GB688821A - Improvements relating to the production of energy from radio-active materials - Google Patents

Improvements relating to the production of energy from radio-active materials

Info

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
Application number
GB4426/41A
Inventor
Hans Heinrich Von Halban
Lew Kowarski
Egon Bretscher
Norman Feather
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
IMP TRUST FOR ENCOURAGEMEN
Original Assignee
IMP TRUST FOR ENCOURAGEMEN
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Priority to CA558127A priority Critical patent/CA558127A/en
Application filed by IMP TRUST FOR ENCOURAGEMEN filed Critical IMP TRUST FOR ENCOURAGEMEN
Priority to GB4426/41A priority patent/GB688821A/en
Publication of GB688821A publication Critical patent/GB688821A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/18Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
    • G21C5/20Moderator 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
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear 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.
GB4426/41A 1941-04-02 1941-04-02 Improvements relating to the production of energy from radio-active materials Expired GB688821A (en)

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)

* Cited by examiner, † Cited by third party
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

Cited By (7)

* Cited by examiner, † Cited by third party
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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