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The Ohio State University

Reconsideration of Inherent Neutron Sources in Liquid Fuel of Molten Salt Reactors

Abstract

dc:description

Calculation of inherent neutron sources from alpha-n and gamma-n reactions in molten fluoride fuel salts using current gamma-n and alpha-n cross-sections and codes where possible. Original inherent neutron source was calculated for Molten Salt Reactor Experiment (MSRE) in 1959 using then-determined alpha-n cross-sections and an estimate for gamma-n cross-section for beryllium-9. Values selected to generate conservative neutron population value for determining required external neutron source and operational neutron population. Inherent neutron source values have not been revisited for molten salt fluid fuel reactors since. Updated alpha-n reaction rates per cubic centimeter calculated using SOURCES4C, compared against original Oak Ridge National Laboratory calculations for MSRE. Fuel salt aging simulated using ORIGEN for 300 days (no power) and a 150-day power cycle at 200 kWt followed by 150 days cooling, alpha-n source calculated by SOURCES4C and compared to alpha-n rates given by ORIGEN. Gamma-n reaction rates calculated from updated normalized cross-sections and compared to original ORNL 0.5 mb cross-section, which was for beryllium-9 salt component only. Recalculated reaction rates are markedly greater than original MSRE rates in fresh (unaged) fuel salt.

Degree

thesis:*
Name thesis:degree_name
Master of Science
Level thesis:degree_level
masters
Discipline thesis:degree_discipline
Nuclear Engineering
Grantor dc:publisher
The Ohio State University
Year dc:date
2013

Author and committee

dc:creator, dc:contributor.*
Author dc:creator
  • Powell, Walter Newton
Contributors dc:contributor
  • Cao, Lei

Subjects

dc:subject × 7

Rights

dc:rights
Statement dc:rights
  • unrestricted
  • This thesis or dissertation is protected by copyright: all rights reserved. It may not be copied or redistributed beyond the terms of applicable copyright laws.
Language dc:language
English

Identifiers

dc:identifier.*
OAI identifier oai:identifier
oai:etd.ohiolink.edu:osu1364909574

Chain of custody

source
Harvested from
OhioLINK
Base URL
etd.ohiolink.edu/acprod/odb_etd/ws/oai/oai
Last updated
2026-07-24
Source record
OAI-PMH GetRecord
citation

Powell, Walter Newton. Reconsideration of Inherent Neutron Sources in Liquid Fuel of Molten Salt Reactors. masters thesis, The Ohio State University, 2013. http://rave.ohiolink.edu/etdc/view?acc_num=osu1364909574