Experimental and Theoretical Studies of Heavy-Water Homogeneous Two-Region System
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概要
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A series of critical experiments and theoretical analyses has been made on two-region systems in which a heavy water solution of uranyl sulfate with <SUP>235</SUP>U enrichment of about 20% is surrounded by heavy water, poisoned with B or mixed with ThO<SUB>2</SUB>. D-to-<SUP>235</SUP>U atomic ratios in the core solutions ranged 4, 500-1, 000, depending on the core diameter and the blanket oncentration.<BR>The theoretical effective multiplication factor is decreased by treating the leakage of fast neutrons from the core rigorously, and is increased by using spatial-dependent effective cross sections. These treatments are justified by the agreement found between the calculated and measured values for the Cd ratio and the thermal flux distribution. The disagreement seen in the effective multiplication factor between the theoretical and experimental values may be attributed to uncertainty in the resonance integral of <SUP>235</SUP>U. The discrepancy in the effective multiplication factors does not exceed 1%, when the accepted value of νIf-Ia is reduced to a smaller value.
- 一般社団法人 日本原子力学会の論文
著者
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KATSURAGI Satoru
Japan Atomic Energy Research Institute, Tokai-mura, lbaraki-ken.
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KATSURAGI Satoru
Japan Atomic Energy Research Institute
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HIROTA Jitsuya
Japan Atomic Energy Research Institute, Tokai-mura, lbaraki-ken.
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SAITO Reiko
Japan Atomic Energy Research Institute, Tokai-mura, lbaraki-ken.
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YASUNO Takehiko
Japan Atomic Energy Research Institute, Tokai-mura, lbaraki-ken.
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HIROTA Jitsuya
Japan Atomic Energy Reseach Institute
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YASUNO Takehiko
Japan Atomic Energy Reseach Institute
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SAITO Reiko
Japan Atomic Energy Research Institute
関連論文
- A Method Using Nuclear Emulsions for Measuring the Anisotropy of Fast Neutron Fluxes due to Arrangement of Fast Core Cell
- Studies of the Criticality of 20% Enriched Uranium Fast Critical Assemblies (FCA-I)
- Experimental and Theoretical Studies of Heavy-Water Homogeneous Two-Region System
- Sodium-Void Experiment in Unit k-infinity Core
- Investigation of Effective Inelastic Cross Section for Fast Reactor Compositions
- Number of Resonances to be Adopted for Obtaining Practically Reliable Cross Section Curves
- Accuracy of Analytical Treatments for Resonance Absorption in Doppler Resonance Regions
- Doppler Coefficient Measurements in FCA
- A Note on Treatments of Sodium Void Reactivity Effects in a Large Fast Reactor
- Higher Order Perturbation Method in Reactor Calculation
- Modal Perturbation Method Applied to Diffusion Equation
- Prompt Neutron Life-time in a Reflected System