Solitary wave form of reaction rate in graphite diffusive medium using different neutron absorbers
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Seyede Nasrin Hosseinimotlagh
,
Abuzar Shakeri
,
Mohammad Ali Zarei
Abstract
Graphite nuclear properties such as moderating power and absorption cross-section, are not as good as those of heavy water. But its pure form can be prepared. Its structural and thermal properties are good and it has a high thermal conductivity. The thermal neutron in graphite performs an average of 1,200 scattering collisions before it is absorbed. This very low absorption cross section makes graphite as an ideal material for applications in nuclear reactors. In the current research, graphite is assumed as a diffusive medium due to its low absorption cross-section (0.0035 b) and having a low mass close to the neutron mass. In this medium: Boron (10B), Cadmium (113Cd), Samarium (149Sm), Europium (151Eu), Hafnium (177Hf) and Gadolinium (157Gd), separately are also considered as neutron absorbers. The aim of this paper is obtaining the solitary wave form of reaction rate in graphite diffusive medium using these neutron absorbers.
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Research ethics: Not applicable.
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Informed consent: Not applicable.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Use of Large Language Models, AI and Machine Learning Tools: None declared.
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Conflict of interest: The authors declare no conflicts of interest regarding this article.
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Research funding: None declared.
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Data availability: Not applicable.
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Articles in the same Issue
- Frontmatter
- Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies
- Methodology of probabilistic safety assessment for transportation of radioactive material
- A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event
- A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management
- Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction
- Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−xNd x O4 (0 ≤ x ≤ 0.9): an analogue for actinicles immobilization
- Examination of the use of thorium-based fuel for burning minor actinides in European sodium cooled fast reactor
- Solitary wave form of reaction rate in graphite diffusive medium using different neutron absorbers
- Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components
- Thermal-hydraulic simulation of loss of flow accident for WWR-S research reactor
- A quick parameter configuration tool for SCHISM’s ocean transport simulation of radioactive materials
- Main heat transport system configuration influence on steam drum level control and safety for a pressure tube type boiling water reactor with multiple interconnected loops
- Testing the thermal performance of water cooling towers
- Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm
- Calendar of events
Articles in the same Issue
- Frontmatter
- Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies
- Methodology of probabilistic safety assessment for transportation of radioactive material
- A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event
- A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management
- Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction
- Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−xNd x O4 (0 ≤ x ≤ 0.9): an analogue for actinicles immobilization
- Examination of the use of thorium-based fuel for burning minor actinides in European sodium cooled fast reactor
- Solitary wave form of reaction rate in graphite diffusive medium using different neutron absorbers
- Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components
- Thermal-hydraulic simulation of loss of flow accident for WWR-S research reactor
- A quick parameter configuration tool for SCHISM’s ocean transport simulation of radioactive materials
- Main heat transport system configuration influence on steam drum level control and safety for a pressure tube type boiling water reactor with multiple interconnected loops
- Testing the thermal performance of water cooling towers
- Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm
- Calendar of events
