based on U-Pu as a Fast Reactor Fuel
- 1. Ordena Lenina Institut Atomnoj Energii Im. I.V. Kurchatova , Moskva, SSSR (Russian Federation)
Description
The authors study multicomponent alloys based on U-Pu, to which Mo, Nb, Zr and Ru are added. From the results of microstructure, X-ray and differential thermal analyses it is established that the added elements vary in their ability to stabilize the γ phase: molybdenum has the strongest stabilizing effect, followed by ruthenium, niobium and zirconium. Various of the alloys' physical constants are determined: melting point, thermal conductivity, change in volume at the moment of phase transition, specific weight and coefficient of linear expansion. The short-term rigidity at high temperatures of some of the alloys is studied by the bending method. It is found that the high-temperature rigidity of the alloys is increased most by molybdenum. Ruthenium also produces a significant increase in high-temperature rigidity, but less than molybdenum. The high temperature rigidity of an alloy depends to a great extent on its plutonium content; in the case of a ternary U-Pu-Mo alloy containing 9 wt.% Mo, for example, the sag (for the same load and temperature) is 2.5 and 9.5 mm respectively for 15 wt.% Pu and 20 wt.% Pu. The high-temperature rigidity of a ternary U-Pu-Mo alloy containing 20 wt.% Pu and 9 wt.% Mo is of the same order as that of a U-Pu alloy containing 8.6 wt.% fissium. The stability of the γ phase in multicomponent alloys at 500°C was studied by microstructure analysis. A more accurate phase diagram for U-Pu alloys is obtained by the authors in the concentration range 0-50 wt.% uranium. The existence is established of an eutectoid horizontal at 430°C produced by three-phase equilibrium, ή(δ')-->δ+X'(δ). The extent of the eutectoid horizontal at 260°C is determined more accurately: it is found to extend to 5 wt.% uranium, and not to 4.2 wt.% as reported previously. (author)
Abstract (Russian)
Issledovany mnogokomponentnye splavy na osnove U-Pu. V kachestve dobavok byli ispol'zovany Mo, Nb, Z r i Ru. Po rezul'tatam mikrostrukturnogo, rentge- nograficheskogo i differencial'nogo termicheskogo analizov ustanovleno, chto po sposob- nosti stabilizirovat' γ-fazu prisadki raspolagajutsja sledujushhim obrazom: naibolee sil'no stabiliziruet molibden, zatem idut rutenij, niobij.i cirkonij. Opredelen rjad fizicheskih konstant splavov: temperatura plavlenija, teploprovodnost', izmenenie obe- ma v moment fazovogo perehoda, udel'nyj ves i kojefficient linejnogo rasshirenija. Izuchena kratkovremennaja zharoprochnost' nekotoryh splavov metodom izgiba. Usta- novleno, chto zharoprochnost' splavov naibolee sil'no povyshaet molibden. Rutenij takzhe znachitel'no povyshaet zharoprochnost' splava, odnako slabee, chem molibden. Tak, napri1 mer, strela progiba dlja trojnogo splava U-Pu-Mo, soderzhashhego 9 ves % Mo (pri odnoj i toj zhe nagruzke i temperature) ravna 2,5 i 9,5 mm sootvetstvenno dlja splava s soder- zhaniem 15 ves % Pu i 20 ves% Pu. Zharoprochnost' trojnogo splava U-Pu-Mo, soderzhashhego 20 ves % Pu i 9 ves % Mo, takogo zhe porjadka, kak zharoprochnost' splava U-Pu s 8,6 ves % fissiuma. Mikrostrukturnym analizom izuchena ustojchivost' γ-fazy v mnogokomponentnyh splavah pri temperature 500°C. Privoditsja utochnennaja diagramma sostojanija U-Pu v intervale koncentracii 0 - 50 ves % urana. Ustanovleno nalichie jevtektoidnoj gorizontali pri temperature 430°C. Ona obuslovlena trehfaznym ravnovesiem ή(δ')-->δX'(δ). Utochnena protjazhennost' jevtektoidnoj gorizontali pri temperature 260°C, a imenno, ona prostiraetsja do 5 ves % urana, a ne do 4,2 ves%, kak ukazyvalos' ranee. (author)Additional details
Additional titles
- Original title (Russian)
- Mnogokomponentnye splavy na osnove U-Pu kak yadernoe goryuchee dlya bystrykh reaktorov
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- Imprint Title
- Plutonium as a Reactor Fuel. Proceedings of a Symposium on the Use of Plutonium as a Reactor Fuel
- Imprint Pagination
- 876 p.
- Journal Series
- Proceedings Series
- Journal Page Range
- p. 165-174
- ISSN
- 0074-1884
Conference
- Title
- Symposium on the Use of Plutonium as a Reactor Fuel
- Dates
- 13-17 Mar 1967
- Place
- Brussels (Belgium)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44073745
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Quality check status
- Yes
- Descriptors DEI
- ALLOY SYSTEMS; BENDING; DENSITY; DIFFERENTIAL THERMAL ANALYSIS; FAST REACTORS; MELTING POINTS; MICROSTRUCTURE; MOLYBDENUM; NIOBIUM; NUCLEAR FUELS; PHASE DIAGRAMS; PHASE TRANSFORMATIONS; PLUTONIUM; RUTHENIUM; TEMPERATURE RANGE 0400-1000 K; THERMAL CONDUCTIVITY; URANIUM; X RADIATION; ZIRCONIUM;
- Descriptors DEC
- ACTINIDES; DEFORMATION; DIAGRAMS; ELECTROMAGNETIC RADIATION; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FUELS; INFORMATION; IONIZING RADIATIONS; MATERIALS; METALS; PHYSICAL PROPERTIES; PLATINUM METALS; RADIATIONS; REACTOR MATERIALS; REACTORS; REFRACTORY METALS; TEMPERATURE RANGE; THERMAL ANALYSIS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENTS; TRANSITION TEMPERATURE; TRANSURANIUM ELEMENTS;
Optional Information
- Lead record
- bmrn5-mty63
- Notes
- 8 refs., 5 figs., 2 tabs.
- Secondary number(s)
- IAEA-SM--88/58