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Publication numberUS3659107 A
Publication typeGrant
Publication dateApr 25, 1972
Filing dateJul 29, 1970
Priority dateJul 29, 1970
Also published asDE2137432A1
Publication numberUS 3659107 A, US 3659107A, US-A-3659107, US3659107 A, US3659107A
InventorsKokenge Bernard R, Selle James E
Original AssigneeAtomic Energy Commission
Export CitationBiBTeX, EndNote, RefMan
External Links: USPTO, USPTO Assignment, Espacenet
Radioisotopic fuel capsule
US 3659107 A
A radioisotopic fuel capsule or cell and making thereof for use in such as a thermoelectric or thermionic generators which utilizes substoichiometric plutonium dioxide enclosed within a refractory container.
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Description  (OCR text may contain errors)

United States Patent Selle et al. 5] Apr. 25, 1972 [54] RADIOISOTOPIC FUEL CAPSULE [56] References Cited [72] Inventors: James E. Selle, Miamisburg; Bernard R. UNITED STATES PATENTS Kokenge, Kettering, both of Ohio 3,569,714 3/1971 Anderson ..250/l06 S X 1 Asslgneer The Umled States of America 85 3,354,044 11/1967 Robertson ..l76/68 "Presented by United states Ammic 3,404,200 10/1968 Burgess ..23/344 x Energy Commission [22] Filed; Ju|y 29 1970 Primary ExaminerMorton J. Frome AttorneyRoland A. Anderson [21] Appl. No.: 59,173

[57] ABSTRACT U-S- Cl. S, A radioisotopic fuel capsule o cell and making thereof for use 250/84, 250/106 R, 252/ 11 R in such as a thermoelectric or thermionic generators which [51] Int. Cl. ..G2lh 5/00 utilizes substoichiomen-ic plutonium dioxide enclosed within a [58] Field of Search ..250/106 S, 106 R, 84; 23/344, refractory container 1 Claims, 1 Drawing Figure PATENTEUAPR 25 I972 INVENT BERNARD R. KOK GE BY JAMES E. SELLE RADIOISOTOPIC FUEL CAPSULE BACKGROUND OF INVENTION Plutonium dioxide, in the form of the alpha emitting radioactive plutonium-238, may be utilized in fuel elements or capsules as heat sources for thermoelectric, thermionic, and other power conversion units or simply as heat sources for space or the like applications. A quantity of plutonium-dioxide may be enclosed within a sealed container or capsule and the capsule then used as a heat source for whatever application desired. In these applications, the radioactive fuel element or capsule may operate at elevated temperatures, such as at about 500 C. and higher. At these temperatures, some corrosion of the container or capsule material may occur and cause a weakening of the container structure or even failure thereof.

Utilization of radioisotopes as high temperature heat sources for electrical power generation or space propulsion or the like requires positive containment under all potential conditions. While plutonium-238 is usable at moderate temperatures in space and the like applications, it would be desirable to use the same at higher temperatures to achieve more efficient utilization of the thermal energy available with minimum or no corrosion or degradation of the container material.

SUMMARY OF INVENTION It is an object of this invention to provide an improved radioisotopic fuel capsule using plutonium oxide fuel.

It is a further object of this invention to provide a plutonium oxide fuel exhibiting reduced corrosive attack of radioisotopic fuel capsule container materials.

Various other objects and advantages will appear from the following description of the invention, and the most novel features will be particularly pointed out hereinafter in connection with the appended claims.

It will be understood that various changes in the details, materials and arrangements of the parts, which have been herein described and illustrated in order to explain the nature of the invention, may be made by those skilled in the art.

This invention comprises a radioactive fuel capsule using substoichiometry plutonium dioxide fuel within a sealed container and a method of making same.

DESCRIPTION OF DRAWING Aspects of the present invention are shown in the accompanying drawing of a sectional view representing a radioisotopic fuel capsule incorporating the fuel of this invention.

