194
Views
0
CrossRef citations to date
0
Altmetric
TECHNICAL PAPERS

A Stochastic Transport Model for the Cumulative Number of Fissions and Deposited Fission Energy

& ORCID Icon
Pages 189-211 | Received 16 Feb 2022, Accepted 31 May 2022, Published online: 25 Aug 2022

References

  • L. PÁL, “On the Theory of Stochastic Processes in Nuclear Reactors,” Il Nuovo Cimento., 7, S1, 25 (1958); https://doi.org/10.1007/BF02725086.
  • G. I. BELL, “Probability Distribution of Neutrons and Precursors in a Multiplying Assembly,” Ann. Phys., 21, 2, 243 (1963); https://doi.org/10.1016/0003-4916(63)90108-8.
  • G. I. BELL, “On the Stochastic Theory of Neutron Transport,” Nucl. Sci. Eng., 21, 390 (1965); https://doi.org/10.13182/NSE65-1.
  • M. M. R. WILLIAMS, Random Processes in Nuclear Reactors, Pergamon Press, (1974).
  • J. LEWINS, “Linear Stochastic Neutron Transport Theory,” Proc. R Soc. Lond. A Math. Phys. Sci., 362, 537 (1978).
  • I. PAZSIT and L. PÁL, Neutron Fluctuations, Elsevier, Oxford (2008).
  • A. K. PRINJA and F. J. SOUTO, “Some Considerations on Stochastic Neutron Populations,” Trans. Am. Nucl. Soc., 102, 255 (2010).
  • A. ENQVIST, I. PAZSIT, and S. POZZI, “The Number Distribution of Neutrons and Gamma Photons Generated in a Multiplying Sample,” Nucl. Instrum. Methods, 566, 2, 598 (2006); https://doi.org/10.1016/j.nima.2006.06.046.
  • E. D. FICHTL and R. S. BAKER, “Computing the Moments of the Neutron Population Using Deterministic Neutron Transport,” presented at the Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, Idaho, May 5–9, 2013.
  • A. K. PRINJA and P. F. O’ROURKE, “Pál-Bell Theory: Beyond the Neutron Number Distribution,” Proc. ANS M&C 2021—Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering,” Raleigh, North Carolina, October 3–7, 2021.
  • J. LESTONE, “Energy and Isotope Dependence of Neutron Multiplicity Distributions,” LA-UR-05-0288, Los Alamos National Laboratory (2005).
  • H. BATEMAN, Tables of Integral Transforms, McGraw-Hill, New York (1954).
  • B. MÉCHITOUA, “Monte Carlo Estimation of Nonextinction Probabilities,” Trans. Am. Nucl. Soc, 82, 134 (2000).
  • A. K. PRINJA, “On the Probability Density Function for Neutron Chain Extinction Times,” LA-UR-21-28716, Los Alamos National Laboratory (2021).
  • W. FELLER, An Introduction to Probability Theory and Its Applications, Vols. 1 and 2, Wiley (1968).
  • P. F. O’ROURKE, “Modeling and Simulation of Stochastic Neutron and Cumulative Deposited Fission Energy Distributions,” PhD Dissertation, University of New Mexico, Department of Nuclear Engineering (2020).
  • E. D. FICHTL and A. K. PRINJA, “The Asymptotic Probability Distribution of Fission Numbers in a Multiplying System,” Trans. Am. Nucl. Soc, 111, 1221 (2014).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.