Interaction of {alpha} particles with elements of low atomic number leads to the emission of neutrons by the ({alpha}, n) reaction. The light element content may become one of the limiting factors in the production of U-233 acceptable for projected uses. Neutron production by the ({alpha}, n) reaction was calculated as functions of U-232 and light element contents.

A letter dated June 3, 1963 to W, E. Johnson, General Manager, Hanford Atomic Products Operation, from J. E. Travis, Manager, Richland Operations Office requested an updated study on the expected life of existing production reactors similar to Sections II, III and IV of document HW-59000. This study covers the ten year period to FY 1973 as the previous study document covered the ten year period FY 1958 to Fy 1968. In Section II, production has been forecast for the existing plant with no improvements beyond the current program for installation of zirconium process tubes in the K Reactors. Section III contains estimates of additional production from the six smaller reactors made possible through overboring the process channels and retubing with zirconium plus the associated water plant expansions. Section IV presents our analysis of the assurance which can reasonably be assigned to the predictions of Sections II and.III. The production forecasts have been prepared from the same base as the current production studies and have been developed within the technical limits listed later in the report,

The objective of this test is to evaluate the irradiation dimensional stability of uranium fuel cores produced by an induction heat treating process.

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Feasibility and cost data are supplied for the production of tungsten-rhenium alloys from tungsten targets in the N-Reactor. The two types of target elements assumed were: (a) tungsten containing 90 a/o tungsten-186, 9 a/o tungsten-184 and 1 a/o tungsten-183 and 182, and (b) tungsten of natural isotopic composition (28.4 a/o tungsten-186, 30.6 a/o tungsten-184, 14.4 a/o tungsten 183, and 26.4 tungsten-182). It is assumed that the average thermal neutron capture cross section for the tungsten-186 is 32 barns.

This report briefly describes the circumstances involving the accidental release of Iodine 131 into the atmosphere from the Purex Plant at Hanford in September, 1963.

The production of Po{sup 210} by irradiating Bi{sup 209} has been proposed as a possible use of N Reactor. The purpose of this study was to make an estimate of the production rates for various exposure times and flux levels. The production rate was calculated for the three flux levels of: (1) 5.0 {times} 10{sup 13} neutrons/cm{sup 2}/second, which is about the average flux level expected in the N Reactor graphite moderator; (2) 6.74 {times} 10{sup 13} neutrons/cm{sup 2}/second, which is the estimated flux level in the 68 empty process tubes on the top and bottom of the N Reactor core; (3) 7.5 {times} 10{sup 13} neutrons/cm{sup 2}/second, which is the estimated flux level present in a flux trap made by removing a column of fuel. In addition to the above calculations, an estimate was made of the fuel enrichment needed to support a column of bismuth in the core of the reactor; and the percentage loss in the Pu production was calculated for the reactor.

Reactor Fuel Elements--temperature peaking in SNAP due to surrounding rods; systems for nuclear auxiliary power (SNAP)--reactor fuel temperataure peaking due to surrounding fuel rods; temeprature--calculations of peaking of, in SNAP fuel due to sourround fuel rods.

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Modifications consisted of redesigning the feedback loop and shielding the toroid to minimize capacitive pickup and of insulating the core from the magnet buss. A system analysis is presented, and system controls and operation are described. Operational properties of the redesigned loop and tests on the insulation between the grounded Faraday shield and the magnet buss and core are discussed. (D.C.W.)

Structural evaluations were made of the 15% cold-worked Zircaloy fuel- element containers proposed for the NS Savannah reactor. These evaluations, which are consistent with the Navy Code, permitted the sizing of components so that under conservative loading conditions both stress and deflection limitations would be met. The necessary design modifications were specified for the fuel- element container assembly. (auth)

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This report explains details of the Advanced Materials Program. The purpose of this program is to develop improved alloys for nuclear powerplant structural applications in the 16000F to 2000F range and for advanced applications at temperatures to 2400F or above.

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The use of bubble density measurements to eliminate obviously wrong mass assignments is described. The process is traced through each of the four computer programs of the Hough-Powell system. (D.C.W.)

Source-deck listings of two computer programs are given for the calculation of relative intensities in the vibrational structure of an electronic transition. The first program finds turning points of an electronic potentialenergy curve by direct numerical evaluation of the Klein action integrals in the RKR procedure. The second program uses these turnlng points to construct an effective potential for the molecule with rotational quantum number J. The radial Schrodinger equation then is solved for this potential to yield vibrational-rotational wavefunctions from which the program calculates Franck- Condon factors, rcentroids, and relative intensities. Sample input and output are included. (auth)

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A survey of literature on irradiation experience with boron stainless steel was conducted to determine the effect of neutron irradiation and boron-10 burnup on the two weight per cent natural boron stainless steel control rods being used in the Pathfinder reactor. The literature reviewed included irradiation test samples and full-size control rods in operating reactors. From the analysis of the survey, it was concluded that the Pathfinder control rods will operate satisfactorily and retain their integrity within the burnup limits prescribed. The effects of irradiation and boron-10 burnup on boron stainless were divided into the categories of mechanical properties, cracks, and swelling and gas release. These categories were examined in detail with the data available and correlated with the Pathfinder rods and operating conditions. The allowable local burnup of the boiler rods is limited to one core at.% (50% boron- 10 depletion) and the superheater rods are limited to one-half core at.% (25% boron-10 depletion). (auth)

At the Chemonuclear Workshop held at Brookhaven National laboratory in November 1962 it was pointed out that the production of ozone from oxygen by a liquid phase fission fragment chemonuclear process appears to have reasonable economic potential. The maximum theoretical reaction yield for the formation of ozone from oxygen is a "G" value of 68 molecules for 100 ev based on heat of reaction data. The authors felt a "G" value of 15 to be reasonable for this study. the reactor system chosen has liquid oxygen as its moderator and the operating pressure and temperature were selected so as to allow boiling of the oxygen-ozone mixture. The total plant investment cost is estimated to be in the range of $100,000,000. Other system designs will be considered in the future.