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Operating limits Hanford Production Reactors. Revision 2

Description: This report is applicable to the eight operating production reactors, B, C, D, DR, F, H, KE, and KW. It covers the following: operating parameter limitations; reactivity limitations; control and safety systems; reactor fuel loading; coolant requirements with irradiated fuel in reactor; reactor confinement; test facilities; code compliance; safety instrumentation and set points; and control criteria. Also discussed are administrative procedures for process control, training, audits and inspectio… more
Date: May 20, 1963
Creator: Owsley, G. F.
Partner: UNT Libraries Government Documents Department
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Effect of 6.6 pH process water on process tube and fuel element corrosion

Description: Reduction of the reactor process water pH from 6.9 to 6.6 at 100-B, D, DR, KF, and H currently is proposed in order to reduce the aluminum corrosion rate and the resultant outage time for water leaks, fuel ruptures, and process tube replacement. This document reviews the current knowledge of the effect of reducing the pH to 6.6 on aluminum corrosion. An estimate of the expected costs and benefits is included.
Date: May 20, 1963
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department
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Description of Reactor Operating Limits (ROL) and Reactor Master File (RMF) reports

Description: The detailed description includes flow measuring methods, flow rate calculations, operating pressure constants, crossheader number, header elevation corrections, and header pressures for the reactor record. The unit records include: tube number, header number, flow zone, trip dial readings, effective range, taps, corrosion index, rib type, rear fitting type, Panellit pressure, date, calculation methods, tube flow rate, tube class, load type, charge date, and header pressures. The reactor operat… more
Date: May 20, 1963
Creator: Wood, S. A.
Partner: UNT Libraries Government Documents Department
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Development status and incentives for the hot die sizing process

Description: The development status and incentives for the hot the sizing process for reactor production fuels is reviewed and updated and economic justification for the process for four different case studies presented. Based on whether the end bonding step can be eliminated, payout periods of 1.2 to 1.7 years can be realized if the present AlSi process (two-shift, five-day week) is converted to hot die sizing for all reactors. For K-Reactor operation only, Payouts of 1.5 to 2.2 years can be realized by co… more
Date: November 20, 1963
Creator: Blanton, W. A.
Partner: UNT Libraries Government Documents Department
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PITA IP-27-I, Part 1 increased coolant flow, H reactor

Description: The PITA`s (process improvement transition authorizations) present the specific requirements necessary to accomplish the outage work and to control the use of this increased flow capability. The procedures and methods to accomplish the programmed modifications are contained in the approve design changes or in supplemental procedures.
Date: December 20, 1963
Creator: Clinton, M. A. & Spicka, R. E.
Partner: UNT Libraries Government Documents Department
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Interim report on hot die sizing variables test

Description: Studies were initiated at Hanford in 1961 and 1962 toward the development of an alternate assembly process for the production of I&E fuel elements for the eight existing Hanford reactors. Of the processes considered, hot die sizing, a diffusion bonding process, offered the greatest incentives in terms of improved quality and potentially cheaper unit cost of fuel elements compared to the currently used AlSi braze process. This interim report presents the results of initial process variables test… more
Date: May 20, 1963
Creator: Strand, C. A.
Partner: UNT Libraries Government Documents Department
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Provisional process specifications for fabrication of KIT and KIIT target elements for K Reactor E-N load (PT-IP-561-C)

Description: It is necessary to modify existing I&E fuel element components to produce the requested target elements by early April 1963. Normally, a minimum of eighteen weeks is required to produce components of a new design. Therefore, the finished target elements will not be of the optimum designed dimensions. The proposed minor deviations have been approved by Reactor Engineering for the demonstration load. It is anticipated that only these test quantities will be fabricated to these dimensions. These p… more
Date: March 20, 1963
Creator: Padgett, E. V. Jr.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: November 1963

Description: This report for November 1963, from the Chemical Processing Department at HAPO discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing; and power and crafts operation.
Date: December 20, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Interim report 1, Production Test IP-442-A half-plant reduction in process water pH, 105-D

Description: A half-plant low pH test began at D Reactor on March 19, 1963. The purpose of the test was to provide quantitative data on the reduction in aluminium corrosion obtained by lowering reactor coolant pH from 7.0 to 6.6. The benefits of lower pH will be monitored by ex-reactor tube examinations) in-reactor wall thickness measurements, coupons, and visual examination pleas weight loss measurements of fuel elements. This report presents the results of the visual examination and weight loss measuremen… more
Date: September 20, 1963
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Provisional specifications for the hot die sizing process

Description: Hot die sizing is one of three solid state diffusion bonding (SSDB) processes that has been proposed as an alternate manufacturing process for fabricating HAPO metallic uranium, aluminum-clad fuel elements. This document establishes the provisional process specifications for the assembly of fuel elements by the hot die sizing process. These specifications were developed for the CDB2N model fuel element (CSN equivalent AlSi model) and do not necessarily apply to any other model.
Date: May 20, 1963
Creator: Burgess, C. A.; Stinger, J. T. & Greager, O. H.
Partner: UNT Libraries Government Documents Department
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Proposed graphite coring patterns for B, D, F, DR, and H Reactors

