Recoil Based Fuel Breeding Fuel Structure
Description
Nuclear transmutation reactions are based on the absorption of a smaller particle as neutron, proton, deuteron, alpha, etc. The resulting compound nucleus gets out of its initial lattice mainly by taking the recoil, also with help from its sudden change in chemical properties. The recoil implantation is used in correlation with thin and ultra thin materials mainly for producing radiopharmaceuticals and ultra-thin layer radioactive tracers. In nuclear reactors, the use of nano-particulate pellets could facilitate the recoil implantation for breeding, transmutation and partitioning purposes. Using enriched 238U or 232Th leads to 239Pu and 233U production while using other actinides as 240Pu, 241Am etc. leads to actinide burning. When such a lattice is immersed into a radiation resistant fluid (water, methanol, etc.), the recoiled product is transferred into the flowing fluid and removed from the hot area using a concentrator/purifier, preventing the occurrence of secondary transmutation reactions. The simulation of nuclear collision and energy transfer shows that the impacted nucleus recoils in the interstitial space creating a defect or lives small lattices. The defect diffuses, and if no recombination occurs it stops at the lattices boundaries. The nano-grains are coated in thin layer to get a hydrophilic shell to be washed by the collection liquid the particle is immersed in. The efficiency of collection depends on particle magnitude and nuclear reaction channel parameters. For 239Pu the direct recoil extraction rate is about 70% for 238UO2 grains of 5 nm diameters and is brought up to 95% by diffusion due to 239Neptunium incompatibility with Uranium dioxide lattice. Particles of 5 nm are hard to produce so a structure using particles of 100 nm have been tested. The particles were obtained by plasma sputtering in oxygen atmosphere. A novel effect as nano-cluster radiation damage robustness and cluster amplified defects rejection will be discussed. The advantage of the method and device is its ability of producing small amount of isotopic materials easy to separate, using the nuclear reactors, with higher yield than the accelerator based methods and requiring less chemistry. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- Materials Research Society - MRS
- Imprint Place
- Warrendale (United States)
- ISBN
- 978-1-60511-074-5
- Imprint Title
- Proceedings of the symposium Actinides 2008 - Basic Science, Applications and Technology
- Imprint Pagination
- v. 1104, [260 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- Symposium Actinides 2008 - Basic Science, Applications and Technology
- Dates
- 24-28 Mar 2008
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39101766
- Subject category
- S38: RADIATION CHEMISTRY, RADIOCHEMISTRY AND NUCLEAR CHEMISTRY; S07: ISOTOPES AND RADIATION SOURCES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTINIDES; AMERICIUM 241; CHEMICAL PROPERTIES; COMPOUND NUCLEI; FUEL PELLETS; PLUTONIUM 239; PLUTONIUM 240; RADIATION EFFECTS; RADIOPHARMACEUTICALS; RECOILS; SIMULATION; THIN FILMS; THORIUM 232; TRANSMUTATION; URANIUM 233; URANIUM 238; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; AMERICIUM ISOTOPES; CHALCOGENIDES; DRUGS; ELEMENTS; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FILMS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; ISOTOPES; LABELLED COMPOUNDS; MATERIALS; METALS; NEON 24 DECAY RADIOISOTOPES; NUCLEI; ODD-EVEN NUCLEI; OXIDES; OXYGEN COMPOUNDS; PELLETS; PLUTONIUM ISOTOPES; RADIOACTIVE MATERIALS; RADIOISOTOPES; SPONTANEOUS FISSION RADIOISOTOPES; THORIUM ISOTOPES; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANIUM OXIDES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 15 refs.; Full text available at: http://www.mrs.org/s_mrs/bin.asp?CID=12409&DID=212637&DOC=FILE.PDF