GB804902A - Neutron shielding material - Google Patents
Neutron shielding materialInfo
- Publication number
- GB804902A GB804902A GB2888656A GB2888656A GB804902A GB 804902 A GB804902 A GB 804902A GB 2888656 A GB2888656 A GB 2888656A GB 2888656 A GB2888656 A GB 2888656A GB 804902 A GB804902 A GB 804902A
- Authority
- GB
- United Kingdom
- Prior art keywords
- cadmium
- lithium
- parts
- fluoride
- carbon
- 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
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
Abstract
Material for moderating and absorbing neutrons from a fast reactor comprises carbon, carbonisable binder and lithium, cadmium, gadolinium, samarium and/or europium. Amorphous and/or crystalline carbon may be used, for example a graphitic mix, 50 parts dust finer than 100 mesh and 25 parts dust coarser than 50 mesh mixed with 25 parts pitch and/or tar. This mix is formed into a block, e.g. by tamping layer after layer, and heat treated at about 1000 DEG C. to carbonize the binder. Before this heat treatment, 10 parts of lithium fluoride may be added, to provide 0.0455 gms. Li per cc. and hence a neutron capture cross-section of 0.28 cm.2 per cc. Or the block of carbon after heat treatment may be immersed in molten lithium fluoride or in molten cadmium. Lithium sulphate, cadmium fluoride, hydrated cadmium acetate and gadolinium acetate are other examples of suitable compounds. The material may be used as a shield for a fast reactor or a fast breeder reactor, but a gamma-ray shield is necessary if cadmium is used and if lithium is used the active tritium produced may be extracted. Blocks may be built to form a wall or the granular material compacted and/or heattreated in situ. To reduce Wigner growth the screen may be maintained at a temperature of several hundred degrees Centigrade.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB2888656A GB804902A (en) | 1956-09-21 | 1956-09-21 | Neutron shielding material |
DEM35391A DE1064163B (en) | 1956-09-21 | 1957-09-19 | Nuclear reactor shielding material and process for its manufacture |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB2888656A GB804902A (en) | 1956-09-21 | 1956-09-21 | Neutron shielding material |
Publications (1)
Publication Number | Publication Date |
---|---|
GB804902A true GB804902A (en) | 1958-11-26 |
Family
ID=10282769
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB2888656A Expired GB804902A (en) | 1956-09-21 | 1956-09-21 | Neutron shielding material |
Country Status (2)
Country | Link |
---|---|
DE (1) | DE1064163B (en) |
GB (1) | GB804902A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2183713A1 (en) * | 1972-05-05 | 1973-12-21 | Inst Max Von Laue P Langevin | Neutron shield material - comprising polyurethane and absorption material |
FR2918498A1 (en) * | 2007-07-06 | 2009-01-09 | Antoine Jacques Candeias | Living organism protecting device, has carbon matrix mounted between dense materials to stop beta rays and gamma rays, where materials with good heat conductivity enclose carbon matrix and paraffin matrix for stopping neutron rays |
US11177045B2 (en) | 2017-03-15 | 2021-11-16 | Kabushiki Kaisha Toshiba | Thermal-neutron reactor core and design method for thermal-neutron reactor core |
CN115215659A (en) * | 2021-04-16 | 2022-10-21 | 国立大学法人筑波大学 | Sintered body for radiation shielding material, and method for producing same |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1178527B (en) * | 1959-11-24 | 1964-09-24 | Licentia Gmbh | Nuclear reactor shield |
-
1956
- 1956-09-21 GB GB2888656A patent/GB804902A/en not_active Expired
-
1957
- 1957-09-19 DE DEM35391A patent/DE1064163B/en active Pending
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2183713A1 (en) * | 1972-05-05 | 1973-12-21 | Inst Max Von Laue P Langevin | Neutron shield material - comprising polyurethane and absorption material |
FR2918498A1 (en) * | 2007-07-06 | 2009-01-09 | Antoine Jacques Candeias | Living organism protecting device, has carbon matrix mounted between dense materials to stop beta rays and gamma rays, where materials with good heat conductivity enclose carbon matrix and paraffin matrix for stopping neutron rays |
US11177045B2 (en) | 2017-03-15 | 2021-11-16 | Kabushiki Kaisha Toshiba | Thermal-neutron reactor core and design method for thermal-neutron reactor core |
CN115215659A (en) * | 2021-04-16 | 2022-10-21 | 国立大学法人筑波大学 | Sintered body for radiation shielding material, and method for producing same |
Also Published As
Publication number | Publication date |
---|---|
DE1064163B (en) | 1959-08-27 |
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