Long-life Water Cooled Small Reactor with U-Np-Pu Fuel
スポンサーリンク
概要
- 論文の詳細を見る
The paper presents the advanced concept of a long-life small light water reactor in which the fuel irradiation time is comparable with reactor life-time. The equilibrium analysis reveals that the U–Np–Pu fuel with unique neutronic properties allows to keep sufficient criticality up to burnup value about 140 GWd/tHM. The fuel recycle does not lead to additional Pu accumulation. Both Pu and Np are well protected against un-controlled proliferation by a large fraction of 238Pu in their mixture. To improve the reactor safety, the wider fuel pin lattice was applied. The radiation damage of structural materials is within the stainless steel limitation.
- 社団法人 日本原子力学会の論文
- 2001-07-25
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
-
Artisyuk Vladimir
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
-
SHMELEV Anatolii
Moscow Engineering Physics Institute
-
NIKITIN Konstantin
Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
-
KAWASHIMA Masatoshi
Toshiba Corporation, Power Systems & Services Company
-
Nikitin Konstantin
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
-
Kawashima Masatoshi
Toshiba Corporation
-
Kawashima Masatoshi
Toshiba Corporation Power Systems & Services Company
-
Saito Masakatu
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
-
Saito Masaki
Research Laboratory For Nuclear Reactor Tokyo 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
- 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
- ICONE11-36198 REACTOR PHYSICS EXPERIMENTS AND ANALYSIS FOR BURNABLE POISON IN ULTRA-LONG LIFE, SMALL LMR
- Denaturing Generated Pu in Fast Breeder Reactor Blanket
- 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
- 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
- Blanket Safety by GEMSAFE Methodology