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SOx-NOx-Rox Box{trademark} flue gas clean-up demonstration. Final report

Description: Babcock and Wilcox`s (B and W) SOx-NOx-Rox Box{trademark} process effectively removes SOx, NOx and particulate (Rox) from flue gas generated from coal-fired boilers in a single unit operation, a high temperature baghouse. The SNRB technology utilizes dry sorbent injection upstream of the baghouse for removal of SOx and ammonia injection upstream of a zeolitic selective catalytic reduction (SCR) catalyst incorporated in the baghouse to reduce NOx emissions. Because the SOx and NOx removal proces… more
Date: September 1995
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Engineering Development of Advanced Froth Flotation. Volume 2, Final Report

Description: This report is an account of findings related to the Engineering and Development of Advanced Froth Flotation project. The results from benchscale and proof-of-concept (POC) level testing are presented and the important results from this testing are used to refine a conceptual design and cost estimate for a 20 TPH Semi-Works Facility incorporating the final proposed technology.
Date: March 1995
Creator: Ferris, D. D.; Bencho, J. R. & Torak, E. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Studies: Final Report, Part 1

Description: This report presents a study investigating the possibility of designing a somewhat advanced power reactor using existing and proven technology insofar as possible. It covers a preliminary analysis of a 500 mw reactor.
Date: November 1955
Creator: Babcock & Wilcox Company. Atomic Energy Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor: Design of the MMSR Primary Shield

Description: The purpose of this report is to describe the shielding calculations and techniques used in sizing the MMSR primary shield, the results obtained, and the resulting shield thicknesses. The present report covers many of the items scheduled for presentation in the final MMSR shield design report to be issued in November of 1958. The primary shield in the MMSR consists of the reflector, thermal shields, pressure vessel wall, a 33" water annulus and a layer of lead shielding at the exterior of the… more
Date: April 1958
Creator: Smith, W. R. & Turner, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effects of Fuel Rod Fission Product Leakage on the Consolidated Edison Thorium Reactor Plant

Description: Experiments performed by WAPD and others have shown that with fuel in an oxide form, it is possible to continue to operate a nuclear plant with fuel rods that have developed defects with only a small increase in the radiation contamination problem
Date: June 1960
Creator: Montgomery, D. W.; Howard, J. O. & Dodd, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Lynchburg Test Reactor: Critical Experiment, Hazard Evaluation

Description: This report summarizes the hazards associated with the operation of the Lynchburg Test Reactor (LTR) critical experiments. The LTR critical experiment program is outlined and the design of the experiment is described. The experiments will provide basic data to check two-dimensional calculational methods and provide information needed in the design of the LTR.
Date: November 1959
Creator: Engelder, T. C. & Schutt, P. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Hot Exponential Experiment

Description: A series of exponential experiments were performed using Consolidated Edison Thorium Reactor oxide type fuel pins in a light water lattice. These experiments were performed in a new facility where measurements were made at temperatures up to 468 F. In addition, boric acid was added to the system in various concentrations. The main objective of these experiments was to obtain the change in material buckling for the system as operating conditions were changed from ambient temperature to high t… more
Date: June 1960
Creator: Clark, R. H.; Barrett, L. G. & Funderburg, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated Edision Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.
Date: July 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Lynchburg Test Reactor Summary Hazards Report

Description: The Babcock and Wilcox Company (B&W) proposes to construct and operate a Nuclear Test Reactor on the grounds of the Company's integrated nuclear facilities site, Mt. Athos, near Lynchburg, Virginia. This preliminary Summary Hazards Report present to the U.S. Atomic Energy Commission (AEC), Division of Licensing and Regulations, a description of the facility, the characteristics of the proposed site, and an evaluation of potential hazards to the area surrounding the site of operation.
Date: April 1960
Creator: Kulynych, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor: Reactor Vessel Internal Components Design

Description: The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods.
Date: July 1960
Creator: Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Control System Design

Description: The Consolidated Edison Thorium Reactor Control System has been designed to provide the operators with a reliable, safe and accurate means of controlling the plant. Manual and automatic positioning of control rods can be accomplished. The automatic plant controller has been designed to meet the design criteria under the representative CETR demanded load changes. Adaptability has been built into the plant controller by providing variable controller adjustments for variations in reactor charac… more
Date: August 1960
Creator: Carson, W. E.; Chubb, W. B.; Pickett, R. T. & Deddens, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Corrosion Product Activity Distribution Across the Chemical Process System in the Consolidated Edison Thorium Reactor Plant

Description: A study has been performed to determine the corrosion product and water impurity activities in the CETR Chemical Process System. A simplified mathematical model is used to represent the physical situation; however, the magnitude of the activities, taken at the end of the core life to represent the most conservative case, is considered sufficiently accurate for engineering calculations.
Date: August 1960
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: January 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. Initial contacts were made at National Reactor Testing Station and Hanford Works, design conditions for the proposed reactor vessels were reviewed, estimates of heating rates caused by radiation and the pluggage of fuel passages were computed, and design parameters for the LMFRE were established.
Date: January 1957
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: February 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. Included in this report was a study made regarding the possible use of beryllium as a core moderating material, calculations made regarding temperature distribution for various channel sizes and power levels, design parameters for initial operation of the LMFRE, and other work in the design and operation of the reactor.
Date: February 1957
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: March 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this monthly report work was reported on a completed study of the change in critical concentration and critical diameter with small changes in the physical and nuclear parameters of the reference design, reactor design #8 which incorporates an integral graphite core and core tank has been completed and distributed, and other work required for the design and construction of a LMFRE.
Date: March 1957
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: April 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this monthly report information on the reactor design No. 10 had been selected as the LMFRE preliminary reference design, various shielding designs have bee studied, various calculations on multiregion code and reactivity have been continued, and other related to the LMFRE
Date: April 1957
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor: Determination of the Purification Rate for Normal Operation

Description: The objective of this study is to establish a primary loop purification rate for normal operation to (1) maintain the activity created in the primary coolant water by corrosion products and other impurities (excluding fission products) at tolerable level and (2) minimize the crud deposition on the core heat-transfer surfaces.
Date: June 1958
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: May 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. This month's report includes the Research and Development program was completed, a study of shielding requirements indicated the necessity for test data, more information on studies regarding reactor startup, and other developments related to develop the LMFRE.
Date: May 1957
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: June 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. This month's report includes information on various factors entering into the estimate of reference design core which has been analyzed for sources of error, further design and testing procedures on the nuclear core, and other work focused on construction and design elements.
Date: June 1957
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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