GB887197A - Method and apparatus for the investigation of neutron propagating media - Google Patents
Method and apparatus for the investigation of neutron propagating mediaInfo
- Publication number
- GB887197A GB887197A GB23149/58A GB2314958A GB887197A GB 887197 A GB887197 A GB 887197A GB 23149/58 A GB23149/58 A GB 23149/58A GB 2314958 A GB2314958 A GB 2314958A GB 887197 A GB887197 A GB 887197A
- Authority
- GB
- United Kingdom
- Prior art keywords
- neutron
- sample
- revolutions
- source
- sources
- 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
- G21C7/00—Control of nuclear reaction
- G21C7/34—Control of nuclear reaction by utilisation of a primary neutron source
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Analysing Materials By The Use Of Radiation (AREA)
Abstract
887,197. Moderating neutrons. COMMISSARIAT A L'ENERGIE ATOMIQUE. July 18, 1958 [July 22, 1957], No. 23149/58. Class 39(4) Apparatus for investigating the neutron propagating characteristics of a medium comprises means for supporting a sample of the medium, neutron source means for irradiating the sample from a surface substantially completely surrounding the sample or for simulating irradiation from a surface substantially completely surrounding the sample, and means for detecting the resulting neutron flux at points within the sample. In the arrangement shown in Fig. 1 the medium 1 may comprise a cylindrical beryllium oxide-uranium lattice arranged between two guard sections 30, 31 on a fixed support. The guard section may comprise graphite-hydrogen-uranium lattices, the hydrogen being in the form of polyethylene tubes. The fixed structure is surrounded by a rotatable tower 4 driven by a motor 8. The tower carries two diametrically opposed neutron sources 12, 13 which are reciprocated up and down by a drive taken through a coupling and reversing arrangement from a gear 23 meshing with a rack 24. It is arranged that the sources move from top to bottom in 12.25 revolutions of the tower and then remain stationary for 3 revolutions; thus a complete cycle is half an integral number of revolutions and the sources 12, 13 exchange positions every cycle thereby ensuring perfect compensation for any minor inequalities between the sources. Each revolution may take 30 seconds, and a complete cycle of 30.5 revolutions thus takes about 15 minutes. The detectors may be rods of manganese or indium, the induced activity of which is measured to give the integrated flux. Each neutron source block, Fig. 7, comprises a sodium-beryllium source 40 surrounded by a bismuth shield 41 for screening the gamma rays and a cylindrical block 42 of uranium which also acts as a gamma ray shield and retards fast neutrons by inelastic collisions. In front of the source is a beryllium oxide stack 39 containing uranium rods 35-38 to act as a multiplier, and behind the source is a graphite reflector 43 and a layer of paraffin 44. Two sheets of cadmium 45, 46 line the side surfaces of the block to absorb thermal neutrons.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR1065102X | 1957-07-22 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB887197A true GB887197A (en) | 1962-01-17 |
Family
ID=9602112
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB23149/58A Expired GB887197A (en) | 1957-07-22 | 1958-07-18 | Method and apparatus for the investigation of neutron propagating media |
Country Status (5)
Country | Link |
---|---|
BE (1) | BE569372A (en) |
DE (1) | DE1065102B (en) |
FR (1) | FR1179674A (en) |
GB (1) | GB887197A (en) |
LU (1) | LU36263A1 (en) |
-
0
- BE BE569372D patent/BE569372A/xx unknown
- LU LU36263D patent/LU36263A1/xx unknown
-
1957
- 1957-07-22 FR FR1179674D patent/FR1179674A/en not_active Expired
-
1958
- 1958-07-18 GB GB23149/58A patent/GB887197A/en not_active Expired
- 1958-07-22 DE DEC17233A patent/DE1065102B/en active Pending
Also Published As
Publication number | Publication date |
---|---|
FR1179674A (en) | 1959-05-27 |
DE1065102B (en) | 1959-09-10 |
BE569372A (en) | |
LU36263A1 (en) |
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