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At 10:59 AM (PST), Saturday, April 7, 1962 a criticality accident occurred in a plutonium waste chemical recovery facility at the Hanford Atomic Products Operation, operated for the Atomic Energy Commission by the General Electric Company. Four men were hospitalized but were released after medical observation and after estimates of the radiation doses received were available. This report describes the dosimetry investigation that was made following the accident. This investigation was facilitated by the fact that all employees affected had personnel dosimeters in their possession when the incident occurred. The interpretation of the data supplied by these dosimeters was supplemented by information gathered by techniques that were developed in connection with other accidents. Below, the available information is first presented and then applied in a discussion of the dosimetry of the people involved in the accident.

This report summarizes the results obtained in the experimental measurement of the reactor heat extracted by the coolant during two different scrams of the DR Reactor. These tests were conducted with the reactor flow carefully controlled to establish different reactor coolant temperatures following the scram. During normal reactor scrams, which have been used in the past to measure the reactor heat output, a high coolant flow was maintained. Consequently, the coolant outlet temperature dropped very quickly from an operating value of 90 to 95 C down to 20 to 30 C following the scram. Under emergency conditions, however, with only the last ditch emergency flow available, the coolant outlet temperature could remain as high as 80 to 90 C. This condition could prevail because of the small amount of last ditch flow available, and could last for 5 to as long as 70 minutes after the reactor scram.

The interests of several departments at Hanford are involved in the planning, execution and evaluation of the results of the KER loop testing effort in support of the NPR fuel program. The varied interests and activities of the participating groups must be well-integrated if effective use of our limited testing capability is to be made. The purpose of this report is to help achieve this integration by summarizing the current thinking on the goals of the NPR fuel testing program and by presenting the current loop schedule.

The steadily increasing plutonium production rates in the 234-5 Building has resulted in a large increase in the number of PR cans that are now being handled in the building. This has resulted in the available receiving and storage places for PR cans being taxed beyond their full capacity thereby necessitating the storage of PR cans within the building corridors. Accordingly, the ten-year business plan for the 234-5 Building, as documented in HW-65000, included a program for providing new receiving and storage facilities to alleviate this problem. The purpose of this document is to present a complete process engineering design on the combined receiving, storing, and blending facility. This document will provide the basis for the preparation of all subsequent Title 1 and Title 2 designs of this combined facility which has been given the title of Metal Control Facility.

A computer program is being developed for the solution of general system flow problems. As a complement to this program, a summary of the process system has been prepared. This assembles information from a number of different reports, drawings and technical notebooks into one place for easy use and reference. It is expected that the information contained in this report will be of use in safety and design studies of these process systems. This report presents current values of the reactor flow characteristics and the primary pumping system characteristics. It also presents the process piping system and the basis for a computing program for calculating system pressure drops.

As TORY II-C is presently designed, a nuclear excursion would occur if the core were flooded with water. This is true even if all of the existing control rods were fully inserted. Indeed ANGIE calculations indicate that the reactor would be about 30% super-critical in such a case. There are several methods by which the core may be forced sub- critical under these extreme conditions. We will here consider only the method of introducing, directly into the core, a material which strongly absorbs neutrons. It must be possible to remove this excess `poison` prior to, or during the boost phase. Since the computer codes can be trusted to only approximately 3%, we will, for safety, insist on 40% negative reactivity to be introduced by the excess poison.

This memo is distributed to acquaint personnel with (a) the status of the various 410 areas, (b) time and personnel required to do optic experiments in the ``Dog`` area, and (c) status of the timing and firing system and conditions of cables from Able to Dog.

This memorandum outlines some of the problems and requirements that appear to go with a submarine-based nuclear ramjet startup.

This paper presents thrust calculations for low altitude trajectories for a Tory II-C type propulsion reactor.

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This report provides a summary of the Nuclear Effects Group Program for fiscal year 1963. Efforts in space physics and instrumentation are detailed for the space exploration effort. Pinex type experiments are proposed, as are Phonex, Nuclear Emulsion Research and Low Energy X-Rays Measurements projects.

