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1B HEAT EXCHANGER LEAK TEST. CORE I, SEED 1. Test Results

Description: Descriptions are given of various procedures used in determining leaks in the tubes of the 1B heat exchanger. Air pressurization tests determined leakage and leak rate of nine tubes. The leak-location-detector-probe method was found promising for locating defects along the length of the tube. Results of the probalog, dye-penetrant, and ultrasonic tests proved inconclusive in determining leak locations. (B.O.G.)
Date: February 24, 1961
Item Type: Refine your search to only Report
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Aerosol research at Hanford and engineering applications to production reactors

Description: When the construction of the confinement facilities for Hanford production reactors is completed, the potential for contaminating the environment with accidentally released fission products will be greatly reduced. This was demonstrated already when rupture debris burned in the rear face area of one of the reactors in which the fog spray was installed and ready for service. The fog spray effectively prevented the spread of contamination to the ventilation equipment downstream of the rear face e… more
Date: October 24, 1960
Creator: Linderoth, C. E.; Heacock, H. W. & Schwendiman, L. C.
Item Type: Refine your search to only Article
open access

Alpha correlation

Description: This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.
Date: March 24, 1960
Creator: Cremer, B. R.
Item Type: Refine your search to only Report
open access

An Analysis of the Inherent Stability of the EOCR

Description: The inherent stability of the EOCR at full power, exclusive of the heat exchanger, is investigated. Space and time dependent differential equations and transfer functions for the nuclear and thermal processes occurring in the reactor core and vessel are derived. Reactor stability is analyzed by application of the Nyquist stability criterion. The results show that the EOCR has an extremely large margin of inherent stability. (auth)
Date: August 24, 1962
Creator: Gossmann, S.R.
Item Type: Refine your search to only Report
open access

Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968

Description: Annual report with the objectives of evaluating, producing, and maintaining an up-to-date set of basic nuclear data; producing and evaluating multigroup constants; and improving of present day methods of neutronic calculations as related to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
Date: May 24, 1969
Item Type: Refine your search to only Report
open access

Artificial cooling of the Columbia River by dam regulation 1959

Description: An increase in the flow of water from the lower depths of the Grand Coulee Reservoir was used to lower the river temperature at Hanford Atomic Products Operation (HAPO). A net average daily reduction of over 1 C resulted. The average for one day varied from 1.7 to 0.2 C. Before the dam control period, the Bonneville Power Administration transferred load from Grand Coulee Dam to other dams in order to conserve cold water. The authors calculate that there was more value to HAPO from this transfer… more
Date: June 24, 1960
Creator: Kramer, H. A.
Item Type: Refine your search to only Report
open access

Atomic Energy Levels in Crystals

Description: Report discussing discrete energy levels observed within certain crystals which are due to perturbations of energy levels of the free ion by an electrostatic field arising from the crystal lattice. The analytic procedures for determining the field from the charge configuration are given, and the resulting fields are classified according to their symmetry. After a general survey of group-theoretical ideas, the applicable groups are analyzed in detail, and characters appropriate for both integral… more
Date: February 24, 1961
Creator: Prather, John L.
Item Type: Refine your search to only Report
open access

Boron Carbide-Graphite Nuclear Control-Rod Material: Preparation, Thermal Stability, and Irradiation Evaluation

Description: Boron carbide-graphite nuclear control-rod materials containing up to 45 wt% B were prepared by hot-pressing techniques. The densities of these compacts decreased with increasing B content. Compact strengths, however, were noticeably increased with B content of 20 wt%, suggesting that the B acts as a sintering aid. Thermal stability was evaluated by annealing compacts under a variety of temperature and atmospheric conditions. The upper limit of the ioss of 13 was 5% to 10%~ in 200 hr at 2000 de… more
Date: April 24, 1962
Creator: Goeddel, W. V.; Lonsdale, H. K. & Meyer, R. A.
Item Type: Refine your search to only Report
open access

C Reactor overbore test facility review

Description: In 1961, large-size, smooth-bore, Zircaloy process tubes were installed in C-Reactor graphite channels that had been enlarged to 2.275 inches. These tubes were installed to provide a test and demonstration facility for the concept of overboring as a means of securing significant improvement in the production capability of the reactors, After two years of facility operation, it is now appropriate to consider the extent to which original objectives have been achieved, to re-examine the original o… more
Date: April 24, 1964
Creator: Carlson, P. A. & Nilson, R.
Item Type: Refine your search to only Report
open access

