This report summarizes the radiation and shielding analysis for a 30,000 SHP natural circulation boiling water reactor for ship propulsion. The reactor is proposed for installation in a 60,000 DWT, 18 knot tanker of the T-7 class.

Neutron attenuation in the old pile shields is dependent more and more on the slowing down characteristics of the iron as the hydrogen is baked out of the masonite. For neutrons above 1 or 2 Mev, iron does a good job by inelastic scattering. However, below this energy attenuation can be done only by the gradual moderation by elastic scattering to thermal energies with subsequent capture in the iron. Since iron is heavy and thus a poor moderator, there is a good possibility that many neutrons of intermediate energy will leak out of a burned out shield. Also, iron has a large dip in its cross section at 25 Kev which might allow a large burst of neutrons at this energy to leak out. Measurements using a lucite moderator with gold foil detectors indicate a large leakage of neutrons of intermediate energy, but interpretation of these measurements is difficult. These considerations prompted an attempt to get a rough idea of the energy distribution of the leakage neutrons through pure iron using a simple qualitative theory.

Apparent excessive concentrations of atmospheric contamination which were reported to be associated with an inert-gas-shielded consumable electrode arc wielding operation were studied to evaluate the potential health hazards. A study was made of the concentrations of metal fume and gaseous products of the operation as well as the spectrum of ultraviolet radiation. Recommendations for necessary controls were made.

The concept of thermonuclear explosives as a potentially cheap and almost inexhaustible energy source for mankind's non military needs has for several years been under active consideration at the Lawrence Radiation Laboratory. Many of the proposed peaceful applications involve underground nuclear explosions, and several experiments at the AEC Nevada Test Site have provided valuable insight into the phenomenology of such explosions. Among the possible uses currently under consideration are excavation, heat production, isotope production, mining, recovery of oil from shales and tar sands, improvements of ground water supplies, and the construction of earth fill dams. In addition a program of experimental research in the laboratory and in the field is under way. Sometime in 1961 Project Gnome if approved will be conducted in New Mexico. The purpose of Gnome, a contained nuclear explosion in a salt deposit, is to study the feasibility of heat recovery and isotope production, neutron scattering experiments will also be included. Other proposed nuclear projects will involve the creation of a small harbor near Cape Thompson, Alaska as the result of an experiment designed to investigate the cratering effects of nuclear explosives; a proposal to investigate the recovery of oil from Canadian tar sands using thermonuclear …

Daily cash report for Imperial Sugar Company including a list of large withdrawals for the months surrounding the date showing the daily expenses and estimated balance for each entry. It also lists scheduled payments for bank loans.

An R.F. joint tester was designed to determine the relative heating and tendency toward arching at high RF current density (100 amps/linear inch) of a 12 inch diameter circular copper butt joint in vacuum with several types of inserts and at various amounts of axial loading, ranging from a very small contact pressure to one of 1400 pounds per linear inch of joint.

Abstract: The most adverse power distribution and power peaking factors have been developed for Type 3 replacement cores for SM-1, SM-1A, and PM-2A. Also included is the 37 element Type 3 core for SM-1, which is known as SM-1 Core III and is a prototype of a Type 3 core for PM-2A. The power distributions were compared with measured distributions obtained on type 3 fuel elements in SM-1, SM-1A and PM-2A core configurations. Using the measured data as a standard, correction factors were obtained and applied to the analytical predictions of the most adverse power distribution.

Daily cash report for Imperial Sugar Company including a list of large withdrawals for the months surrounding the date showing the daily expenses and estimated balance for each entry. It also lists scheduled payments for bank loans.

Time-reversal processing was simulated for several possible electromagnetic communication channels, including random point scatterers, large plates and a conducting cavity. Communication was from a single transmitting antenna to a receiving array. The effectiveness of time-reversal processing was compared for a single receiver and the array. The aim of these simulations was to determine a communication environment that would give an interesting level of multipath interference and that can be constructed in a laboratory.

