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Journal of Nuclear Engineering, Volume 5, Issue 2

June 2024 - 5 articles

Cover Story: The lifespan of core graphite under neutron irradiation in a commercial molten salt reactor (MSR) has an important influence on its economy. Flattening the fast neutron flux (≥0.05 MeV) distribution in the core is the main method to extend the graphite irradiation lifespan. In this paper, the effects of the key parameters of MSRs on fast neutron flux distribution, including volume fraction (VF) of fuel salt, pitch of hexagonal fuel assembly, core zoning, and layout of control rod assemblies, were studied. Flattening the fast neutron flux distribution of a commercial MSR core was then carried out by zoning the core into two regions under different VFs. Considering both the fast neutron flux distribution and burnup depth, an optimized core was obtained. View this paper
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Articles (5)

  • Technical Note
  • Open Access
3 Citations
1,640 Views
11 Pages

Immediate Radiological Risk Evaluation after a Hypothetical Radioactive Off-Site Release Event

  • Ana Carolina Lodi Lobato,
  • Sérgio Gavazza,
  • Avelino Santos,
  • Rodrigo Carneiro Curzio and
  • Edson R. Andrade

19 June 2024

This study used an analytical computational model to evaluate safe zones in contaminated areas that may result from a hypothetical significant off-site release from a nuclear power plant. The model, considering local atmospheric stability, wind direc...

  • Article
  • Open Access
1,876 Views
18 Pages

10 May 2024

The lifespan of core graphite under neutron irradiation in a commercial molten salt reactor (MSR) has an important influence on its economy. Flattening the fast neutron flux (≥0.05 MeV) distribution in the core is the main method to extend the gra...

  • Article
  • Open Access
2,430 Views
18 Pages

The Effects of Irradiation on Structure and Leaching of Pure and Doped Thin-Film Ceria SIMFUEL Models Prepared via Polymer-Templated Deposition

  • Alistair F. Holdsworth,
  • Zizhen Feng,
  • Ruth Edge,
  • John P. Waters,
  • Alice M. Halman,
  • David Collison,
  • Kathryn George,
  • Louise S. Natrajan and
  • Melissa A. Denecke

8 May 2024

When studying hazardous materials such as spent nuclear fuel (SNF), the minimisation of sample volumes is essential, together with the use of chemically-similar surrogates where possible. For example, the bulk behaviour of urania (UO2) can be mimicke...

  • Article
  • Open Access
4 Citations
2,749 Views
22 Pages

24 April 2024

Reliability and efficiency of valves are necessary for precise control and sufficient heat-flow to heat application plants for the integrated energy systems of nuclear power plants (NPPs). Strategic Management Analysis Requirement and Technology (SMA...

  • Article
  • Open Access
1,609 Views
14 Pages

31 March 2024

The development of compact neutron sources for applications is extensive and features many approaches. For ion-based approaches, several projects with different parameters exist. This article focuses on ion-based neutron production below the spallati...

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J. Nucl. Eng. - ISSN 2673-4362Creative Common CC BY license