↓ Skip to main content

Handbook of Nuclear Engineering

Overview of attention for book
Cover of 'Handbook of Nuclear Engineering'

Table of Contents

  1. Altmetric Badge
    Book Overview
  2. Altmetric Badge
    Chapter 1 Neutron Cross Section Measurements
  3. Altmetric Badge
    Chapter 2 Evaluated Nuclear Data
  4. Altmetric Badge
    Chapter 3 Neutron Slowing Down and Thermalization
  5. Altmetric Badge
    Chapter 4 Nuclear Data Preparation
  6. Altmetric Badge
    Chapter 5 General Principles of Neutron Transport
  7. Altmetric Badge
    Chapter 6 Nuclear Materials and Irradiation Effects
  8. Altmetric Badge
    Chapter 7 Mathematics for Nuclear Engineering
  9. Altmetric Badge
    Chapter 8 Multigroup Neutron Transport and Diffusion Computations
  10. Altmetric Badge
    Chapter 9 Lattice Physics Computations
  11. Altmetric Badge
    Chapter 10 Core Isotopic Depletion and Fuel Management
  12. Altmetric Badge
    Chapter 11 Radiation Shielding and Radiological Protection
  13. Altmetric Badge
    Chapter 12 High Performance Computing in Nuclear Engineering
  14. Altmetric Badge
    Chapter 13 Analysis of Reactor Fuel Rod Behavior
  15. Altmetric Badge
    Chapter 14 Noise Techniques in Nuclear Systems
  16. Altmetric Badge
    Chapter 15 Deterministic and Probabilistic Safety Analysis
  17. Altmetric Badge
    Chapter 16 Multiphase Flows: Compressible Multi-Hydrodynamics
  18. Altmetric Badge
    Chapter 17 Sensitivity and Uncertainty Analysis, Data Assimilation, and Predictive Best-Estimate Model Calibration
  19. Altmetric Badge
    Chapter 18 Reactor Physics Experiments on Zero Power Reactors
  20. Altmetric Badge
    Chapter 19 Pressurized LWRs and HWRs in the Republic of Korea
  21. Altmetric Badge
    Chapter 20 VVER-Type Reactors of Russian Design
  22. Altmetric Badge
    Chapter 21 Sodium Fast Reactor Design: Fuels, Neutronics, Thermal-Hydraulics, Structural Mechanics and Safety
  23. Altmetric Badge
    Chapter 22 Gas-Cooled Reactors
  24. Altmetric Badge
    Chapter 23 Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design
  25. Altmetric Badge
    Chapter 24 GEM*STAR: The Alternative Reactor Technology Comprising Graphite, Molten Salt, and Accelerators
  26. Altmetric Badge
    Chapter 25 Front End of the Fuel Cycle
  27. Altmetric Badge
    Chapter 26 Transuranium Elements in the Nuclear Fuel Cycle
  28. Altmetric Badge
    Chapter 27 Decommissioning of Nuclear Plants
  29. Altmetric Badge
    Chapter 28 The Scientific Basis of Nuclear Waste Management
  30. Altmetric Badge
    Chapter 29 Proliferation Resistance and Safeguards
Attention for Chapter 18: Reactor Physics Experiments on Zero Power Reactors
Altmetric Badge

Mentioned by

wikipedia
1 Wikipedia page

Readers on

mendeley
17 Mendeley
You are seeing a free-to-access but limited selection of the activity Altmetric has collected about this research output. Click here to find out more.
Chapter title
Reactor Physics Experiments on Zero Power Reactors
Chapter number 18
Book title
Handbook of Nuclear Engineering
Published by
Springer, Boston, MA, January 2010
DOI 10.1007/978-0-387-98149-9_18
Book ISBNs
978-0-387-98130-7, 978-0-387-98149-9
Authors

Gilles Bignan, Philippe Fougeras, Patrick Blaise, Jean-Pascal Hudelot, Frédéric Mellier, Bignan, Gilles, Fougeras, Philippe, Blaise, Patrick, Hudelot, Jean-Pascal, Mellier, Frédéric

Mendeley readers

Mendeley readers

The data shown below were compiled from readership statistics for 17 Mendeley readers of this research output. Click here to see the associated Mendeley record.

Geographical breakdown

Country Count As %
Unknown 17 100%

Demographic breakdown

Readers by professional status Count As %
Student > Ph. D. Student 5 29%
Researcher 5 29%
Student > Master 2 12%
Other 1 6%
Student > Doctoral Student 1 6%
Other 2 12%
Unknown 1 6%
Readers by discipline Count As %
Engineering 6 35%
Physics and Astronomy 5 29%
Materials Science 2 12%
Energy 1 6%
Chemistry 1 6%
Other 0 0%
Unknown 2 12%