Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (9): 90303-090303.doi: 10.11889/j.0253-3219.2020.hjs.43.090303

• NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE • Previous Articles    

Design of moderator for boron neutron capture therapy based on D-D neutron source

Yi GONG,Xingcai GUAN(),Qiang WANG Tieshan WANG   

  1. School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000, China
  • Received:2019-10-30 Revised:2020-02-21 Online:2020-09-15 Published:2020-09-09
  • Contact: Xingcai GUAN E-mail:tswang@lzu.edu.cn;guanxc@lzu.edu.cn
  • About author:GONG Yi, female, born in 1996, graduated from Lanzhou University with a master's degree in 2020, focusing on the design of BNCT neutron source and characterization of BNCT radiation field
  • Supported by:
    National Natural Science Foundation of China(11905090)

Abstract: Background

Boron neutron capture therapy (BNCT) is a promising targeted cancer radiotherapy. The neutron source is pivotal to BNCT. The epithermal neutron flux is one of crucial characteristics for the BNCT neutron source. Therefore, in order to evaluate the quality of the BNCT neutron source, neutron flux detectors have been developed to measure the epithermal neutron flux accurately in our previous work.

Purpose

This study aims to design a moderator for the D-D neutron source for evaluating the performances of the developed BNCT neutron flux detectors.

Methods

The MCNP5 (Monte Carlo N Particle Transport Code, version 5) was employed for the BNCT moderator design based on the D-D neutron source. First of all, the neutron spectrum of a D-D neutron source passing through a single-layer moderating material with different thickness was simulated. Then combined calculation was carried out for three moderator layers configured by different materials with various thickness.

Results

A suitable configuration of the BNCT moderator based on the D-D neutron source is obtained, that is, the combination of 5 cm thick polyethylene (PE) layer + 24 cm thick titanium trifluoride (TiF3) layer + 22 cm thick magnesium fluoride (MgF2) layer is adapted as the moderator material, 20 cm thick nickel (Ni) layer is employed as the reflector and 0.03 cm thick cadmium (Cd) sheet is used as the thermal neutron filter.

Conclusions

The moderated neutron beam can be used to evaluate the performances of the developed BNCT neutron flux detectors.

Key words: D-D neutron source, Moderator, BNCT, Monte Carlo simulation

CLC Number: 

  • TL99