DETAILED DESCRIPTION A plutonium oxide fuel 10, described in more detail below, may be disposed within a suitable container or cell 12, which may be of cylindrical or other configuration, and the container sealed by welding a lid or cover 14 thereon in an inert, oxygen free atmosphere. A void 16 maybe left within container 12 wherein it may accumulate gaseous material or products emitted from the plutonium oxide fuel, or appropriate gas pressure relieving means (not shown) may be positioned in a wall or cover of the container to facilitate escape of gas from the container and minimize pressure buildup therein. An outer protective housing 18 or housings with sealed cover 20 may be disposed about container 12, if desired.

Container 12 and cover 14 may be made of refractory material, such as certain refractory metals or alloys thereof. For the plutonium oxide fuel of this invention, such refractory metals may include tantalum, niobium, rhenium, tungsten, hafnium, vanadium, zirconium, nickel and titanium and alloys thereof or alloys with other refractory metals. Of these materials, tantalum and tantalum-l% tungsten maybe preferred because of their particularly high corrosion resistance and ease of fabrication. Other refractory metals and alloys may react to a greater or lesser extent depending on the materials and environmental conditions.

It has been found, that a plutonium oxide fuel 10 having an oxide to plutonium ratio in the range of about 1.60 to about 1.98, with the optimum composition being from about 1.75 to 1.85, exhibits substantially lower corrosive and other forms of attack against the container material. Such plutonium oxide fuel may be referred to as substoichiometric plutonium dioxide and may be used in the form of particles, powder or microspheres with particle sizes ranging from about 25 to 400 microns. If desired, the substoichiometric plutonium dioxide particles may be pressed into a pellet and the pellet sintered into a solid mass.

The substoichiometric plutonium dioxide fuel may be prepared by reducing stoichiometric plutonium dioxide with hydrogen or with plutonium metal, or by other convenient means.

The substoichiometric plutonium dioxide may be prepared within a fuel capsule by mixing ordinary or stoichiometric plutonium dioxide with a material which is more reactive to the oxygen than the container material. In other words, the reactive metal oxide should have a free energy of formation more negative than the free energy of formation of the container material oxide so that the reactive metal reacts preferentially with any oxides within the container. Such reactive materials may include yttrium, tantalum, cerium, titanium, uranium, thorium, and niobium and some of the rare earths as well as plutonium. By heating the stoichiometric plutonium dioxide with these reactive materials to elevated temperatures the oxygen may be preferentially gettered" by the reactive material. When this happens, the plutonium dioxide fuel becomes substoichiometric in composition. The desired oxygen to plutonium ratio, such as a preferred ratio of about 1.8, may be achieved by selecting an appropriate reactive material and amount thereof and reacting the same for some prescribed period of time and temperature. The reactive material may be added to the stoichiometric plutonium dioxide in any of several finely divided or dispersed forms, such as by chemical vapor deposition of the reactive material onto the surface of the oxide particles.

Stoichiometric plutonium dioxide particles were placed in contact with tungsten, tungsten-25% rhenium and rhenium at 2,000 C for 1,000 hours. Test results show that gross reaction occurred between the tungsten and stoichiometric plutonium dioxide with a 250 micrometers intergranular penetration and a certain amount of general solution attack. The stoichiometric plutonium dioxide exhibited three forms of attack with tungsten 25 atom percent rhenium (intergranular penetration, general solution and oxide precipitation) with penetration to 200 micrometers. Rhenium showed not only about 50 micrometers attack in contact with the stoichiometric plutonium dioxide but also a massive amount of vapor-phase transport from the fuel material to the capsule wall. Tantalum-10% tungsten alloy exhibited intergranular penetration to greater than 530 micrometers when contacted with stoichiometric plutonium dioxide at 1,200 C. for about 1,400 hours.

substoichiometric plutonium dioxide particles having an oxygen to plutonium ratio of about 1.8 were placed in contact with the same materials under the same conditions. The tungsten exhibited about 25 micrometer general solution attack and less than 50 micrometer intergranular penetration while the tungsten-25% rhenium and the rhenium exhibited a total attack of less than about 10 and 25 micrometers, respectively. Further, no transport was observed in the rhenium capsule containing PuO Substoichiometric plutonium dioxide samples exhibited 0 general solution attack and 0 and 12.5 micrometer intergranular penetration of tantalum-10% tungsten at 1,200 C. after about 1,400 hours. These latter tests included a 4.4 percent yttrium and 5.4 percent tantalum getter addition to achieve the substoichiometry.

