GB1011348A - Improvements in or relating to nuclear fuel materials - Google Patents
Improvements in or relating to nuclear fuel materialsInfo
- Publication number
- GB1011348A GB1011348A GB42407/63A GB4240763A GB1011348A GB 1011348 A GB1011348 A GB 1011348A GB 42407/63 A GB42407/63 A GB 42407/63A GB 4240763 A GB4240763 A GB 4240763A GB 1011348 A GB1011348 A GB 1011348A
- Authority
- GB
- United Kingdom
- Prior art keywords
- carbon
- matrix
- pellets
- fuel
- refractory
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/626—Coated fuel particles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Compositions Of Oxide Ceramics (AREA)
- Carbon And Carbon Compounds (AREA)
Abstract
1,011,348. Nuclear fuel materials. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Oct. 26, 1964 [Oct. 28, 1963], No. 42407/63. Drawing to Specification. Heading G6C. A nuclear fuel particle comprises a hollow centre bounded by a wall of a refractory material in which fissile and/or fertile material is dispersed. A method of making such a particle in which the fuel material is UC 2 including ZrC as a diluent is to first form a pellet of 100 to 200 microns diameter from the mixed carbides and to coat this pellet with pyrolytic carbon by a conventional fluidized bed process, the coating comprising two layers separated by a discontinuity. If, by way of example, the initial layer is of laminar structure, then the outer layer may be of columnar structure. A number of such pellets are incorporated in a matrix of carbon granules by being mixed with powdered carbon and a binder, compacted by applying light pressure and sintered to form a coherent mass. The whole body is then placed in a graphite tube resistance furnace wherein an inert atmosphere is maintained and heated at a uniform rate up to 2400‹ C. whereupon the matrix, but not the pyrolytic carbon coatings, is graphitized. The temperature is then raised to above 3000‹ C. for half a minute, i.e. a temperature above the m.p. of the UC 2 but below that of the matrix. The UC 2 diffuses into the inner coating layer but the discontinuity between the inner and outer layers inhibits much, if not all, further outward diffusion of the UC 2 . The space left by the outward diffusing UC 2 becomes the hollow centre of the resulting particle. It is not necessary to incorporate the coated pellets in a matrix of carbon or graphite and the method described may alternatively be taken as far as the application of the two layers of pyrolytic carbon, whereupon other pellets are placed in a pot of refractory material, preferably carbon or graphite, and heated to above 3000‹ C. as before in a graphite tube resistance furnace. The particles so formed are preferably given a coating of pyrolytic carbon at low temperature by a conventional fluidized bed process and may then be incorporated in a fuel bearing component of any desired form. The invention is applicable to other fuel and refractory materials and, by way of example, pellets of UO 2 may be coated with Al 2 O 3 , BeO or Nb, possibly also further coated with carbon or other refractory materials, and then incorporated in a suitable refractory matrix material either before or after being heated to a temperature above the m.p. of the UO 2 .
Priority Applications (9)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB42407/63A GB1011348A (en) | 1963-10-28 | 1963-10-28 | Improvements in or relating to nuclear fuel materials |
AT873864A AT257757B (en) | 1963-10-28 | 1964-10-14 | Spheroidal nuclear fuel particle and process for its manufacture |
SE12439/64A SE316244B (en) | 1963-10-28 | 1964-10-15 | |
NL6412149A NL6412149A (en) | 1963-10-28 | 1964-10-19 | |
FR992641A FR1527682A (en) | 1963-10-28 | 1964-10-26 | Process for the preparation of nuclear fuel particles and fuel particles produced by the process |
BE654841D BE654841A (en) | 1963-10-28 | 1964-10-26 | |
LU47215A LU47215A1 (en) | 1963-10-28 | 1964-10-27 | |
DE19641464906 DE1464906A1 (en) | 1963-10-28 | 1964-10-27 | Nuclear fuel particles and processes for their manufacture |
CH1402964A CH427061A (en) | 1963-10-28 | 1964-10-28 | Nuclear fuel particles for high temperature nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB42407/63A GB1011348A (en) | 1963-10-28 | 1963-10-28 | Improvements in or relating to nuclear fuel materials |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1011348A true GB1011348A (en) | 1965-11-24 |
Family
ID=10424280
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB42407/63A Expired GB1011348A (en) | 1963-10-28 | 1963-10-28 | Improvements in or relating to nuclear fuel materials |
Country Status (8)
Country | Link |
---|---|
AT (1) | AT257757B (en) |
BE (1) | BE654841A (en) |
CH (1) | CH427061A (en) |
DE (1) | DE1464906A1 (en) |
GB (1) | GB1011348A (en) |
LU (1) | LU47215A1 (en) |
NL (1) | NL6412149A (en) |
SE (1) | SE316244B (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3466166A (en) * | 1967-01-03 | 1969-09-09 | Gen Electric | Method for making a hollow metal article |
-
1963
- 1963-10-28 GB GB42407/63A patent/GB1011348A/en not_active Expired
-
1964
- 1964-10-14 AT AT873864A patent/AT257757B/en active
- 1964-10-15 SE SE12439/64A patent/SE316244B/xx unknown
- 1964-10-19 NL NL6412149A patent/NL6412149A/xx unknown
- 1964-10-26 BE BE654841D patent/BE654841A/xx unknown
- 1964-10-27 DE DE19641464906 patent/DE1464906A1/en active Pending
- 1964-10-27 LU LU47215A patent/LU47215A1/xx unknown
- 1964-10-28 CH CH1402964A patent/CH427061A/en unknown
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3466166A (en) * | 1967-01-03 | 1969-09-09 | Gen Electric | Method for making a hollow metal article |
Also Published As
Publication number | Publication date |
---|---|
BE654841A (en) | 1965-04-26 |
SE316244B (en) | 1969-10-20 |
AT257757B (en) | 1967-10-25 |
LU47215A1 (en) | 1964-12-28 |
DE1464906A1 (en) | 1969-10-23 |
NL6412149A (en) | 1965-04-29 |
CH427061A (en) | 1966-12-31 |
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