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This document is a report on our activities in FY03 exploring nuclear safety and hazard analysis issues relevant to the Rare Isotope Accelerator (RIA). It is not clear whether DOE will classify the RIA as an accelerator facility subject to the accelerator-specific safety requirements of DOE Order 420.2A or as a nonreactor nuclear facility subject to the requirements of 10 CFR 830. The final outcome of this issue will have significant impact on the construction and operation of the facility and the quality assurance requirements for items or services that may affect nuclear safety. The resolution of this issue will be an important earlier decision for the RIA project team and will require early consultation with the appropriate DOE authorities. For nuclear facilities, facility hazard classification depends on the inventory of releasable radionuclides; therefore, some simplistic, scoping inventory calculations for some assumed targets and beams are done to estimate the hazard category of RIA if it is declared a nuclear facility. These calculations show that for the scenarios analyzed, RIA would produce sufficient quantities of radionuclides to be classified as a Category 3 nuclear facility. Over the lifetime of RIA operations, it may be possible to build up Category 2 …

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This report presents the findings of continued groundwater quality assessment at Waste Management Area T in the 200 West Area of the Hanford Site. It covers January 1988 through December 2001.

The FFTF Plant Operational Data Management (PODM) System provides capabilities for storing, managing and retrieving data recorded by FFTF plant computers [the Plant Data System (PDS), in particular]. The PODM system is currently implemented on SUN{sup TM} Workstations{sup (R)}. This guide contains a description of the PODM System, and instructions for using programs available for retrieving and processing FFTF data stored in the data base. Section 2.0 provides a brief overview and the background of the system. The organization and content of the data base are described in more detail in Sections 3.0 and 4.0. Available computer programs are described in sections 5.0 and 6.0 while subroutines that can be called by a user`s FORTRAN program are described in section 7.0.

Recently there has been a great surge of interest in almost-exact sum rules for the magnetic moments of nucleons. (By almost-exact we mean: exact to all orders in the strong couplings but only the lowest order in electromagnetic and weak couplings.) Besides providing a means for calculation of the magnetic moments on the same level as the calculation of GA/GV by Adler and Weisberger these sum rules, taken together with the Adler-Weisberger sum rule, constitute a useful tool for investigating the nature of the dynamical approximations that underlie higher symmetry schemes.

The 105-B Pile which was shut down on July 18, 1951 to permit removal of a ruptured uranium slug from tube No. 2169-B. The rupture was detected from effluent water monitor evidence and a survey of rear face pigtails. Removal was accomplished with the pneumatic charging machine using only normal pushing force.

There is no evidence to suggest that the adrenal medulla plays a significant role in the production or maintenance of renal hypertension. The decisive experiment was made by Goldblatt and collaborators/who successfully produced experimental hypertension in dogs by renal artery constriction despite the surgical removal of·one entire adrenal and the medulla of the other.

The General Electric Company, as prime contractor to the AEC at Hanford, is proposing to modify the lattice characteristics of the 8 3/8-inch lattice reactors for the purposes of improving the conversion ratio of these reactors. The proposed overbore modification of the reactors would remove the existing aluminum process tubes, enlarge the diameters of the graphite channels by about one-half inch, insert smooth-bore Zircaloy-2 process tubes and refuel the reactor with larger size, self-supported fuel elements. The overbore fuel will remain the internally-and-externally-cooled cylindrical type, but the weight per foot will be about twice that of the present fuel element. The removal of the inlet and outlet piping connections which would be required in the overboring process will permit the replacement of the existing fittings with ones of improved design. Furthermore, new orifices and venturis which are compatible with the hydraulic characteristics of the overbore tube and fuel geometry and the pumping system will be installed. No basic changes are proposed in the pumping system though the reactor flaw rate may be increased 5--10 percent by changes in hydraulic characteristics depending on the water plant flow capacity.

Construction of proposed facilities to be operated under Technical Division supervision for research with plutonium is discussed. An attempt is made in this memorandum to visualize the research program for such a facility for the next five years, to aid in determining whether the cost of providing such facilities is justified.

