Published September 1967 | Version v1
Book

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)

Optional Information

Lead record
bmrn5-mty63
Notes
8 refs., 5 figs., 2 tabs.
Secondary number(s)
IAEA-SM--88/58