GB688821A - Improvements relating to the production of energy from radio-active materials - Google Patents
Improvements relating to the production of energy from radio-active materialsInfo
- Publication number
- GB688821A GB688821A GB4426/41A GB442641A GB688821A GB 688821 A GB688821 A GB 688821A GB 4426/41 A GB4426/41 A GB 4426/41A GB 442641 A GB442641 A GB 442641A GB 688821 A GB688821 A GB 688821A
- Authority
- GB
- United Kingdom
- Prior art keywords
- reactor
- mass
- per
- ratio
- atoms
- 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
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
- G21C5/20—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone contains fissile material and another zone contains breeder material
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- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Transition And Organic Metals Composition Catalysts For Addition Polymerization (AREA)
- Soy Sauces And Products Related Thereto (AREA)
Abstract
688,821. Nuclear reactors. IMPERIAL TRUST FOR THE ENCOURAGEMENT OF SCIENTIFIC AND INDUSTRIAL RESEARCH. Dec. 10, 1941 [April 2, 1941], No. 4426/41. Class 39(iv) U<SP>233</SP> or PU<SP>239</SP> is produced in a nuclear reactor (breeder) by transmuting Th<SP>232</SP> or U<SP>238</SP> respectively. A single-medium reactor producing Pu<SP>239</SP> comprises about 10 kg. of U<SP>235</SP> or U<SP>235</SP> diluted with U<SP>238</SP>, (this U<SP>235</SP> being concentrated as described in Specification 685,360), and mixed with natural uranium and water to give a total mass of a few tons. The ratio of enriched U<SP>235</SP> to the U<SP>235</SP> present in natural uranium is 0.4 to 1 and it is stated that a theoretical minimum of 0.2 to 1 for a homogeneous reactor or 0.15 to 1 for a heterogeneous reactor would require infinite total mass. In this reactor the H to U<SP>238</SP> ratio is 6-8 atoms to 1 atom, and the ratio PU<SP>239</SP> produced to U<SP>235</SP> consumed is 4 to 1.2. A reactor producing U<SP>233</SP> comprises U<SP>235</SP>, H 2 O and Th in the weight ratio 1:10:50, and yields 1 gram U<SP>233</SP> per gram U<SP>235</SP>. A less efficient (two-medium) reactor, requiring a lesser amount of enriched U<SP>235</SP> comprises a neutron-producing mass surrounded by a neutronreceiving mass. A neutron-producing mass comprises more than 30 litres of pure U<SP>235</SP> and H 2 O in proportions 1:23 by weight, cooling being assisted by preserving a suitable surface/volume ratio, by forming the mass as a flattened shape, as a hollow sphere, or as a string of 30-litre spheres, or by setting a part of the mass in motion, as described in Specification 688,822. Similar reactors are described comprising (a) 116 kg. of benzene and 3.5 kg. of U<SP>235</SP>; (b) 240 litres of H 2 O containing U<SP>235</SP> in the ratio 61:1 by weight; (c) D 2 O+ H 2 O+ U<SP>235</SP>; (d) several hundred litres of D 2 O + U<SP>235</SP> in the ratio 1200: 1 by weight; (e) highdensity deuteroparaffin of approximate formula CD 2 + U<SP>235</SP>; (f) graphite plus several kgs. of U<SP>235</SP> cooled by CO 2 or intermittently by H 2 O or molten metal; and these reactors give better cooling, or require less U<SP>235</SP>. The neutron-receiving mass or envelope may comprise natural uranium, thorium, or U<SP>238</SP> and is of the order of one or a few decimeters thick. 