Description: Heat transfer calculations were performed with the aid of the IBM 7090 to determine whether or not feasible graphite channel coring patterns could be adopted at the five older Hanford Reactors. The purpose of front and rear process channel coring is to significantly reduce or eliminate net expansion of the fringe graphite by raising the operating temperature above the annealing temperature of 300{degree}C. The results of the study show that such coring patterns are possible. Also, it was found … more
Date: June 20, 1963
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Approximate Models for Distributed-Parameter Heat-Transfer Systems

Description: Summary: The use of dimensionless-parameter frequency response diagrams to determine accuracies of lumped-parameter approximations is demonstrated by two examples: calculation of the heat flux at the surface of a semi-infinite solid due to temperature fluctuations of an adjacent fluid; and the response of a counterflow heat exchanger to inlet fluid temperature perturbations. Dimensionless system parameters make it possible to use general-purpose plots to find the error in particular approxima… more
Date: August 20, 1963
Creator: Ball, S. J.
Partner: UNT Libraries Government Documents Department
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Deflection of an Aluminum Sheet Into a Depression in a Graphite Block

Description: The purpose of this test was to determine the amount of deflection which could occur into the graphite cavity with a .032" thick sheet of 2219-T31 aluminum alloy.
Date: April 20, 1963
Creator: Schreiber, J.J. & Skoff, R.
Partner: UNT Libraries Government Documents Department
open access

Models for Fission-Gas Release From Coated Fuel Particles

Description: Mathematical relations are presented for estimating the release fractions of gaseous fission products from coated fuel particles and fuel elements containing them. The relations are based on simplified models of the release process, with particular emphasis on the following mechanisms: recoil, diffusion from fuel, diffusion through particle coating, and diffusion through fuel element matrix. The characteristics of fission-gas release by these mechanisms, acting singly and in combination, are co… more
Date: June 20, 1963
Creator: Prados, J.W. & Scott, J.L.
Partner: UNT Libraries Government Documents Department
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Spert Project Quarterly Technical Report, January-March 1963

Description: Additional data from the 3.2-msec-period destructive test were analyzed. Recovery and cleanup operations in the Spert I area were completed. Each of the 270 highly enriched, aluminum-clad fuel plates in the core was found to have experienced melting to some degree. The available data on the nature of the pressure pulse and on the condition of the core fuel plates at the time of the pulse are consistent with the hypothesis that the observed destructive effects were produced by a self-propagating… more
Date: May 20, 1963
Creator: Schroeder, F. ed.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant. Butterfly Valve Cavitation Test

Description: Tests were made on butterfly vaives similar to those used in the discharge leg of each of the three external recirculation loops of the Pathfinder reactor in order to determine the critical values of a dimensionless cavitation number ( /occurred in pu ) used to specify the limits of operation for reactor valves, at incipient cavitation. The experimentally determined values of the cavitation number were used to determine the cavitation-free control range of the Pathfinder valves. The tests showe… more
Date: March 20, 1963
Creator: Grimm, N.P.
Partner: UNT Libraries Government Documents Department
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Catalytic Hydrocracking of High Boiler in Nuclear Reactor Coolant

Description: Selective hydrocracking of total coolant was found to be an efficient and economic method for reconstitution of high boiler in the coolant to usable product. Such a process could eliminate the expense of vacuum distillation and disposal of high boilers produced in a nuclear reactor power plant. The selective conversion was possible since polyphenyls were found to be more susceptible towards hydrocracking as the phenyl chain length increased. Both cobalt molybdate on alumina and nickel oxide on … more
Date: May 20, 1963
Creator: Gardner, L.E.
Partner: UNT Libraries Government Documents Department
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SNAP Aerospace Safety Program Quarterly Technical Progress Report, July- September 1962

Description: Statements are presented concerning project objectives, major accomplishments in FY 1962, progress during the report period, evaluation of effort to date, and next report period activities. The subject material covers reactor separation and fuel element ejection, reactor transient and excursion tests, reactor end-of-life shutdown devices, fission product release studies, critical configuration tests, mechanical and thermochemical effects, and fuel element burnup and fission products dispersal. … more
Date: March 20, 1963
Partner: UNT Libraries Government Documents Department
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A PRELIMINARY REPORT OF BERYLLIUM DAMAGE OBSERVED IN THE MTR REFLECTOR

Description: Evidence of bowing was observed in an MTR beryllium shim rod section during the Cycle 184 shutdown. Inspection and measurements of this and other selected beryllium lattice pieces confirmed this observation. Preliminary measurements were made along a vertical transverse between the north and south reflector walls with some bowing again noted. An inspection of the north wall revealed cracking and spalling of the beryllium sections, primarily in the vicinity of the HB-2 thimble. (auth)
Date: June 20, 1963
Creator: Dykes, J.W. & Ford, J.D.
Partner: UNT Libraries Government Documents Department
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