Potential of ^<231>Pa for Gas Cooled Long-life Core
スポンサーリンク
概要
- 論文の詳細を見る
Feasibility study of the long-life core loaded with 231Pa, which has very large capture cross-section, has been performed in the pebble bed-type gas cooled reactor. The results of infinite cell burn-up calculations show that 231Pa has attractive potential to reduce the initial excess-reactivity and to be effectively converted to fissile nuclides 232U and successively 233U with the burn-up. These characteristics enable the reactor to sustain nuclear reactions for a longer time. Based on the optimization of the fuel composition and the moderator to fuel ratio, it is found that the high fuel burn-up of about 700 GWd/t is achievable in consideration of the material restriction of coated fuel particles. Safety studies show negative temperature coefficients during the irradiation.
- 社団法人 日本原子力学会の論文
- 2002-03-25
著者
-
SAITO Masaki
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
-
Artisyuk V
Tokyo Inst. Of Technol. Tokyo
-
Saito Masaki
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
-
ARTISYUK Vladimir
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
-
YOSHIDA Tadashi
Faculty of Engineering, Musashi Institute of Technology
-
Artisyuk Vladimir
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
-
IMAMURA Tomo
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
-
Saito Masaki
Research Laboratory For Nuclear Reactor Tokyo Institute Of Technology
-
Yoshida Tadashi
Faculty Of Engineering Musashi Institute Of Technology
関連論文
- Measurement and Analysis of Reactivity Worth of ^Np Sample in Cores of TCA and FCA
- Transmutation of ^Sn in Spallation Targets of Accelerator-Driven Systems
- ^Cm Transmutation in Accelerator-Driven System
- Neutron Excess Generation by Fusion Neutron Source for Self-Consistency of Nuclear Energy System
- Inherent Protection of Plutonium by Doping Minor Actinide in Thermal Neutron Spectra
- Denaturing of Plutonium by Transmutation of Minor-Actinides for Enhancement of Proliferation Resistance
- Simultaneous Evaluation of Fission Cross Sections of Uranium and Platonium Isotopes for JENDL-3.3
- Effect of Transplutonium Doping on Approach to Long-life Core in Uranium-fueled PWR
- Long-life Water Cooled Small Reactor with U-Np-Pu Fuel
- Accumulation and Transmutation of Spallation Products in the Target of Accelerator-Driven System
- Fusion-Driven Transmutation of Fission Product Cesium in its Elemental Form
- Transmutation of Zirconium-93 in High-flux Blanket of Fusion Neutron Source
- Pandemonium Problem in Fission-Product Decay Heat Calculations Revisited
- Denaturing Generated Pu in Fast Breeder Reactor Blanket
- Possible Origin of the Gamma-ray Discrepancy in the Summation Calculations of Fission Product Decay Heat
- Production of Pa-U Fuel with Proliferation Resistance by 14MeV Neutron for Long-life Core
- Potential of ^Pa for Gas Cooled Long-life Core
- Protected Plutonium Breeding by Transmutation of Minor Actinides in Fast Breeder Reactor
- Evaluation of Proliferation Resistance of Plutonium Based on Decay Heat
- Nonlinear Fracture Mechanics Analysis of Surface Crack Propagation in Fusion Reactor First Wall by Cyclic High Heat Flux Irradiation
- Theoretical Treatment of the Asymptotic Behavior of Fission Product Decay Heat toward Very Short Cooling-Time
- Concept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors
- Radiation Dose as a Barrier against Proliferation for Advanced Fuel Compositions
- Application of Fusion Neutron Source for Denaturing of Plutonium
- Vectorization of Direct Fock Matrix Construction in DIRAC-DHF Calculations
- Blanket Safety by GEMSAFE Methodology