This report addresses the Organized Crime Task Force and a summary of the basic report.

This report address the conscientious objection to war.

This report consists of selected list of references.

The concept of reactor effluent disposal to ground in infiltration trenches was proposed by Nelson and Alkire in 1963. At that time the available data indicated that radionuclide infiltration rates were probably adequate for trench disposal and that decontamination factors of 10 to 100 should be obtainable. Field tests at 100-F Area 1965 and 100-D Area 1967 have indicated that the infiltration rates are adequate and DF`s of from 2.5 for {sup 51}Cr to 7276 for {sup 65}Zn were obtained during the 100-D test. The purpose of this report is to present the results and interpretations of data from studies conducted over a reactor coolant effluent disposal test site. Data presented in this report were collected over the 100-C Area test in which a significant percentage of the reactor coolant effluent was disposed to an existing trench for a five-month period. Results of infrared thermal surveys and ground water temperature and potential measurements collected during this test are presented.

C Reactor was shutdown over a 20 minute period at 2058 hours on 10-27-67. The reactor was shutdown because of an excessive Panellit pressure increase on tube 2562. Subsequent examinations revealed that a fuel element rupture had occurred in process tube 2562, and the element was stuck within the process tube. The maximum force required to remove the rupture was 28,000 pounds, thus exceeding the force limit of 12,000 pounds specified by Process Standards. Then applying the higher-than-normal forces for stuck charge or tube removal, it is necessary to consult Process Guide HW-56000 on ``Stuck Charge and Tube Removal Forces -- C Reactor.`` Subsequent to the stuck slug and tube removal it is then important to evaluate the adequacy of the Process Guide. The purpose of this report is to present some of the data, action taken, and development concerning this particular fuel failure.

At 0308 on January 10, 1966, both B and C Reactors ``scrammed`` due to an electrical fault on Line C2-L8 caused by a raccoon coming in contact with the 13-8 KV line on top of transformer No. 2 at 182-B Building. Line C2-L8 relayed out at the 151-B Building. Details of the occurrence at 151-B are covered in the attachment. C-Reactor scrammed due to reduced voltage on the pressure monitor system. The reduction in voltage caused the auxiliary relays of the pressure monitor ground detector to open, de-energizing the end result relays PSR and PSRA. The safety circuit trip identification system displayed ``Pressure Monitor`` and ``Ground Detector.`` B-Reactor scrammed by a power failure signal from 190-B Building. The power failure relays for pump numbers 1 and 3 opened due to these pumps contributing power to the fault. The power failure relays at 190-B remained open long enough for the end result relays PF and PFA to open. Since these relays are timed delayed, 0.26 seconds, the power failure relays must have remained open at least that long. At the 190-B Building the steam turbines started due to the power failure relays for pump numbers 1 and 3 opening. The main …

This report details reactor incidents dating from February 26, 1959 through December 3, 1968.

This report details Hanford Reactors` incidents from January 24, 1961 through September 28, 1967.

This report documents reactor incidents from October 23, 1954 to September 19, 1964.

This report includes three separate reactor incident reports. The first incident report covers a series of Panellit scrams on the KE reactor that occurred on 10-17-67 and 10-18-67. Cause of these scrams was determined to be plugging on crossheader screens. The second incident report covers the KE reactor shutdown on Nov. 27, 1962, caused by upstream plugging in tube 0570. The third incident report covers the scram of reactor F on 7-27-61, due to a Panellit low trip on 3063. The 3063 tube had a leak.

A ceramic-to-metal seal was developed capable of operation up to 1200 deg C in a cesium environment. A new metallizing technique based on a promising tungsten--yttria system reported by LASL, was studied. Effects of mixture age, delay time between metallizing and brazing, and high-temperature outgassing were measured and found critical to the final joint strength. Seals were prepared by brazing metallized Lucalox to niobium with a 60 vanadium--40 niobium braze alloy. A complex braze thermal history was required for a high-strength joint. A seal coat was developed which inhibits corrosive interaction between the braze alloy and alumina at high temperatues. With careful control of metallizing and brazing techniques, room-temperature joint strengths equivalent to or better than early 700 deg C seals were obtained. Seals were subjected to thermal stability and cesium corrosion proof tests; they remained leak tight. (40 figures) (auth)

This report provides a bibliography of sources published between June 1967 and June 1969 related to organized crime in the United States divided by material type (books and documents, Congressional Record, magazine articles, and newspaper articles).

This report is about the development of office and a synopsis of its duties and responsibilities.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

It is the purpose of this report to present data obtained from the routine reactor effluent radioactivity monitoring program as well as the results obtained from the research and development program directed toward the reduction of effluent radioactivity.

The mechanical cycling test was required to verify the integrity of the welded joints and the thin wall tube bends in the primary loop manifold assembly of a four pack thermo electric module and to help establish structural and mechanical requirements of any possible redesign. The test section was subjected to more severe loading conditions than will be experienced during actual operating conditions. The test was a mechanical simulation of the differential thermal expansion which occurs due to the approximately 600{degrees} F temperature differential in the subassembly. The actual load exerted on the test section represented this deflection. The effects on the joints and tube material were observed. The test was conducted on a test segment of manifold designed to duplicate two of the flexible elbows; the transition joints between the elbows and the tubular module inner clad; and the welded joints of the elbows to the primary loop header. The assembled test segment and hold-down bracket are shown. The bracket was mounted to the base of the Universal Test Machine. Dial indicators measured the relative displacement between the line of applied load (through the vertical axis of the primary loop header) and the attachment point at the holddown bracket. …

This report discusses the oceans resources and their potential use for food, minerals, drugs, and recreation. Plans for a formal federal research group devoted to oceanography and ocean resource research are also discussed.

This document presents details of irradiations performed for BNW as of October 31, 1969.

This report presents details of the status of special reactor process tube loadings for the month of April 1969.

This report presents the details of the status of special reactor process tube loadings for the month of March 1969.

This report presents the details of the status of special reactor process tube loadings for the month of January 1969.