Sodium fire protection by space isolation with nitrogen flooding was evaluated by performing a large-scale sodium fire test within a mockup of an FFTF secondary sodium system pipeway. The full scale (3350 ft/sup 3/) mockup was initially filled with air and its leak tightness set to correspond to that expected in an actual FFTF pipeway. The basis for specifying the rate of nitrogen flood gas is discussed ad the experimental verification provided. Nitrogen flooding was activated 15 minutes after the spill of 770 lb of 1100/sup 0/F sodium into a 32 ft/sup 2/ steel pan. The nitrogen flow was controlled manually at a constant rate of 60 ft/sup 3//min (STP) until the pool temperature had decreased to 370/sup 0/F. After cooldown, 87% of the spilled sodium remained in the unreacted form, demonstrating that sodium fires can be effectively controlled by the method of space isolation with nitrogen flooding.

As part of the overall study of the consequences of a hypothetical failure to scram following loss of pumping power, design requirements and preliminary concepts evaluation of an ex-vessel core catcher (EVCC) were performed. EVCC is the term applied to a class of devices whose primary objective is to provide a stable subcritical and coolable configuration within containment following a postulated accident in which it is assumed that core debris has penetrated the Reactor Vessel and Guard Vessel. Under these assumed conditions a set of functional requirements were developed for an EVCC and several concepts were evaluated. The studies were specifically directed toward the FFTF design considering the restraints imposed by the physical design and construction of the FFTF plant.

In this analysis the structural integrity of the double tubesheet connector for the LMFBR demonstration plant steam generator is investigated for design and steady state conditions. Although the evaporator and superheater are to be interchangeable, only the steam outlet end of the evaporator is investigated. This was selected because the mean temperature differences between the tubesheets, tubes and connector are largest here at steady state, thus yielding the highest thermal loads. Combined with the thermal loads are superheater pressures in order to also use the highest mechanical loads. Although this is a conservative approach for the evaporator, the superheater must be analyzed separately at a later date in order to assure interchangeability. Evaluation of the results is based upon ASME Code Case 1331-8.

The Pacific Hake, Merluccius productus (Ayers) was used to monitor the waters off Puget Sound and the West Coast of the US for zinc(Zn), cadmium(Cd), mercury(Hg) and {sup 65}Zn. The Columbia River is not the source of Zn, Cd or Hg contamination, but is the source of {sup 65}Zn, with the concentration in the Hake reflecting the position of the Columbia River plume. Zn and Cd accumulation in the Hake were fit to the equation Y=B{sub 1}+B{sub 2}e{sup B}{sub 3}X where Y is the concentration of the element and X is the length or weight of the fish. Biological attributes were assigned to the other parameters as follows: B{sub 1} is the asymptotic value for Zn or Cd at chemical maturity; B{sub 2} is the location of the curve with respect to the length or weight of the fish; and B{sub 3} is a constant pertaining to the rate of change of Zn or Cd. Although Zn, Cd and Hg are all Group 2B elements, only the concentrations of Zn and Cd were correlated for all locations; Hg concentrations varied as a function of location. Zn and Cd concentrations increase with fish size and approach an asymptotic value at maturity, …

This specification establishes the requirements and procedures (using epoxy adhesive) for the installation and removal of the dynamic inflatable test seal for the Fast Flux Test Facility (FFTF), In-Vessel Handling Machine (IVHM) Reactor Refueling Plug (RRP).

Missing mass spectra were obtained by measuring recoil protons from the reaction p + p {yields} p + X in the Jacobian peak region at |t| = 0.175 and 0.25 (GeV/c){sup 2}. The incident momentum range from 9 to 300 GeV/c was covered continuously by taking data during the acceleration ramp of the Fermi National Accelerator Laboratory machine. Our missing mass range varied from 1.5 to 8.5 GeV and we observed the well known N*(1688) and N*(2l90) but no significant structures at higher mass.

The authors have observed two events induced by high energy (> 150 GeV) neutrinos in which two highly penetrating particles (muons) of opposite sign are produced. Both events have a large inelasticity and a massive {mu}-hadron system.

The reaction {pi}{sup -}p {yields} {pi}{sup -}{pi}{sup +}{pi}{sup -} p at 100 GeV/c has been analyzed in terms of effective mass and rapidity variables. It is found to be dominated by two well-separated processes, i.e. the diffractive dissociation of the pion and that of the proton. the Diffractive nature of these processes is confirmed by the weak energy dependence of the cross section for the reaction, which falls like p{sub LAB}{sup -0.25} between 5 and 200 GeV/c. A small class of events is found having the properties expected for 'double Pomeron exchange', {pi}{sup -}p {yields} {pi}{sup -} ({pi}{sup -}{pi}{sup +})P. The cross section for such events is estimated to be 40 {+-} 20 {micro}b.

