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Title: Improved Sample Geometries for Fast Neutron Irradiations

Abstract

A Monte Carlo calculation provided a comparison of radiolytic yield efficiencies in a series of cylindrical sample geometries for irradiation by neutrons from the {sup 3}H(d,n){sup 4 }He reaction. Improvements of better than an order of magnitude were found over geometries used in previous work. The results permit optimizing either the product concentration or the total amount of the product. Use of the sample fluid to cool the tritium target of the neutron generator offers advantages in some cases. A by-product of the Monte Carlo procedure gave estimates of the linear energy transfer (LET) for 14 MeV neutron irradiation of hydrocarbons. Not surprisingly, the average initial LET depends sensitively on the carbon-to-hydrogen ratio of the hydrocarbon.

Authors:
;
Publication Date:
Research Org.:
Princeton University. New York Operations Office, AEC
Sponsoring Org.:
USDOE
OSTI Identifier:
973193
Report Number(s):
NYO-2807-42
TRN: US201015%%1001
DOE Contract Number:  
AT(30-1)-2807
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS; BY-PRODUCTS; FAST NEUTRONS; HYDROCARBONS; IRRADIATION; LET; NEUTRON GENERATORS; NEUTRONS; TRITIUM TARGET

Citation Formats

Hite, J R, and Axtmann, R C. Improved Sample Geometries for Fast Neutron Irradiations. United States: N. p., 1953. Web. doi:10.2172/973193.
Hite, J R, & Axtmann, R C. Improved Sample Geometries for Fast Neutron Irradiations. United States. https://doi.org/10.2172/973193
Hite, J R, and Axtmann, R C. Sat . "Improved Sample Geometries for Fast Neutron Irradiations". United States. https://doi.org/10.2172/973193. https://www.osti.gov/servlets/purl/973193.
@article{osti_973193,
title = {Improved Sample Geometries for Fast Neutron Irradiations},
author = {Hite, J R and Axtmann, R C},
abstractNote = {A Monte Carlo calculation provided a comparison of radiolytic yield efficiencies in a series of cylindrical sample geometries for irradiation by neutrons from the {sup 3}H(d,n){sup 4 }He reaction. Improvements of better than an order of magnitude were found over geometries used in previous work. The results permit optimizing either the product concentration or the total amount of the product. Use of the sample fluid to cool the tritium target of the neutron generator offers advantages in some cases. A by-product of the Monte Carlo procedure gave estimates of the linear energy transfer (LET) for 14 MeV neutron irradiation of hydrocarbons. Not surprisingly, the average initial LET depends sensitively on the carbon-to-hydrogen ratio of the hydrocarbon.},
doi = {10.2172/973193},
url = {https://www.osti.gov/biblio/973193}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1953},
month = {1}
}