Calculation of Explosion-Produced Craters

Description: In this study, a physical-numerical model is used to investigate processes important for cratering, or excavation, physics for high-explosive sources in desert alluvium. High explosives do not vaporize much of the geological environment surrounding the initial cavity containing the explosive. Thus, a relatively simple, and in some cases a well-known, equation of state exists for the high-explosive cavity gas for pressure greater than 1 atmosphere. However, nuclear explosives are known to vapori… more
Date: April 24, 1964
Creator: Knox, Joseph B. & Terhune, R. W. (Robert William)
Item Type: Refine your search to only Report
open access

Calculation Of The Shock Wave From An Underground Nuclear Explosion In Granite

Description: In any underground nuclear explosion, the shock front that propagates from the shot point carries with it energy from the explosion, and distributes this energy by doing work on the surrounding material. In the process, the material undergoes changes in both its physical and mechanical states. If enough energy is deposited in the material, it will vaporize or melt thus changing its physical state, or cause it to crush or crack. During the past few years, special computer codes have been develop… more
Date: April 24, 1964
Creator: Butkovich, Theodore R.
Item Type: Refine your search to only Report
open access

Carbon-14 extraction from reactor gas, Progress report. Production test authorization {number_sign}124

Description: Carbon-14 is by far the most popular of the labeled isotopes because of its adaptability to so many chemical compounds and its relatively harmless characteristic beta radiation. Because the inert gas atmosphere contains up to 30% nitrogen, carbon-14 is generated within the K Reactors by the conversion of nitrogen-14, and if not immediately oxidized, carbon-14 may remain in the reactor core for some time. It is eventually oxidized and escapes when the outward gas leakage from the reactor is vent… more
Date: January 24, 1969
Creator: Cooke, J. P.
Item Type: Refine your search to only Report
open access

A CDC-1604 SUBROUTINE PACKAGE FOR MAKING LINEAR, LOGARITHMIC AND SEMILOGARITHMIC GRAPHS USING THE CALCOMP PLOTTER

Description: A CDC-1604 subroutine package was written to facilitate the plotting of curves and points on linear, logarithmic, and semilogarithmic graphs using the CALCOMP plotter. The subroutines accomplish the necessary computations and prepare a magnetic tape for use by the plotter. (auth)
Date: June 24, 1963
Creator: Trubey, D.K. & Emmett, M.B.
Item Type: Refine your search to only Report
open access

Characteristics Of Radioactivity Produced By Nuclear Explosives

Description: The production of energy by nuclear reactions results in the production of radioactive nuclei. Therefore, in considering the possible utilization of nuclear explosives for peaceful purposes it is necessary to be able to predict the expected activities, their amounts, and dispositions. The amounts and kinds of radioactivities produced by detonation of a nuclear explosive are dependent upon the specific design of the explosive. The behavior and ultimate fate of the activities produced by the expl… more
Date: April 24, 1964
Creator: Miskel, John A.
Item Type: Refine your search to only Report
open access

Chemical Processing Technology Quarterly Progress Report, April-June 1962

Description: Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in determination of dissolution rates over a wide range of conditions. The addition of oxidants to 4.8M hydrofluoric acid used for the continuous dissolution of 3% uranium-Zircaloy- 2 fuel decreased the amount of uranium-containing residue in the dissolver at the expense of a decreased dissolution rate.… more
Date: September 24, 1962
Creator: Bower, J. R.
Item Type: Refine your search to only Report
open access

Clean Area Assembly

Description: To assure that the NEERVA reactor will function reliably during its test program, cleanliness must be controlled at each stage. These stages include design, manufacture, assembly, shipping, and test. The assembly stage is that phase which this handbook is concerned.
Date: June 24, 1964
Creator: King, T.L.
Item Type: Refine your search to only Report
open access

Comment issue N-Reactor startup physics test program test procedures -- approach to critical and minimum critical size

Description: This document describes the detailed test procedures to be used during the initial phases of the physics test program--the approach to critical and minimum critical size tests. During these initial phases, several physics characteristics of the reactor will be evaluated in addition to determination of the critical loading. Overall flux distributions will be determined in the critical pile and used to evaluate the lattice buckling characteristics. Theoretical calculations normalized to experimen… more
Date: June 24, 1963
Creator: Hagan, J. W.
Item Type: Refine your search to only Report
open access

COMPARISON OF FEDAL MONITOR READINGS WITH RADIOCHEMICAL SAMPLE DATA. CORE I, SEED 1. Test Results T-641305

Description: Tests were conducted to compare the specific isotopic fission product activities with those of delayed neutron emitters which are monitored by the FEDAL System, and to obtain irformation on the source of activity observed in the PWR coolant. The monitors detected definite activity bursts of delayed neutrons during load increases, which indicated a rupture of the core blanket element. A radiochemical analysis of the coolant data did not show any unusual activity bursts, thus indicating a fuel el… more
Date: October 24, 1960
Item Type: Refine your search to only Report
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