Data tabulated for chemical composition of geothermal waters are presented for four areas of interest in Nevada: Beowawe steam well and Beowawe Hot Spring, Buffalo Valley Hot Springs, Kyle Hot Springs, and Leach Hot Springs. Material recommendations were prepared for the Nevada geothermal well. A detailed field corrosion test program planned for the Nevada test well is included. A progress report is presented for a laboratory research program on velocity effects in corrosion. (MHR)

Engineering scale experiments were performed to determine the fractional airborne release of strontium during a fire involving a contaminated, flammable solvent. Earlier laboratory scale experiments using radioactive materials indicated that this release would be one percent or less. Twenty-five grams of strontium as strontium nitrate was added to 150 liters of 30% normal tributyl phosphate in a kerosine diluent, which was then burned in the ARHCO 224-T Fire Test Facility. Temperatures of 1000/sup 0/C were recorded during the fire, the maximum scale of the instruments. There were 2 successful fires lasting 70 and 51 minutes, both burning to the point of self-extinguishment. 0.2% of the strontium was released in both burns. The bulk of the released strontium measured was collected in bubbler samplers installed upstream of the sprayed chamber air washer, indicating that the water sprayed in this chamber scavenged the strontium from the air stream.

Neutron total and elastic and inelastic scattering cross sections of /sup 92/Mo, /sup 96/Mo, /sup 98/Mo and /sup 100/Mo were measured. Neutron total cross sections were determined at intervals of less than or equal to 10 keV from 1.6 to 5.5 MeV with resolutions of approximately 10 keV. Neutron elastic and inelastic scattering cross sections were measured from 1.8 to 4.0 MeV at intervals of 0.2 MeV. Neutron groups corresponding to the excitation of forty states were identified. The experimental results were examined in the context of optical- and statistical-nuclear models. It was concluded that the real part of the optical potential includes a term proportional to ((N - Z)/A) and suggested that the imaginary part is shell dependent with decreasing magnitude as N = 50 is approached. Comparison of measured and calculated inelastic neutron excitation cross sections suggested a number of J/sup ..pi../ assignments extending previous knowledge. The experimental and calculational results were used, together with previously reported values, to generate an evaluated neutron total and scattering cross section file in the ENDF format extending over the energy range 0.1 to 8.0 MeV.

A simple program is explained for those who are just beginning to work with computers in general and the MCS-8 Microcomputer in particular. The text is a guide to understanding some of the processes which occur when a program is written into random access memory (RAM) with the Octal Debug technique (ODT). 3 figures. (RWR)

A description of the Marysville site is given. The drilling program, an environmental analysis, and a survey of geophysical surveys are described. A preliminary survey is presented of the area using aerial thermal infrared imaging techniques. (MOW)

The objective of Mound Laboratory's Decontamination and Decommissioning (D&D) projects has been the effective termination of radioactive material processing facilities with no significant personnel exposures or environmental releases. This objective must be met with available resources and manpower. Mound has effectively decontaminated and/or decommissioned four major facilities in the 1949 through 1973 time period. Many minor areas were also decontaminated and/or decommissioned during this period. The major D & D projects involved the following isotopes: polonium-210, radium-226, actinium-227, and plutonium-238. To achieve a D & D status, Mound has employed several control and decontamination techniques such as: "Navy Cocooning", entombment, removal, foaming, bagging, tents, chutes, portable exhausters, dry ice, vents, bubble suits, three-zones, fire watches, painting and sealing, in-line cleaning, high pressure water blaster, and chemical cleaning.

Methods and facilities have been developed for the collection, storage, measurement, assay, solidification, and packaging of tritiated liquid wastes (concentrations up to 5 Ci/ml) for disposal by land burial. Tritium losses to the environment from these operations are less than 1 ppm. All operations are performed in an inert gas-purged glovebox system vented to an effluent removal system which permits nearly complete removal of tritium from the exhaust gases prior to their dischardge to the environment. Waste oil and water from tritium processing areas are vacuum-transferred to glovebox storage tanks through double-walled lines. Accommodations are also available for emptying portable liquid waste containers and for removing tritiated water from molecular sieve beds with heat and vacuum. The tritium concentration of the collected liquids is measured by an in-line calorimeter. A low-volume metering pump is used to transfer liquids from holding tanks to heavy walled polyethylene drums filled with an absorbent or cement for solidification. Final packaging of the sealed polyethylene drums is in either an asphalt-filled combination 30- and 55- gallon metal drum package or a 30-gallon welded stainless steel container.

None

None

None

None

None

None

None

None

None