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Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices

Description: Abstract: A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt % enriched, uranium metal, hollow cylinder, fuel elements, in AGOT graphite moderator.
Date: June 30, 1963
Creator: Campbell, R. W.; Doyas, R. J.; Field, H. C.; Guderjahn, C. A.; Guenther, R. L.; Hausknecht, D. F. et al.
Partner: UNT Libraries Government Documents Department

Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

Description: Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.
Date: August 1, 1960
Creator: Reardon, W. A.; Clayton, E. D.; Brown, C. L.; Masterson, R. H.; Powell, T. J.; Richey, C. R. et al.
Partner: UNT Libraries Government Documents Department

Criticality Survey of Hydroxides as Coolant Moderators for Aircraft Nuclear Reactors

Description: Memorandum presenting a screening of various hydroxides for use in nuclear reactors as possible coolant moderators for operation at temperatures of about 1500 degrees Fahrenheit. The hydroxides that appear stable at a pressure of about 1 atmosphere are those of sodium, potassium, rubidium, lithium, barium, and strontium. Results regarding the core uranium investments and reflector savings are provided.
Date: October 27, 1953
Creator: Bogart, Donald & Soffer, Leonard
Partner: UNT Libraries Government Documents Department

Criticality studies of interacting cylindrical systems

Description: From introduction: "As a part of this program, this report presents the results of a study of an interacting system in which the conditions for criticality are given in terms of the concentration of fissionable material and the geometry of the system."
Date: October 29, 1954
Creator: Miraldi, F. D.; Farquhar, J., III & Perry, P. I.
Partner: UNT Libraries Government Documents Department

First Responders and Criticality Accidents

Description: Nuclear criticality accident descriptions typically include, but do not focus on, information useful to first responders. We studied these accidents, noting characteristics to help (1) first responders prepare for such an event and (2) emergency drill planners develop appropriate simulations for training. We also provide recommendations to help people prepare for such events in the future.
Date: November 1, 2005
Creator: Putman, Valerie L. & Minnema, Douglas M.
Partner: UNT Libraries Government Documents Department

CSER 97-001 Criticality safety limits for PFP 26-inch vacuum lineremoval

Description: As part of the plutonium stabilization operations in the 234-5Z Building, several runs of 26-inch (26 inches of Hg) process vacuum header, along with associated smaller piping is to be cut into sections and disposed of. This criticality safety evaluation report (CSER) requested by Nirider (1996) addresses the removal of several hundred feet of abandoned 3 and 4 inch nominal diameter vacuum header and associated smaller diameter piping runs located in the duct level of the 234-5Z Building in rooms 262, 263, and 264 as shown in the two attached drawings.
Date: February 14, 1997
Creator: Himes, D. A.
Partner: UNT Libraries Government Documents Department

Calculation notes that support accident scenario and consequence determination of a waste tank criticality

Description: The purpose of this calculation note is to provide the basis forcriticality consequences for the Tank Farm Safety Analysis Report(FSAR). Criticality scenario is developed and details and description of the analysis methods are provided.
Date: August 2, 1996
Creator: Crowe, R.D., Westinghouse Hanford
Partner: UNT Libraries Government Documents Department

Drain Holes for Criticality Safety Control Guidance for the Analyst

Description: Drain and overflow holes are integral to the nuclear criticality safety basis of many processes and provide different functions in achieving their safety goal. In most cases, unverified engineering judgement was used to conclude that the holes were adequate to accomplish their mission. Such judgement may adequately serve some configurations but is inadequate in other applications. It was determined that the exact function of every hole for both normal and upset process conditions must be understood and clearly documented. Y-12 has embarked on an effort to document engineering analyses of drain and overflow holes. This effort is essential to demonstrating that the holes are capable performing their intended safety function. The Y-12 EUO approach is based on criticality safety function and engineering analysis. The main components of the policies regarding drain holes are: C The criticality safety requirements are written in terms of function (e.g., depth in pan filter must always be less than 5 cm). C Engineering justifications are being written to show existing drains meet required function. Sometimes, detailed analysis of inflows and outflows is required. In some other cases, physical functional tests are performed. C Drains are documented on controlled drawings to ensure configuration control. A program of periodic inspections (usually annual) is in place for each required drain.
Date: November 30, 1998
Creator: LeTellier, m.s. & Smallwood, d.j.
Partner: UNT Libraries Government Documents Department

Criticality safety evaluation - an endusers's perspective

Description: This paper presents criticality safety evaluations from an enduser's perspective. Overall issues related to a criticality safety evaluation in an operations support setting are discussed. A work flow process is presented which shows the key steps in conducting an effective criticality evaluation. Finally, a few suggestions are given to assist newcomers to this field.
Date: May 6, 1999
Creator: Huang, S T
Partner: UNT Libraries Government Documents Department

Calculated Reactivity of Uranyl-Fluoride - Water Criticality Experiments

Description: Memorandum presenting a modified group method used to calculate the reactivity of the uranyl-fluoride-water experimental critical assemblies which are part of the Oak Ridge critical mass studies. The method relates the experimental slowing-down length for water to that in fluoride solutions and includes the effects of epithermal absorption and fission.
Date: March 30, 1956
Creator: Bogart, Donald & Soffer, Leonard
Partner: UNT Libraries Government Documents Department