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Title: Analysis of the neutronic behavior of the Maryland University training reactor

Abstract

This effort analyzed the potential for the Maryland University Research Reactor to received slightly burned fuel in a new core configuration.

Authors:
 [1];  [1]
  1. Oregon State Univ., Corvallis, OR (United States)
Publication Date:
Research Org.:
Oregon State Univ., Corvallis, OR (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1394642
Report Number(s):
Final Report DE-NE0008618
DOE Contract Number:
NE0008618
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats

Reese, Steven, and Schickler, Robert. Analysis of the neutronic behavior of the Maryland University training reactor. United States: N. p., 2017. Web. doi:10.2172/1394642.
Reese, Steven, & Schickler, Robert. Analysis of the neutronic behavior of the Maryland University training reactor. United States. doi:10.2172/1394642.
Reese, Steven, and Schickler, Robert. 2017. "Analysis of the neutronic behavior of the Maryland University training reactor". United States. doi:10.2172/1394642. https://www.osti.gov/servlets/purl/1394642.
@article{osti_1394642,
title = {Analysis of the neutronic behavior of the Maryland University training reactor},
author = {Reese, Steven and Schickler, Robert},
abstractNote = {This effort analyzed the potential for the Maryland University Research Reactor to received slightly burned fuel in a new core configuration.},
doi = {10.2172/1394642},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2017,
month = 7
}

Technical Report:

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  • A study of the elimination and control of potential hazards arising from a proposed reactor installation at the University of IIlinois is presented. Criteria for the metallation include maximum flexibility for experiments, inherent safety, and the capability for isotope production. Explanations of the safety and control features of the reactor (TRIGA), as well as the special precautions taken in building design to complete operational safety of the whole installation, are presented. (J.R.D.)
  • Overall, the instrumentation obtained under the first year 1992-93 University Reactor Instrumentation Program grant assured that the goals of the program were well understood and met as well as possible at the level of support provided for the University of Florida Training Reactor facility. Though the initial grant support of $21,000 provided toward the purchase of $23,865 of proposed instrumentation certainly did not meet many of the facility's needs, the instrumentation items obtained and implemented did meet some critical needs and hence the goals of the Program to support modernization and improvement of reactor facilities such as the UFTR withinmore » the academic community. Similarly, the instrumentation obtained under the second year 1993-94 University Reactor Instrumentation Program grant again met some of the critical needs for instrumentation support at the UFTR facility. Again, though the grant support of $32,799 for proposed instrumentation at the same cost projection does not need all of the facility's needs, it does assure continued facility viability and improvement in operations. Certainly, reduction of forced unavailability of the reactor is the most obvious achievement of the University Reactor Instrumentation Program to date at the UFTR. Nevertheless, the ability to close out several expressed-inspection concerns of the Nuclear Regulatory Commission with acquisition of the low level survey meter and the area radiation monitoring system is also very important. Most importantly, with modest cost sharing the facility has been able to continue and even accelerate the improvement and modernization of a facility, especially in the Neutron Activation Analysis Laboratory, that is used by nearly every post-secondary school in the State of Florida and several in other states, by dozens of departments within the University of Florida, and by several dozen high schools around the State of Florida on a regular basis. Better, more reliable service to such a broad-based user community can only support further growth in quality facility usage.« less
  • The University of Maryland Reactor (UMR) is a 10-kw light water- moderated. graphite-reflected. open-topped tank reactor. Maximum unpenturbed thermal flux is 2.5 x l0/sup 11/ n/cm/sup 2/-sec. The experimental facilities consist of two beam tubes, one through tube, a thermal column, and a - sample- holding fuel element. The reactor and nuclear characteristics, the site, and building are described. The administration and operation of the reactor are outlined. The analysis of reactor hazards is presented. (W.D.M.)
  • A report on the location, design, and hazards analysis of the University of Florida training reactor has been submitted to the Atomic Energy Commission as a part of the University's application for a class 104 license and construction permit for a 10-kw training reactor. ThB reactor will be used primarily for the training and education of graduate students in nuclear science and engineering. The basic element of the reactor is a rectangular prism (5 ft x 5 ft x 4 ft) constructed of shield of concrete made partly of barytes and ordinary concrete and partly of concrete blocks. The reactormore » is housed in a cell having monolithic concrete walls and a precast, light-weight, concrete roof deck sealed with tarred felt and pitch with a slag covering. A control room and records office is located in one corner of the cell. A storage place for the fuel plates when not in use is provided in the floor near the reactor. The cooling system is integrated with the building structure. In addition to the design description, a detailed safety analysls is preseated. (L.T.W.)« less
  • This is a preliminary report on the location, conceptual design, and hazards analysis of the University nf Florida 10-kw Training Reactor. The reactor design was developed as a modification of the Argonaut type. (W.D.M.)