skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Accelerator-based neutron source for boron neutron capture therapy (BNCT) and method

Abstract

A source for boron neutron capture therapy (BNCT) comprises a body of photoneutron emitter that includes heavy water and is closely surrounded in heat-imparting relationship by target material; one or more electron linear accelerators for supplying electron radiation having energy of substantially 2 to 10 MeV and for impinging such radiation on the target material, whereby photoneutrons are produced and heat is absorbed from the target material by the body of photoneutron emitter. The heavy water is circulated through a cooling arrangement to remove heat. A tank, desirably cylindrical or spherical, contains the heavy water, and a desired number of the electron accelerators circumferentially surround the tank and the target material as preferably made up of thin plates of metallic tungsten. Neutrons generated within the tank are passed through a surrounding region containing neutron filtering and moderating materials and through neutron delimiting structure to produce a beam or beams of epithermal neutrons normally having a minimum flux intensity level of 1.0{times}10{sup 9} neutrons per square centimeter per second. Such beam or beams of epithermal neutrons are passed through gamma ray attenuating material to provide the required epithermal neutrons for BNCT use. 3 figs.

Inventors:
; ; ;
Publication Date:
Research Org.:
Lockheed Martin Idaho Tech Co
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
350325
Patent Number(s):
US 5,903,622/A/
Application Number:
PAN: 8-713,317
Assignee:
Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States)
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Patent
Resource Relation:
Other Information: PBD: 11 May 1999
Country of Publication:
United States
Language:
English
Subject:
07 ISOTOPE AND RADIATION SOURCE TECHNOLOGY; 43 PARTICLE ACCELERATORS; 55 BIOLOGY AND MEDICINE, BASIC STUDIES; NEUTRON SOURCES; NEUTRON CAPTURE THERAPY; LINEAR ACCELERATORS; DESIGN; COOLING SYSTEMS; EPITHERMAL NEUTRONS

Citation Formats

Yoon, W Y, Jones, J L, Nigg, D W, and Harker, Y D. Accelerator-based neutron source for boron neutron capture therapy (BNCT) and method. United States: N. p., 1999. Web.
Yoon, W Y, Jones, J L, Nigg, D W, & Harker, Y D. Accelerator-based neutron source for boron neutron capture therapy (BNCT) and method. United States.
Yoon, W Y, Jones, J L, Nigg, D W, and Harker, Y D. Tue . "Accelerator-based neutron source for boron neutron capture therapy (BNCT) and method". United States.
@article{osti_350325,
title = {Accelerator-based neutron source for boron neutron capture therapy (BNCT) and method},
author = {Yoon, W Y and Jones, J L and Nigg, D W and Harker, Y D},
abstractNote = {A source for boron neutron capture therapy (BNCT) comprises a body of photoneutron emitter that includes heavy water and is closely surrounded in heat-imparting relationship by target material; one or more electron linear accelerators for supplying electron radiation having energy of substantially 2 to 10 MeV and for impinging such radiation on the target material, whereby photoneutrons are produced and heat is absorbed from the target material by the body of photoneutron emitter. The heavy water is circulated through a cooling arrangement to remove heat. A tank, desirably cylindrical or spherical, contains the heavy water, and a desired number of the electron accelerators circumferentially surround the tank and the target material as preferably made up of thin plates of metallic tungsten. Neutrons generated within the tank are passed through a surrounding region containing neutron filtering and moderating materials and through neutron delimiting structure to produce a beam or beams of epithermal neutrons normally having a minimum flux intensity level of 1.0{times}10{sup 9} neutrons per square centimeter per second. Such beam or beams of epithermal neutrons are passed through gamma ray attenuating material to provide the required epithermal neutrons for BNCT use. 3 figs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {5}
}