Published 2017 | Version v1
Miscellaneous

Kernel density estimation method in time-dependent Monte Carlo simulation

Creators

  • 1. Inst. of Applied Physics and Computational Mathematics, Beijing (China)

Description

With the development of computer technology, direct Monte Carlo simulation of reactor transient behaviors has received more attention. The state-of-the-art method in time-dependent Monte Carlo simulation involves linearizing the equations over a time step; snapshots of the neutrons at the time boundaries are created as the source for the next time step. How to construct the neutron distribution at time boundary is an important new problem. In this paper we present a kernel density estimation (KDE) method in sampling time boundary sources. This method can obtain the continuous distribution from discrete time boundary sources. For subcritical systems, KDE method effectively improves confidence of direct Monte Carlo simulation. (author)

Part of:
Our nuclear future: renewal and responsibility. 37th Annual CNS conference and 41st CNS/CNA student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-24-7
Imprint Title
Our nuclear future: renewal and responsibility. 37th Annual CNS conference and 41st CNS/CNA student conference
Imprint Pagination
408 Megabytes
Journal Page Range
[4 p.]

Conference

Title
37. annual Canadian Nuclear Society conference; 41. CNS/CNA student conference
Dates
4-7 Jun 2017
Place
Niagara Falls, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
50008961
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; MONTE CARLO METHOD; NEUTRON TRANSPORT; SUBCRITICAL ASSEMBLIES; TRANSIENT OVERPOWER ACCIDENTS
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; EXPERIMENTAL REACTORS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION

Optional Information

Notes
10 refs., 3 figs.