Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

The neutron number probability distribution in coupled lumped assemblies

Journal Article · · Annals of Nuclear Energy
 [1];  [2]
  1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
  2. Univ. of New Mexico, Albuquerque, NM (United States)
Here, the validity of the gamma distribution in describing the neutron number probability distribution function for both isolated and coupled multiplying assemblies when constrained to reproduce the true mean and variance is investigated in lumped geometry by numerical comparison with kinetic Monte Carlo simulations. The mean and variance are obtained from numerical solution of moment equations constructed from the relevant forward Master equation with assembly coupling coefficients obtained from a view factor method. Numerical results for a two-group, two coupled assemblies model, with static and dynamic reactivity insertion, show that except for subcritical assemblies, the gamma distribution well-approximates the number distribution. Differences in the fast and thermal neutron population shapes are explained in terms of effective source strengths due to downscatter and coupling.
Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
89233218CNA000001
OSTI ID:
2477787
Alternate ID(s):
OSTI ID: 1994419
Report Number(s):
LA-UR--23-20518
Journal Information:
Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Vol. 193; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (11)

Probability distribution of neutrons and precursors in a multiplying assembly journal February 1963
A general method for numerically simulating the stochastic time evolution of coupled chemical reactions journal December 1976
Solution of the neutron survival probability equation using k-eigenmode expansion journal December 2019
Theoretical foundations of dynamical Monte Carlo simulations journal July 1991
Univariate Distribution Relationships journal February 2008
The Simulation of Probability Distribution of the Burst Waiting Time of Neutron Initiation journal September 2011
Initiation of Persistent Fission Chains in the Fast Burst Reactor Caliban journal June 2014
Burst Wait-Times in the Caliban Reactor Using the Gamma Probability Distribution Function journal May 2016
Assembly of Fissionable Material in the Presence of a Weak Neutron Source journal December 1960
On the Stochastic Theory of Neutron Transport journal March 1965
Stochastic Kinetic Theory for a Space- and Energy-Dependent Zero Power Nuclear Reactor Model journal June 1969

Similar Records

A Lumped Stochastic Model of Coupled Neutronic Assemblies
Technical Report · Mon Oct 19 00:00:00 EDT 2020 · OSTI ID:1680005

Neutron Number Probability Distributions in a Subcritical System Using the Forward Master Equation
Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:22991994

A Stochastic Transport Model for the Cumulative Number of Fissions and Deposited Fission Energy
Journal Article · Wed Aug 24 20:00:00 EDT 2022 · Nuclear Science and Engineering · OSTI ID:1895133