One problem faced in the clean-up operation at Hanford is that a number of radioactive waste storage tanks are experiencing a periodic buildup and release of potentially explosive gases. The best known example is Tank 241-SY-101 (commonly referred to as 101-SY) in which hydrogen gas periodically built up within the waste to the point that increased buoyancy caused a roll-over event, in which the gas was suddenly released in potentially explosive concentrations (if an ignition source were present). The sonic probe concept is to generate acoustic vibrations in the 101-SY tank waste at nominally 100 Hz, with sufficient amplitude to cause the controlled release of hydrogen bubbles trapped in the waste. The sonic probe may provide a potentially cost-effective alternative to large mixer pumps now used for hydrogen mitigation purposes. Two important parameters needed to determine sonic probe effectiveness and design are the speed of sound and yield stress of the tank waste. Tests to determine these parameters in a 240 ml sample of 101-SY waste (obtained near the tank bottom) were performed, and the results are reported.

One of the early candidate fuel elements for N Reactor use was the coextruded, Zircaloy-2-clad seven-rod cluster. As part of the program of evaluating the seven-rod cluster geometry, three-rod cluster fuel elements, two and three feet long, were irradiated. These long cluster fuel elements were irradiated to determine the distortion (or sag) which might occur at the center of the unsupported length during irradiation. Two three-rod clusters made up of 0.630 inch diameter rods, containing natural uranium cores were irradiated in KER Loop 3. The rods of one cluster were three feet long; the rods of the other were two feet long. The three-feet long rods were supported at their ends and at their midlengths, the two-feet long rods only at their ends. During the irradiation, the maximum core temperature was 435 C. The fuel elements were discharged from the loop after they had reached an exposure of 1400 MWD/T. Following the discharge, the fuel elements were visually examined in the KE view pit. No sag was observed in any of the rods. The test demonstrated that two- and three-feet long rod cluster fuel elements can be irradiated without appreciable sag occurring in the rods.

This Progress Report describes the operation of the Los Alamos Meson Physics Facility (LAMPF) and the research programs carried out there for the years 1992 and 1993. The accelerator operated for over 100 days in 1992, providing beams of H{sup +}, H{sup {minus}}, and polarized H{sup {minus}} for a rich and varied research program in nuclear physics. The accelerator had only fair beam availability in 1992 (for example, the average H{sup +} beam availability was 72%), caused largely by problems in the 201-MHz rf system. A major effort was expended to address these problems before the 1993 run. These efforts were rewarded by good beam availability in 1993 and few problems with the 201-MHz system. LAMPF operated remarkably smoothly during 1993, in the midst of a period of great uncertainty in the future of the facility and the downsizing of MP Division, which led to the loss of a large number of key people to positions elsewhere in the Laboratory. The H{sup +} intensity had to be held to no more than {approximately} 800{mu}A because of a vacuum leak in the A2 target. Nevertheless, the accelerator operated very.reliably and the summer run in 1993 proved to be extremely productive. This …

This report contains a letter, written on July 25, 1947, concerning the sampling program at Columbia River. The author suggests reducing the sampling schedule. He states that chemical composition sampling should be reduced by one-fifth and radioactivity sampling be reduced by one-third. He suggests that only mid-channel samples are required for representative studies. He further states that weekly sampling should occur. By following these suggestions, the cost of the sampling program should be drastically reduced because the hours of manpower taken to sample the river, analyze the data, organize, and store information would be reduced.

One of the early candidate fuel elements for the N Reactor was the seven-rod cluster fuel element. An objective of the program to determine the suitability of the seven-rod cluster fuel element for N Reactor use was to evaluate the irradiation performance of coextruded, Zircaloy-2-clad, seven-rod cluster fuel elements over a range of exposures from low exposures to high exposures. This report describes the irradiation testing of an enriched seven-rod cluster fuel element which was irradiated to 520 MWD/r.