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Title: INITIAL Reactor Laboratory Irradiation Safety Calculations

Abstract

The INITIAL reactor experiment being pitched to UC Davis and agreed upon by the professor teaching the course is a natural uranium neutron activation experiment in the McClellan Nuclear Research Center (MNCR) reactor. Due to the complex nature of the build up and decay of fission products in nuclear fuel, and the subsequent variety of radiation emitting nuclides, the following dose calculations are provided to ensure the safety of the experiment. These calculations are performed for both non-cadmium covered (Ex:1 - bare) and cadmium covered (Ex:2 - Cd) neutron irradiated UO 2 samples.

Authors:
 [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1427398
Report Number(s):
LA-UR-18-22321
DOE Contract Number:  
AC52-06NA25396
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
61 RADIATION PROTECTION AND DOSIMETRY

Citation Formats

Mendoza, Paul Michael. INITIAL Reactor Laboratory Irradiation Safety Calculations. United States: N. p., 2018. Web. doi:10.2172/1427398.
Mendoza, Paul Michael. INITIAL Reactor Laboratory Irradiation Safety Calculations. United States. doi:10.2172/1427398.
Mendoza, Paul Michael. Mon . "INITIAL Reactor Laboratory Irradiation Safety Calculations". United States. doi:10.2172/1427398. https://www.osti.gov/servlets/purl/1427398.
@article{osti_1427398,
title = {INITIAL Reactor Laboratory Irradiation Safety Calculations},
author = {Mendoza, Paul Michael},
abstractNote = {The INITIAL reactor experiment being pitched to UC Davis and agreed upon by the professor teaching the course is a natural uranium neutron activation experiment in the McClellan Nuclear Research Center (MNCR) reactor. Due to the complex nature of the build up and decay of fission products in nuclear fuel, and the subsequent variety of radiation emitting nuclides, the following dose calculations are provided to ensure the safety of the experiment. These calculations are performed for both non-cadmium covered (Ex:1 - bare) and cadmium covered (Ex:2 - Cd) neutron irradiated UO2 samples.},
doi = {10.2172/1427398},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {3}
}

Technical Report:

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