Ganguly et al., 1994 - Google Patents
Fabrication of (Pu0. 55U0. 45) C fuel pellets for the second core of the fast breeder test reactor in IndiaGanguly et al., 1994
- Document ID
- 4054120319908833587
- Author
- Ganguly C
- Hegde P
- Jain G
- Publication year
- Publication venue
- Nuclear technology
External Links
Snippet
Abstract Around 200 kg of (Pu0. 55 U0. 45) C fuel pellets of relatively low density (86±2% theoretical density) would be used as a driver fuel in the second core of the Fast Breeder Test Reactor in India. The current paper summarizes the production experience of the initial …
- 239000008188 pellet 0 title abstract description 71
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/623—Oxide fuels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
-
- 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/38—Fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2002/00—PROBLEM
- G21Y2002/104—Inadequate performance, deformation, cracks, rupture
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2004/00—SOLUTION
- G21Y2004/10—Compositions
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Assmann et al. | Oxide fuels with controlled microstructure | |
| Ganguly et al. | Preparation, characterisation and out-of-pile property evaluation of (U, Pu) N fuel pellets | |
| Ganguly et al. | Fabrication of (Pu0. 55U0. 45) C fuel pellets for the second core of the fast breeder test reactor in India | |
| Kutty et al. | Development of CAP process for fabrication of ThO2–UO2 fuels Part I: Fabrication and densification behaviour | |
| Bernard | Advanced fuel fabrication | |
| Burkes et al. | A US perspective on fast reactor fuel fabrication technology and experience. Part II: Ceramic fuels | |
| Roepenack et al. | Development of thermal plutonium recycling | |
| Brett et al. | THE SINTERING BEHAVIOUR AND STABILITY OF (PuU) O $ sub 2$ SOLID SOLUTIONS | |
| Govers et al. | Characterization of Belgian spent fuel assemblies | |
| Richter et al. | Direct pressing: a new method of fabricating MX fuel pellets | |
| Eidson | Comparison of physical chemical properties of powders and respirable aerosols of industrial mixed uranium and plutonium oxide fuels. Technical report | |
| Durand et al. | Preliminary developments of MTR plates with uranium nitride | |
| US3254030A (en) | Plutonium enriched uranium fuel for nuclear reactors | |
| Rahimi et al. | Neutronic analysis of alternative ceramic fuels in the next generation of VVER-1000/V446 reactor | |
| Mishra et al. | Fabrication of Nuclear Fuel Elements | |
| Tikare | Property-process relationships in nuclear fuel fabrication | |
| Jayaraj et al. | Recent developments in design and manufacture of uranium dioxide fuel pellets for PHWRs in India | |
| Kapoor et al. | Shaping of nuclear fuel fabrication in India-a journey of self-reliance. | |
| Ganguly | STATUS OF LMFBR FUEL DEVELOPMENT AND THORIUM UTILISATION IN INDIA | |
| Freis et al. | Overview of Post-Irradiation Examination results on Minor Actinide bearing fuels within the FUTURIX-FTA international collaboration | |
| Ganguly et al. | Fabrication of (U, Pu) C and (U, Pu) N Fuels for FBTR and PFBR | |
| Richter et al. | Fabrication processes and characterization of LMFBR carbide and nitride fuels and fuel pins | |
| Ohai | Technologies for manufacturing UO 2 sintered pellets to fuel burnup extension | |
| Vaidya | Nuclear ceramics | |
| Brand et al. | PYROCHEMICAL REPROCESSING OF UO $ sub 2$ BY AIROX. Summary Report |