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Title: Startup of the Fission Converter Epithermal Neutron Irradiation Facility at the MIT Reactor

Abstract

A new epithermal neutron irradiation facility, based on a fission converter assembly placed in the thermal column outside the reactor core, has been put into operation at the Massachusetts Institute of Technology Research Reactor (MITR). This facility was constructed to provide a high-intensity, forward-directed beam for use in neutron capture therapy with an epithermal flux of [approximately equal to]10{sup 10} n/cm{sup 2}.s at the medical room entrance with negligible fast neutron and gamma-ray contamination. The fission converter assembly consists of 10 or 11 MITR fuel elements placed in an aluminum tank and cooled with D{sub 2}O. Thermal-hydraulic criteria were established based on heat deposition calculations. Various startup tests were performed to verify expected neutronic and thermal-hydraulic behavior. Flow testing showed an almost flat flow distribution across the fuel elements with <5% bypass flow. The total reactivity change caused by operation of the facility was measured at 0.014 {+-} 0.002% {delta}K/K. Thermal power produced by the facility was measured to be 83.1 {+-} 4.2 kW. All of these test results satisfied the thermal-hydraulic safety criteria. In addition, radiation shielding design measurements were made that verified design calculations for the neutronic performance.

Authors:
; ; ; ; ;  [1]
  1. Massachusetts Institute of Technology (United States)
Publication Date:
OSTI Identifier:
20826781
Resource Type:
Journal Article
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 139; Journal Issue: 2; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 0029-5450
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CONTAMINATION; DEPOSITION; DESIGN; EPITHERMAL NEUTRONS; FAST NEUTRONS; FISSION; FUEL ELEMENTS; GAMMA RADIATION; HEAT; HEAVY WATER; IRRADIATION; NEUTRON CAPTURE THERAPY; PERFORMANCE; REACTIVITY; RESEARCH REACTORS; TANKS; TESTING; THERMAL COLUMNS; THERMAL HYDRAULICS

Citation Formats

Newton, Jr, Thomas H, Riley, Kent J, Binns, Peter J, Kohse, Gordon E, Linwen, Hu, and Harling, Otto K. Startup of the Fission Converter Epithermal Neutron Irradiation Facility at the MIT Reactor. United States: N. p., 2002. Web.
Newton, Jr, Thomas H, Riley, Kent J, Binns, Peter J, Kohse, Gordon E, Linwen, Hu, & Harling, Otto K. Startup of the Fission Converter Epithermal Neutron Irradiation Facility at the MIT Reactor. United States.
Newton, Jr, Thomas H, Riley, Kent J, Binns, Peter J, Kohse, Gordon E, Linwen, Hu, and Harling, Otto K. 2002. "Startup of the Fission Converter Epithermal Neutron Irradiation Facility at the MIT Reactor". United States.
@article{osti_20826781,
title = {Startup of the Fission Converter Epithermal Neutron Irradiation Facility at the MIT Reactor},
author = {Newton, Jr, Thomas H and Riley, Kent J and Binns, Peter J and Kohse, Gordon E and Linwen, Hu and Harling, Otto K},
abstractNote = {A new epithermal neutron irradiation facility, based on a fission converter assembly placed in the thermal column outside the reactor core, has been put into operation at the Massachusetts Institute of Technology Research Reactor (MITR). This facility was constructed to provide a high-intensity, forward-directed beam for use in neutron capture therapy with an epithermal flux of [approximately equal to]10{sup 10} n/cm{sup 2}.s at the medical room entrance with negligible fast neutron and gamma-ray contamination. The fission converter assembly consists of 10 or 11 MITR fuel elements placed in an aluminum tank and cooled with D{sub 2}O. Thermal-hydraulic criteria were established based on heat deposition calculations. Various startup tests were performed to verify expected neutronic and thermal-hydraulic behavior. Flow testing showed an almost flat flow distribution across the fuel elements with <5% bypass flow. The total reactivity change caused by operation of the facility was measured at 0.014 {+-} 0.002% {delta}K/K. Thermal power produced by the facility was measured to be 83.1 {+-} 4.2 kW. All of these test results satisfied the thermal-hydraulic safety criteria. In addition, radiation shielding design measurements were made that verified design calculations for the neutronic performance.},
doi = {},
url = {https://www.osti.gov/biblio/20826781}, journal = {Nuclear Technology},
issn = {0029-5450},
number = 2,
volume = 139,
place = {United States},
year = {Thu Aug 15 00:00:00 EDT 2002},
month = {Thu Aug 15 00:00:00 EDT 2002}
}