2 to 6 atoms H (in H 2 O) per atom U or Th are needed as moderators in the case of U<SP>238</SP> or Th. With an envelope containing natural uranium, convergent fission chains are produced therein. This uranium is mixed homogeneously or heterogeneously with H 2 O or other suitable hydrogen compound (e.g. paraffin wax). A homogeneous mixture of uranium oxide with water (3 atoms H per atom U) surrounding a core emitting 1.5 neutrons per fission yields 5 atoms Pu per fission. A similar core surrounded by a heterogeneous mixture of U with paraffin wax (3 to 4 atoms H per atom U) yields 15 atoms P'u per fission. These reactors are of the order 10 to 100 tons. Thorium in the envelope may be arranged heterogeneously with respect to the uranium to avoid dilution of U<SP>233</SP> with the natural uranium. The accumulation of Pu<SP>239</SP> or U<SP>233</SP> in any of these reactors continues until it becomes practicable (a) to extract U<SP>233</SP> or Pu<SP>239</SP> chemically, leaving enough fissile material for the reactor to continue functioning, or (b) to add 50 per cent to 100 per cent to the water content of the core as the concentration of Pu<SP>239</SP> or U<SP>233</SP> in the envelope makes it energyproducing, independent of the core; or (c) singlemedium systems become workable in smaller sizes as Pu<SP>239</SP> or U<SP>233</SP> accumulates, so that such a system may form a core for a two-medium system.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CA558127A CA558127A (en) | 1941-04-02 | Production of energy from radio-active materials | |
GB4426/41A GB688821A (en) | 1941-04-02 | 1941-04-02 | Improvements relating to the production of energy from radio-active materials |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB4426/41A GB688821A (en) | 1941-04-02 | 1941-04-02 | Improvements relating to the production of energy from radio-active materials |
Publications (1)
Publication Number | Publication Date |
---|---|
GB688821A true GB688821A (en) | 1953-03-18 |
Family
ID=9776963
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB4426/41A Expired GB688821A (en) | 1941-04-02 | 1941-04-02 | Improvements relating to the production of energy from radio-active materials |
Country Status (2)
Country | Link |
---|---|
CA (1) | CA558127A (en) |
GB (1) | GB688821A (en) |
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2938844A (en) * | 1953-05-15 | 1960-05-31 | Clifton B Graham | Neutronic reactor counter method and system |
DE1107841B (en) * | 1957-01-24 | 1961-05-31 | Siemens Ag | Fuel element for nuclear reactors |
US3093563A (en) * | 1953-04-30 | 1963-06-11 | John R Menke | Composite neutronic reactor |
DE1260644B (en) * | 1958-08-16 | 1968-02-08 | Schunk Und Ebe G M B H | Process to improve the braking and reflection ability for neutrons in porous graphite moldings for nuclear reactors |
DE1263937B (en) * | 1957-06-10 | 1968-03-21 | Gen Dynamics Corp | Nuclear reactor fuel element with a solid homogeneous mixture of a moderator material and fissile material |
DE1278029B (en) * | 1963-12-27 | 1968-09-19 | Combustion Eng | Method for controlling a nuclear reactor moderated with hydrocarbons |
DE1283406B (en) * | 1958-03-25 | 1968-11-21 | Gen Electric | Nuclear reactor breeding element |
-
0
- CA CA558127A patent/CA558127A/en not_active Expired
-
1941
- 1941-04-02 GB GB4426/41A patent/GB688821A/en not_active Expired
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3093563A (en) * | 1953-04-30 | 1963-06-11 | John R Menke | Composite neutronic reactor |
US2938844A (en) * | 1953-05-15 | 1960-05-31 | Clifton B Graham | Neutronic reactor counter method and system |
DE1107841B (en) * | 1957-01-24 | 1961-05-31 | Siemens Ag | Fuel element for nuclear reactors |
DE1263937B (en) * | 1957-06-10 | 1968-03-21 | Gen Dynamics Corp | Nuclear reactor fuel element with a solid homogeneous mixture of a moderator material and fissile material |
DE1283406B (en) * | 1958-03-25 | 1968-11-21 | Gen Electric | Nuclear reactor breeding element |
DE1260644B (en) * | 1958-08-16 | 1968-02-08 | Schunk Und Ebe G M B H | Process to improve the braking and reflection ability for neutrons in porous graphite moldings for nuclear reactors |
DE1278029B (en) * | 1963-12-27 | 1968-09-19 | Combustion Eng | Method for controlling a nuclear reactor moderated with hydrocarbons |
Also Published As
Publication number | Publication date |
---|---|
CA558127A (en) | 1958-06-03 |
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No | I--General Science and Engineering--I |