This document defines the user`s process and functional requirements which shall be used as the basis for the preparation of the design for Project CGI-905, Interim Modifications for Improved Coolant Backup 100-B, C, D, DR, F, and H Reactors. The objective in making these modifications is to provide improved reliability and adequacy in the last ditch reactor cooling systems for current and short-range forecast conditions. Performance requirements for the last ditch cooling system are based on the reactor cooling system criteria set forth in Document HW-66929. These performance criteria require that the last ditch cooling system be independent of both the primary and secondary cooling system including piping to the reactor manifold, and that it must be capable of providing shutdown flow indefinitely, assuming instantaneous loss of power to the primary system and concurrent failure of the secondary system to provide its rated flow.

The process criteria proposed use of the existing organic wash column, 10, as a stripping column for the neptunium accumulation and isolation cycles. It is now proposed to employ a new processing concept which will permit the use of the scrub section of the neptunium extraction column, 1S, for neptunium stripping thereby obviating the use of the 10 Column. This proposed new scheme will provide increased neptunium stripping efficiency and greater processing flexibility for the 1S Column. The revision will require four new jumpers, but will permit the deletion of eight jumpers required for the original proposal. This document discusses the technical bases and incentives for the proposed change and presents revised flow diagrams and jumper routings.

The objective of this production test is to compare the irradiation behavior of N Reactor inner fuel tubes (NIE1 elements) having negligible warp after beta heat treatment to the behavior of NIE1 elements with extensive warp after beta heat treatment which were straightened and beta heat treated a second time. The information from this test will be used in the development of a program to evaluate the irradiation behavior of NIE1 elements in various conditions of pre-irradiation warp and straightening.

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Purpose of this test was to determine the adequacy of the export system for supplying flow to a dual reactor area under simulated emergency conditions.

Twenty columns of OIIIN-B fuel elements, ten with bumper rails of the present design and ten with elliptical bumper rails, will be charged into D Reactor in pairs, i.e., a column of fuel elements with one rail design will be charged adjacent to a column containing the other bumper rail design. Performance of the elliptical bumper rail will be based on relative visual appearance and measured weight loss. The twenty columns of weight and measured fuel elements required for this test may also be used to fulfill the fuel requirements for required for this test may also be used to fulfill the fuel requirements for PT-IP-442-A.

Neutron activation analysis provides the extremely high sensitivity necessary for the measurement of many trace elements. Activation techniques are presently being used to measure the concentrations of various undesirable parent isotopes in reactor process tubing, slug jackets and their corrosion film, and in process vater and vater treatment chemicals. The interpretation of results from activation analysis are sometimes complicated by the fact that a given radioisotope may be produced by fission neutrons (threshold reactions) from other elements as well as by the more common thermal neutron (n,{gamma}) reactions. Shielding the sample with cadmium prior to irradiation or irradiating in the graphite reflector will minimize the contributions from thermal or fission neutrons, respectively. The purpose of this study has been to measure the ratios and magnitudes of the thermal and fission fluxes in process tubing and to compare these with values at locations where neutron activations can be performed. Also, it was of interest to measure the ratios and magnitudes of the thermal and fission fluxes from a point in the lattice to a point well into the graphite reflector, and to determine if the fission neutron spectrum as measured by two threshold reactions, changes appreciably over this region. These data …

Results of the final dynamic experiments with the ironremoval process model using Fe/sup 59/ indicated that the intrinsic-radiotracer method is rapid, accurate, and suitable for continuous readout. Results from both static and dynamic experiments on the use of Mn/sup 54/ to aid in removing manganese from process water indicated that intrinsic radiotracers can be used to help remove low-concentration critical impurities. One phase of the hazards evaluation was concerned with the ingestion of radiotracer residues which might arise from corrosion of radiotracer-containing steel products. It was concluded that no hazard exists from this source. Another part of the hazards study was concerned with the technical hazards to sensitive industries which might use steel containing radiotracer residues. This area is the most sensitive one encountered in the study. The study of the mechanism of formation of free radicals in polymeric materials was continued. Emphasis was placed on examination of the effect of structural factors on the efficiency of free-radical site formation, especially in acrylate polymers. An initial investigation of the effect of polymer tacticity was completed using polypropylene. The influence of molecular mobility on site formation in polymethylacrylate was established. Measurements of the volatile products from irradiation of the polymers was …