This document summarizes activities of the Hanford Atomic Products Operation during 1955.

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This report provides details of Hanford Atomic Products Operation (HAPO) activities during 1956.

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The November 1956 monthly report for the Chemical Processing Department of Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed was the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operations. (MB)

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operations research, inventions, visits, and personnel status are discussed. This report is for November, 1956.

It is believed that the overall safety of reactor operation will be improved upon completion of projects CG-558, 600, even at the higher power levels anticipated. Installation of sub-critical monitoring instruments concurrent with these projects is a factor in this conclusion. Higher power levels will not of themselves increase the probability of a disaster initiating event; however, higher power levels will reduce the time available for remedial action and will increase the severity of the consequences of a disaster. Loss of process cooling water will precede or accompany a reactor disaster. A reactor containing a normal inventory of fission products will surely be destroyed, with release of some fission products, if cooling water is lost at operational power levels or within hours after shutting down the reactor from operational levels. A power excursion along with the water loss, unless causing a puff release of fission product, will only hasten the destruction. A power excursion not caused by loss of cooling water is possible, but appears to be of almost negligibly small probability. Such an excursion will not become disastrous unless a significant fraction of the cooling water is boiled out of the reactor. The scope of projects CG-558 and CG-600, …

The radiators designated Cambridge #1 and #2 were visually examined and modified before operation. The initial examination revealed poor quality braze joints at the top and bottom plates of Cambridge #1. However, the same plates of Cambridge #2 were adequately brazed. The copper core of the fins was exposed in many of the tube-to-fin joints on both radiators, indicating that the braze material had not covered the fin collars. Samples were removed from each radiator and examined for evidence of mass transfer. Samples were also removed from the air inlet and outlet banks of both radiators and examined for fin-to-tube integrity.

The electron spin paramagnetic resonance of dibenzene chromium cation h a s been observed. I t s c e n t e r is a t a valhe of g = 1.98. I t shows eleven hyperfine components s e p a r a t e d by 3.5 gauss. These a r e i n t e r p r e t e d to b e eleven of the thirteen components expected to r e s u l t f r o m the interaction of the twelve equivalent protons with the unpaired electron.

This document details activities of the irradiation processing department during the month of November 1956. 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; employee relations operation; and financial operation.

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This paper presents a calculation of transient events in the Hanford piles due to the build up of fission product nuclides with a very large neutron absorption cross-section. In particular it was found after operation of the first major pile that Xe{sup 135} was a short lived isotope which built up in the pile, and which possessed a very large cross-section. The dynamics in number density of this isotope has a major impact on the reactivity behavior of the piles, and in particular on the start-up behavior following transient shut-downs.

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This document presents monthly progress at the Savannah River Plant in the 100, 200, 300, and 400 Areas. In the 100 Area (reactors), the power ascension program, the productivity improvement program and general progress is given. Tritium processing, 200-F increased capacity, and waste disposal are reported for the solvent extraction plants in the 200 Area. The increased productivity program is reported for the 300 Area. Dana plant activities and 400-D progress are reported in the 400 area report (heavy water).

This manual contains the Radiation Control Standards'' and Radiation Control Procedures'' at Hanford Operations which have been established to provide the necessary control radiation exposures within Irradiation Processing Department. Provision is also made for including, in the form of Bulletins'', other radiological information of general interest to IPD personnel. The purpose of the standards is to establish firm radiological limits within which the Irradiation Processing Department will operate, and to outline our radiation control program in sufficient detail to insure uniform and consistent application throughout all IPD facilities. Radiation Control Procedures are intended to prescribe the best method of accomplishing an objective within the limitations of the Radiation Control Standards. A procedure may be changed at any time provided the suggested changes is generally agreeable to management involved, and is consistent with department policies and the Radiation Control Standards.

The purpose of this report is to present the derivation of equations useful as a guide for prediction of the critical flow point in orifice assemblies.