During the course of the Christmas Island portion of Operation Dominic, a fairly simple, inexpensive method of making a rapid fireball yield determination was developed. In order to check the zero time alignment of the skysweeper antiaircraft mount on the burst point at zero time as provided by the Sandia 584 radar system, a pinhole camera camera was installed on the mount. This was helpful in determining whether or not the photographic and photoelectric diagnostic systems were observing the appropriate volume of air excited by prompt gamma and neutron radiation. After viewing the initial circular image on the Nambe event, it was decided that an attempt at a prompt fireball yield number would be made. Ad hoc scaling laws were used for the duration of the operation and the instant fireball yield number was included in several TWXs of early shot data. This report provides calculations, graphs, and illustrations which show that with the data now in hand, there is a simple method of determining a yield number to generally better than 10 percent. This number can be available within minutes after the detonation.

In a previous Naval Application memorandum, a discussion was given of what happens to the power level of a reactor when an instantaneous, very large neutron source is introduced. The motivation for the problem arises from the question of what happens when a nuclear bomb is detonated near a reactor powered missile. This present memorandum looks at the same problem as that which is discussed in the previous memorandum but in slightly more detail. The results obtained are essentially the same as those of the previous memorandum with somewhat more attention given to the nature of the assumptions made. The kinetics model used is the space-time separable, one delayed group model. Space-time separability is almost certainly a poor assumption in this case. When a very large neutron wavefront impinges on a reactor, the subsequent short time behavior can hardly be that predicted by this simple model. One would expect very large local power densities in one part of the core before another part would see anything unusual. The other assumption, one delayed group, is not necessary but makes the mathematics simpler and in view of the first assumption is probably quite acceptable. In spite of these simplifications the model gives …

This memorandum provides an discussion as to the possible application of nuclear ramjet propulsion in a submarine-based missile system. Questions are raised as to modifications required, compatibility with present submarine launch facilities, and missile and booster volume.

This memorandum outlines the area of interest in connection with the SSBN launch application, on modification of the Tory II-C control rod system; and suggest a plan of development of information. Because of the very limited space for overall missile length, little room is available for control rod motion upstream from the core. Shortening the rod stroke, and the total length occupied by control rod mechanism., becomes very desirable. Changes in the actuator and linkage mechanism will clearly help, and should be investigated. However, this is concerned only with neutronic aspects.

This memorandum was provided as a response for information concerning sensitivities of detectors that might be used during the boost phase.

This memorandum describes studies undertaken to investigate the properties of Tory II-C with the aims of reducing weight and size and in increasing performance. Space and weight limitations aboard existing sea-going launch vehicles required this general parameter study which utilizes a bare, cylindrical reactor having the same materials as Tory II-C.

This memorandum discusses study areas and items that will require attention for the naval studies of the utilization of nuclear propulsion in a submarine-based missile system.

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Reactor startup of a submarine based missile must be accomplished during boost., so that at burnout the reactor maximum wall temperature is at or near the design value. Because cooling air must be supplied during this period, there exists the possibility of obtaining some thrust to augment the booster. To find how much reactor thrust might be available, a representative high altitude boost trajectory was selected. This is shown together with an estimated pressure recovery curve for the inlet. It has been assumed that by some appropriate means the flow rate passed by the inlet exactly matches that demanded by the reactor and nozzle. Hot day conditions are assumed. The missile power plant was the Tory II-C reactor with its design point-optimized nozzle throat area of 750 square inches. Nozzle expansion is complete. The reactor maximum wall temperature was assumed to be constant at design (2500 degrees F) from time zero. Thus the thrust computed at any time is the maximum possible within the reactor design temperature limitation, and provides a guide to a desirable startup time. Available thrust and reactor exit conditions were obtained with the digital codes Dash N and Nomac.

This report provides a compilation of Hydrogen compounds of low atomic weight. Compounds known and reported in literature are given. Cations and anions of high Hydrogen content and/or low Z are provided as are molecules which form Lewis salts. Finally, unknown compounds for which synthesis seems probable are given.

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From time to time, in discussion of possible naval-based nuclear ramjet missile systems, a question arises concerning whether or not a particular reactor would or would fall within the `Tory II-C Technology`. Such a question is meaningless unless a definition is furnished. This report provides such a definition.