skip to main content

Title: Consideration of a ultracold neutron source in two-dimensional cylindrical geometry by taking simulated boundaries

A new idea to calculate ultracold neutron (UCN) production by using Monte Carlo simulation method to calculate the cold neutron (CN) flux and an analytical approach to calculate the UCN production from the simulated CN flux was given. A super-thermal source (UCN source) was modeled based on an arrangement of D{sub 2}O and solid D{sub 2} (sD{sub 2}). The D{sub 2}O was investigated as the neutron moderator, and sD{sub 2} as the converter. In order to determine the required parameters, a two-dimensional (2D) neutron balance equation written in Matlab was combined with the MCNPX simulation code. The 2D neutron-transport equation in cylindrical (ρ − z) geometry was considered for 330 neutron energy groups in the sD{sub 2}. The 2D balance equation for UCN and CN was solved using simulated CN flux as boundary value. The UCN source dimensions were calculated for the development of the next UCN source. In the optimal condition, the UCN flux and the UCN production rate (averaged over the sD{sub 2} volume) equal to 6.79 × 10{sup 6} cm{sup −2}s{sup −1} and 2.20 ×10{sup 5} cm{sup −3}s{sup −1}, respectively.
Authors:
 [1] ;  [2] ; ;  [3]
  1. Physics Department, Persian Gulf University, Bushehr 75169 (Iran, Islamic Republic of)
  2. (Iran, Islamic Republic of)
  3. Department of Physics, University of Birjand, Birjand 97175 (Iran, Islamic Republic of)
Publication Date:
OSTI Identifier:
22250823
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Advances; Journal Volume: 4; Journal Issue: 1; Other Information: (c) 2014 Author(s); Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; COMPUTERIZED SIMULATION; HEAVY WATER; MONTE CARLO METHOD; NEUTRON TRANSPORT THEORY; SOLIDS; ULTRACOLD NEUTRONS