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in creator/contributor: "Nechodom, W. S."  
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Nuclear safety criteria for special test loads -- N-Reactor

Description: The initial fuel landing for the N-Reactor and the use of a specific alternative fuel element are described in a previous report. It is highly probable that it will also be desirable in the future to irradiate still other types of fuel elements in the reactor. If the test is of small scale, fever than five channels, or if these elements vary only slightly from the initial fuel load (or any other fuel type approved for large-scale use at some future date), the irradiation will be accomplished wi… more
Date: October 14, 1963
Creator: Nechodom, W. S. & Miller, N. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Semi-final report (report No. 3) E-N load conversion ratios

Description: Experimental data on plutonium yield and U{sup 235} burnout are now available on the E metal portion of three central zone striped E-N columns and one fringe blanket E column. These data and an overall E-N load conversion ratio based on experimental data are now reported.
Date: December 22, 1960
Creator: Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Speed-of-control limits, 105-DR

Description: The current operating conditions at 105-DR, because of the recent Ball 3X drop, dictate temporary lower speed-of-control limits. While is si still not expected that this reactor will be limited by the speed-of- control criterion, it is felt that the limit curves have been temporarily sufficiently reduced as to warrant publication of former limits. Limit curves as a function of weighted graphite temperature for the continuous and block discharge schemes are included in this document. The two sou… more
Date: August 1, 1961
Creator: Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical evaluation of E-N demonstration loading: (Interim report, production test IP-350-C)

Description: This report presents the technical observations and conclusions to date of the full-reactor demonstration E-N loading for the combined production of plutonium and tritium. A major incentive for such a loading is the increase in conversion ratio resulting from three factors: (1) A ``blacker`` lattice,, in which a combination of ``E`` metal fuel elements (uranium enriched to 0.95% U{sup 235}) and ``N`` metal target elements (enriched lithium-aluminum alloy) approximately matches the reactivity pr… more
Date: May 11, 1962
Creator: Carter, R. D.; Nechodom, W. S.; Shimer, R. D. & Fullmer, G. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical bases for C-pile overbore test

Description: The production gains and economic evaluation of overboring has been extensively treated. In this document, the justification for a trial attempt at overboring C-Reactor was given. The overboring test, covered by two production tests (one or overboring and one for fuel irradiation), requires the integration of efforts of Equipment Development, Process and Reactor Development, Process Technology, Manufacturing, and the Fuels Preparation Department. In view of this, it appears prudent to collect i… more
Date: November 3, 1960
Creator: Curtiss, D. H.; Clinton, M. A. & Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supplementary E-N load conversion ratio data

Description: The interim report included an analysis of those E-N case and blanket loading conversion ratio data which were available at that time, and an extrapolation of those data to expected, optimum, E-N operating conditions. Since issuance of the interim report further tritium yield data have become available from extraction of the tritium from the lithium-aluminum slugs irradiated in the second E-N core loading, and from the large batches of lithium-aluminum slugs irradiated as part of the blanket lo… more
Date: August 13, 1962
Creator: Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Expansion task force: Old reactors speed of control for no overbore cases

Description: The Criteria for Speed of Control must be met for all cases being considered in the Expansion Studies. These Criteria are dependent upon the ratio Volume of water/volume of uranium in the process channel, the reactor power level, and the rate at which the vertical rods are released and inserted into the reactor. For those cases wherein the graphite channel is overbored by 0.200 inch., the criteria can generally be met for the power levels under consideration since the ratio of Vw/Vu is maintain… more
Date: February 22, 1960
Creator: Gilbert, W. D.; Carlson, P. A. & Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interim report No. 2 E-N load conversion ratios

Description: Experimental data on tritium yield from lithium-aluminum pieces irradiated under PT-IP-255-A-9-FP have been reported previously. Experimental data on plutonium yield and U {sup 235} burnout in the E metal portion of one central zone striped E-N column are now available. These data are now reported. The combined data are compared to the experimental and theoretical values used in the economic analyses of the E-N loadings.
Date: November 4, 1960
Creator: Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Miscellaneous Pu{sup 240} concentration data for the C pile overbore study

Description: This report contains data on the following cases: Pu{sup 240} concentrations in base and overbored cases; values for Pu{sup 240} concentration at 800 MWD/T; data from sources as stated; probable plant-average Pu{sup 240} concentration for the last six months of 1960; average pile parameters--C Reactor; and Pu{sup 240} concentration vs. graphite temperature in the overbored fuel geometry.
Date: July 7, 1961
Creator: Nechodom, W. S. & Blyckert, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

E-N and blanket conversions from analysis of tubes irradiated at H

Description: A block-loading of striped columns and tubes simulating a blanket loading were analyzed for product (Pu, tritium, E-metal) after irradiation in IP-255-A-9-FP. Results are rationalized to full-pile values; pile conversion ratios and pile gains are given.
Date: February 10, 1961
Creator: Lang, L. W. & Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Physics considerations of old pile expansion study

Description: In view of the more-or-less eminent conversion of at least some of the older Hanford reactors to minimum process tubes it has been requested the feasibility and economics of increasing the process channel size by overboring be studied. This report is concerned with the feasibility from an operational physics standpoint of either raising reactor power levels with present aluminum process tubes and redesigned fuel elements raising reactor power levels with zirconium replacement tubes of current o… more
Date: December 1, 1959
Creator: Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production test IP-255-A-9-FP E-N demonstration test

Description: The objectives of the test described in this report are to evaluate the integrity of I & E MINT fuel elements canned by the ``C`` process to determine the conversion ratio of I & E geometry E-N ``striped loadings,`` and to provide a demonstration loading for a full reactor loading incorporating a ``striped`` center loading and a fringe ``blanket`` loading. This test will involve two portions a 26 tube block loading of I & E enriched uranium and MINT fuel elements arranged in a striped array, an… more
Date: May 8, 1959
Creator: Hall, R. E. & Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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C pile mark 1 overbore fuel element design

Description: It is necessary to provide the option of using either aluminum or zirconium tubes in the C pile 20-tube overbore test. A bumper-type fuel element has been designed to fit a fixed ribbed aluminum tube size; zirconium tube dimensions were then determined which will provide the same flow and pressure drop when the fuel element is changed from bumper type or self-supported without changing other fuel dimensions.
Date: October 6, 1960
Creator: Cahoon, R. D. & Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hazards review: N-Reactor 1.25% co-producer fuel element test

Description: The N-Reactor Hazard Summary Report examines the hazard from operating the N-Reactor with a uniform fuel loading enriched to 0.947% U{sup 235}. Incentives have been developed for reactor testing of a block of 49 tubes loaded with co-producer elements, i.e. elements capable of producing both weapons grade plutonium and tritium. The element utilizes an outer fuel tube enriched to 1.25% U{sup 235} with an inner target lithium-aluminum rod. Criteria have been developed to guide the evaluation of sa… more
Date: July 13, 1964
Creator: Miller, N. R. & Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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