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Failure of latch mechanism for motion control of safety rods

Description: During safety rod tests in K-reactor prior to startup, one safety rod could not be lifted because the button'' broke off and became lodged in the mechanism. Examination of the failed latch assembly along with other assemblies from both K-Area and L-Area revealed several missing buttons as well as severely deformed jaw hanger extensions.'' We participated in the investigation of the damage by request of the Reactor Restart Section. Based on our study of the latch mechanism, the modifications to … more
Date: January 16, 1992
Creator: Yau, W. W. F. & Leader, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast Shutdown System tests in the Georgia Tech Research Reactor

Description: The Fast Shutdown System (FSS) is a new safety system design concept being considered for in installation in the Savannah River (SRS) production reactors. This system is expected to mitigate the consequences of a Design Basis Loss of Coolant Accident, and therefore allow higher operational power levels. A test of this system in the Georgia Tech Research Reactor is proposed to demonstrate the efficacy of this concept. Three tests will be conducted at full power (5MW) and one at low power (100kw)… more
Date: March 16, 1990
Creator: Wallace, J.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast Shutdown System tests in the Georgia Tech Research Reactor

Description: The Fast Shutdown System (FSS) is a new safety system design concept being considered for in installation in the Savannah River (SRS) production reactors. This system is expected to mitigate the consequences of a Design Basis Loss of Coolant Accident, and therefore allow higher operational power levels. A test of this system in the Georgia Tech Research Reactor is proposed to demonstrate the efficacy of this concept. Three tests will be conducted at full power (5MW) and one at low power (100kw)… more
Date: March 16, 1990
Creator: Wallace, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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K and N reactor capabilities

Description: This report contains data on the relative capabilities of the K and N plants to produce various isotopes. The data are ``direct and quantitative`` in cases where production plans for the various isotopes have been studied. For isotope studies not completed production capabilities are, of necessity, discussed from only a qualitative standpoint.
Date: August 16, 1963
Creator: Lang, L. W. & Dowis, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Flux distribution problems at C Reactor

Description: This report discusses an outbreak of ruptures in January and February, 1960, which motivated serious consideration of ail phases of reactor operation so that a combined efforts to reduce rupture potential might be made. Items investigated include mixer location, gas composition control, rod movement, rod configuration, tube power, and the axial flux profile of the reactor.
Date: March 16, 1960
Creator: Chitwood, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supplement C -- Production test IP-64-CE poison column displacement during reactor operation

Description: The objectives of this supplement are to test an improved prototypic slug column displacement winch and associated remote control equipment and to demonstrate the feasibility of exerting control over the front-to-rear neutron flux changes as an aid in controlling reactivity cycling. An array of poison displacement columns up to twelve in number is intended, each charge consisting of a center section of I and E natural uranium slugs with mint pieces on each end. Initially six such columns will b… more
Date: June 16, 1959
Creator: Hedges, J. W. & Carter, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Works monthly report, January 1951

Description: This is a progress report of the production reactors on the Hanford Reservation for the month of January 1951. This report takes each division (e.g. manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.
Date: February 16, 1951
Creator: Prout, G. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

KER-2 tube history

Description: Zirconium process tube No. 1986 was installed in KE Reactor tube channel No. 2864 on April 16, 1959. This report describes the history and the conditions to which it was exposed during its residence in the reactor. The tube was removed on May 31, 1963.
Date: August 16, 1963
Creator: Banister, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PT-IP-158-D, Supplement B: Irradiation of one swaged UO{sub 2} stainless steel clad fuel element in a KE front-to-rear test hole

Description: The objective of this supplement is to authorize a change in the panellit trip range from 25--75 psi to 5--95 psi. The test hole facility consists of two concentric aluminum tubes which extend from the front face to the rear face of the reactor. The ID of the inner tube is 2--7/8 inch. Water from one crossheader supplies the annulus, water from another crossheader supplies the inner tube. The three-foot-long, .570 inch OD fuel element is centered in a 40-inch long aluminum holder which has an I… more
Date: February 16, 1959
Creator: Marshall, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses -- Revision 1

Description: The isotopic composition of mixed-oxide fuel (fabricated with both uranium and plutonium isotopes) discharged from reactors is of interest to the Fissile Material Disposition Program. The validation of depletion codes used to predict isotopic compositions of MOX fuel, similar to studies concerning uranium-only fueled reactors, thus, is very important. The EEI-Westinghouse Plutonium Recycle Demonstration Program was conducted to examine the use of MOX fuel in the San Onofre PWR, Unit I, during c… more
Date: March 16, 2000
Creator: Hermann, O.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department Monthly Report: September 1961

Description: This document details activities of the irradiation processing department during the month of September, 1961. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and NPR Project.
Date: October 16, 1961
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pile level objectives

Description: At the 100{endash}300 Areas Steering Committee meeting of March 7, following a general discussion of pile level increases, the chairman pointed out the necessity for programming tentative level objectives as far in advance as possible so that the P and Service Divisions may proceed with the planning details incidental to making the necessary equipment changes. A committee consisting of Mr. Warren and Mr. McCullough was appointed to prepare an outline of pile level objectives and to determine th… more
Date: April 16, 1951
Creator: Windsheimer, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

TIBER engineering test reactor (ETR) startup scenarios

Description: A time-dependent Tokamak Systems Code (TTSC) has been developed and used to examine various inductively driven startup scenarios for the TIBER reactor. Radially averaged particle and energy balance equations are solved. In addition, time varying currents in the PF and OH coils are determined from MHD equilibrium and volt-seconds considerations. Less than 20 MW of auxiliary power deposited in the electrons is required to obtain steady-state operations. For this scenario, less than 10% of the tot… more
Date: October 16, 1987
Creator: Blackfield, D. T. & Perkins, L. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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