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Title: Advances in the computation of the Sjöstrand, Rossi, and Feynman distributions

Journal Article · · Progress in Nuclear Energy
ORCiD logo [1];  [1];  [2];  [2];  [3]
  1. Argonne National Lab. (ANL), Lemont, IL (United States)
  2. Karlsruhe Inst. of Technology (KIT) (Germany)
  3. Kyoto Univ. (Japan)

This study illustrates recent computational advances in the application of the Sjöstrand (area), Rossi, and Feynman methods to estimate the effective multiplication factor of a subcritical system driven by an external neutron source. The methodologies introduced in this study have been validated with the experimental results from the KUKA facility of Japan by Monte Carlo (MCNP6 and MCNPX) and deterministic (ERANOS, VARIANT, and PARTISN) codes. When the assembly is driven by a pulsed neutron source generated by a particle accelerator and delayed neutrons are at equilibrium, the Sjöstrand method becomes extremely fast if the integral of the reaction rate from a single pulse is split into two parts. These two integrals distinguish between the neutron counts during and after the pulse period. To conclude, when the facility is driven by a spontaneous fission neutron source, the timestamps of the detector neutron counts can be obtained up to the nanosecond precision using MCNP6, which allows obtaining the Rossi and Feynman distributions.

Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC02-06CH11357
OSTI ID:
1422765
Alternate ID(s):
OSTI ID: 1550620
Journal Information:
Progress in Nuclear Energy, Vol. 101, Issue PC; ISSN 0149-1970
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 8 works
Citation information provided by
Web of Science

References (12)

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Conceptual design of multi-targets for accelerator-driven system experiments with 100-MeV protons journal April 2013
Pulse superimposition calculational methodology for estimating the subcriticality level of nuclear fuel assemblies
  • Talamo, Alberto; Gohar, Y.; Rabiti, C.
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journal July 2009
MCNPX, MONK, and ERANOS analyses of the YALINA Booster subcritical assembly journal May 2011
Monte Carlo and deterministic calculation of the Bell and Glasstone spatial correction factor journal September 2012
Monte Carlo and Deterministic Neutronics Analyses of YALINA Thermal Facility and Comparison with Experimental Results journal November 2013
Correction factor for the experimental prompt neutron decay constant journal December 2013

Cited By (2)

Calculation of the prompt neutron decay constant for the KUCA facility driven by a stationary or pulsed external neutron source journal August 2019
Paralyzable and non-paralyzable dead-time corrections for the neutron detectors of the KUCA facility driven by external neutron sources journal September 2019

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