Theoretical study on the alloying behavior of -uranium metal; -uranium alloy with 3d transition metals

Kurihara, Masayoshi*; Hirata, Masaru; Sekine, Rika*; Onoe, Jun*; Nakamatsu, Hirohide*

Journal of Nuclear Materials, 326(2-3), p.75 - 79, 2004/03

https://doi.org/10.1016/j.jnucmat.2003.11.013

We have investigated the alloying behavior of g-uranium with 3d transition metals (TMs) using the relativistic discrete-variational Dirac-Fock-Slater (DV-DFS) method. The d-orbital energy (Md) as an alloying parameter well reproduces the alloying behavior of g- uranium metal with TMs: (1) in the case of a large Md value (Ti,V,Cr), the solubility of these TM elements in g-uranium becomes large; (2) in the case of a middle Md value (Mn,Fe,Co), the tendency to form a uranium intermetallic compound with these elements becomes stronger; (3) in the case of a small Md value (Cu), the alloying element is insoluble in g-uranium. The alloying behavior of g-uranium with TMs is also discussed in terms of other parameters such as electronegativity and metallic radius.

Transportation of significant metals recovered in real sea experiment of adsorbents

Takeda, Hayato*; Onuma, Kenji*; Tamada, Masao; Kasai, Noboru; Katakai, Akio; Hasegawa, Shin; Seko, Noriaki; Kawabata, Yukiya*; Sugo, Takanobu

JAERI-Tech 2001-062, 66 Pages, 2001/10

JAERI-Tech-2001-062.pdf:5.5MB

Real sea experiment for the recovery of significant metals such as uranium and vanadium has been carried out at the offing of Mutsu establishment to evaluate the adsorption performance of adsorbent synthesized by radiation-induced graft-polymerization. After elution of uranium and vanadium from the adsorbent, their metals were adsorbed onto the conventional chelate resin. This chelate resin in a plastic column was further put in a cylindrical stainless transport container. The container was transported to the facility for separation and purification by a truck for the exclusive loading. The maximum concentration is 60 Bq/g when the uranium is adsorbed on the chelate resin. Transportation of recovered metals can be treated as general substance since these amount and concentration are out of legal control. However, the recovered metals were transported in conformity to L type transportation as a voluntary regulation. The strength analysis of the container was equal to the safety level of IP-2 type which is higher transportation grade than L type .

Measurement test on creep strain rate of uranium-zirconium solid solutions

*; Akabori, Mitsuo; Ogawa, Toru

JAERI-Tech 96-052, 18 Pages, 1996/11

JAERI-Tech-96-052.pdf:0.92MB

no abstracts in English

Core design study for hybrid type trans-uranium nuclides incineration plant, Part 1; Concept

Takada, Hiroshi; Kanno, Ikuo; Takizuka, Takakazu; Akabori, Mitsuo; ; Kaneko, Yoshihiko

JAERI-M 90-131, 18 Pages, 1990/08

JAERI-M-90-131.pdf:0.59MB

no abstracts in English

Fuel elements and fuel cycle concepts of actinide burner reactors; Conceptual study of actinide burner reacotors, IV

Ogawa, Toru; Mukaiyama, Takehiko; Takano, Hideki; Takizuka, Takakazu; ; *

JAERI-M 89-123, 38 Pages, 1989/09

JAERI-M-89-123.pdf:1.25MB

no abstracts in English

Syntheses and X-ray observations of new uranium fluoride complexes KUF and RbUF

; ; ; Fujino, Takeo

Inorg.Chim.Acta, 54, p.L193 - L194, 1981/00

no abstracts in English

Formation of Organic Iodides on solution of Irradiated Uranium Metal in Nitric Acid

; ; ;

International Journal of Applied Radiation and Isotopes, 22, p.793 - 798, 1971/00

https://doi.org/10.1016/0020-708X(71)90149-9

no abstracts in English

Physical properties of semimetallic magnets UOX (X = S, Se, Te)

Opletal, P.; Sakai, Hironori; Haga, Yoshinori; Miyake, Atsushi*; Tokunaga, Masashi*; Tokiwa, Yoshifumi; Yamamoto, Etsuji; Kambe, Shinsaku; Tokunaga, Yo

no journal, ,