What is claimed is:

1. A radioisotopic fuel capsule comprising a sealed container made of a material selected from the group consisting of tantalum, niobium, rhenium, tungsten, hafnium, vanadium, zirconium, nickel,-titanium and alloys thereof, and in said container oxygen-deficient fuel comprising substoichiometric plutonium dioxide particles with ratio of oxygen to plutonium in the range of about 1.7 to 1.85 and an oxygen-gettering material interspersed with said particles having a free energy of oxide formation more negative than said container material and 5 selected from the group consisting of yttrium, tantalum, cerium, titanium, uranium, thorium, niobium, plutonium and the rare earths.

Patent Citations
Cited PatentFiling datePublication dateApplicantTitle
US3354044 *Dec 17, 1964Nov 21, 1967Atomic Energy Of Canada LtdNuclear reactor fuel
US3404200 *Aug 8, 1967Oct 1, 1968Atomic Energy Commission UsaMethod of preparing a cermet nuclear fuel
US3569714 *Nov 14, 1969Mar 9, 1971Atomic Energy CommissionProtected radioisotopic heat source
Referenced by
Citing PatentFiling datePublication dateApplicantTitle
US3767930 *Jun 21, 1972Oct 23, 1973Atomic Energy CommissionRadioisotopic heat source
US3981805 *Sep 13, 1972Sep 21, 1976The United States Of America As Represented By The Secretary Of The Air ForceConcentric cylinders separated by a gas, tantalum, molybdenum and platinum alloys
US4024068 *Mar 24, 1975May 17, 1977Ceskoslovenska Akademie VedProcess for separating ceramics of uranium and plutonium from zirconium by hydriding and mixtures thereof
US4192765 *Feb 15, 1978Mar 11, 1980John N. BirdContainer for radioactive nuclear waste materials
US4278892 *Dec 6, 1978Jul 14, 1981Steag Kernergie GmbhRadioactivity-shielding transport or storage receptacle for radioactive wastes
US4337167 *Feb 5, 1980Jun 29, 1982Bird John MNickel-iron alloy, encapsulation
US4825088 *Oct 30, 1987Apr 25, 1989Westinghouse Electric Corp.Titanium supports for shielding wall j,ikuijm containing alumina coating
US4861520 *Oct 28, 1988Aug 29, 1989Eric van't HooftCapsule for radioactive source
US4891165 *Jul 28, 1988Jan 2, 1990Best Industries, Inc.Device and method for encapsulating radioactive materials
US5442186 *Dec 7, 1993Aug 15, 1995Troxler Electronic Laboratories, Inc.Radioactive source re-encapsulation including scored outer jacket
US5683345 *Oct 27, 1994Nov 4, 1997Novoste CorporationMethod and apparatus for treating a desired area in the vascular system of a patient
US5899882 *Apr 4, 1996May 4, 1999Novoste CorporationCatheter apparatus for radiation treatment of a desired area in the vascular system of a patient
US6306074May 4, 1999Oct 23, 2001Novoste CorporationMethod and apparatus for radiation treatment of a desired area in the vascular system of a patient
US7066872Apr 11, 2003Jun 27, 2006Best Vascular, Inc.Method and apparatus for treating a desired area in the vascular system of a patient
US7160238Dec 21, 1999Jan 9, 2007Best Vascular, Inc.Method and apparatus for treating a desired area in the vascular system of a patient
WO1990001208A1 *Jul 28, 1989Feb 8, 1990Best Ind IncDevice and method for encapsulating radioactive materials
U.S. Classification250/493.1, 252/644, 250/506.1, 976/DIG.410
International ClassificationG21H1/00, G21G4/04, G21G4/00
Cooperative ClassificationG21H1/00, G21G4/04
European ClassificationG21H1/00, G21G4/04