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Title: Examining Computational Assumptions For Godiva IV

Abstract

Over the course of summer 2016, the effects of several computational modeling assumptions with respect to the Godiva IV reactor were examined. The majority of these assumptions pertained to modeling errors existing in the control rods and burst rod. The Monte Carlo neutron transport code, MCNP, was used to investigate these modeling changes, primarily by comparing them to that of the original input deck specifications.

Authors:
 [1];  [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
OSTI Identifier:
1304745
Report Number(s):
LA-UR-16-26194
TRN: US1601791
DOE Contract Number:  
AC52-06NA25396
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; GODIVA REACTOR; NEUTRON TRANSPORT THEORY; MONTE CARLO METHOD; COMPUTERIZED SIMULATION; COMPARATIVE EVALUATIONS; CONTROL ELEMENTS; ERRORS; SPECIFICATIONS; MATHEMATICAL MODELS

Citation Formats

Kirkland, Alexander Matthew, and Jaegers, Peter James. Examining Computational Assumptions For Godiva IV. United States: N. p., 2016. Web. doi:10.2172/1304745.
Kirkland, Alexander Matthew, & Jaegers, Peter James. Examining Computational Assumptions For Godiva IV. United States. doi:10.2172/1304745.
Kirkland, Alexander Matthew, and Jaegers, Peter James. Thu . "Examining Computational Assumptions For Godiva IV". United States. doi:10.2172/1304745. https://www.osti.gov/servlets/purl/1304745.
@article{osti_1304745,
title = {Examining Computational Assumptions For Godiva IV},
author = {Kirkland, Alexander Matthew and Jaegers, Peter James},
abstractNote = {Over the course of summer 2016, the effects of several computational modeling assumptions with respect to the Godiva IV reactor were examined. The majority of these assumptions pertained to modeling errors existing in the control rods and burst rod. The Monte Carlo neutron transport code, MCNP, was used to investigate these modeling changes, primarily by comparing them to that of the original input deck specifications.},
doi = {10.2172/1304745},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Aug 11 00:00:00 EDT 2016},
month = {Thu Aug 11 00:00:00 EDT 2016}
}

Technical Report:

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