The results of a multi-group, diffusion type code computation for the fast neutron flux distribution in C, K, and N reactors are presented. Relative Ni activations in conjunction with the calculated neutron spectra are used to obtain values for the integrated fast flux per MWD/AT for C and K reactors. The relative, theoretical, integrated fast flux values at the same adjacent fuel powers in C, K, and N reactors in the mid-plane of the filler layers are: (1) C = 1.0; (2) K = 1.3; and (3) N = 2.6. For C reactor, the best estimate of the integrated fast flux per MWD/AT is: 5.0 {times} 10{sup 16} nvt (> 1 MeV) = 1 MWD/AT.

Recent borescoping of the KER-1 tube revealed several scratches, pits, and gall marks on the internal wall of the tube. These deformations could limit the operating temperature and pressure of KER-1. This report is a summary of operating history and is compiles to assist in determining what contributed to the condition of the tube.

The high pressure loop installed in the 3X3 reflector position of the ETR and the associated instrumentation to detect and study failure mechanisms handled the rupture tests without difficulty. Failure of the elements was initiated by shearing off a projection on the fuel elements. The first test of the series used previously unirradiated seven-rod clusters. After the projection was sheared off the fuel elements were operated for seven hours with no failure. Failure is defined as having occurred when sufficient uranium oxide has formed to split open the cladding and release large amounts of fission products into the loop water. The second and third tests used fuel which had been irradiated to 2400 MWD/T at Hanford prior to insertion into the ETR. The second test was operated for 14 hours after the projection was sheared off--again with no failure. The third test was operated for only 33 minutes after the projection was sheared off before fission product activity in the loop water caused the test to be terminated.

Compensation for the positive long-term reactivity transient associated with Hanford reactor may be accomplished in two ways: The addition of a poisonous material (rods, splines, etc.) to the reactor, or cooling the moderator by changing the gas composition. The objective of this study is to investigate the reactivity and temperature effects and the associated operating problems if any, resulting from the use of nitrogen instead of carbon dioxide as a constituent of the reactor atmosphere.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether or not Rule 42 of Vernon's Texas Rules of Civil Procedure, relating to Class Actions, will apply to Eminent Domain proceedings.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the members of the Committee on Saving Taxes, authorized by House Simple Resolution No. 152, 56th Legislature, Regular Session, 1959, are subject to provisions of House Bill No. 14, 56th Legislature, Third Called Session, 1959, and related questions.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether Section 7-a of Article VIII of the Texas Constitution prohibits the expenditure of highway funds for publishing and distributing a brochure, advertising Texas, attracting tourists, encouraging and distributing automobile travel, and giving information pertaining to the supervision of traffic and safety on our highways.

The production gains and economic evaluation of overboring has been extensively treated. In this document, the justification for a trial attempt at overboring C-Reactor was given. The overboring test, covered by two production tests (one or overboring and one for fuel irradiation), requires the integration of efforts of Equipment Development, Process and Reactor Development, Process Technology, Manufacturing, and the Fuels Preparation Department. In view of this, it appears prudent to collect in one place the current design numbers with a word of explanation regarding their derivation. To this end, this document is dedicated.

This partially annotated bibliography contains references on boiling heat transfer of liquid metals. Emphasis is place on boiling heat transfer of liquid sodium, liquid potassium, and liquid rubidium. The period covered is 1950 to date. References are arranged alphabetically by title. Sources used in compiling this bibliography are: Abstracts of Classified Reports, Nuclear Science Abstracts.

ABS>Experimental heat transfer data and analysis are reported for the Title II fuel assembly design modifications and refinements. Three distinct mid- length spacer designs are described. All tests are conducted with a 3,000-in. M fuel assembly sleeve and with the six outer tubes (of the seven tube cluster) located on a 2.000-in. BC. The dath are presented as heat transfer correlations and as comparisons of the heat transfer test results of one design with the results obtained from the other two and also the test results of the Title I fuel assembly design spacers. (auth)

None

This report is about the United States and the Japanese code prior to pearl harbor

Abstract. The Tory II-A reactor is a small, air cooled, high power-density reactor which is to operate at quite high temperatures. Design of the reactor is essentially complete. First operation is scheduled for late 1960 at the Nevada Test Site of the Atomic Energy Commission. Since the reactor is unshielded, the control room which houses the recording and indicting equipment is located approximately two miles from the test bunker. Signals from reactor and facility transducers are amplified in the test bunker and transmitted by cable to the control point. The kinds of quantities measures include neutron flux level, temperatures, pressures, vibration amplitudes, strain and air mass flow rate. The recording and indicating system is centered around 258 channels of 1.5 cycle per second, pulse-width modulation tape recording equipment and 72 channels of 120 cps, analogue strip-chart records. In addition, there is a number of the usual meters, scalers and slow-response strip-chart recorders.

From Abstract: "This Monograph has been prepared to give an understanding of heat treatment principally to those unacquainted with this subject. This Monograph has been prepared to answer such inquiries and to give in simplified form a working knowledge of the basic theoretical and practical principles involved in the heat treatment of iron and steel."

Report giving tables of the specific heat, cp, and the enthalpy of 28 metals, 3 alloys, 8 other inorganic substances, and 8 organic substances in the temperature range, 1º to 300º K.

Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.

The attached memo by G. N. Krouse of Sturm-Krouse, Inc. gives results of a preliminary analysis of the deflections of beam holes due to thermal expansion and internal pressure in the vessel. A partial solution of the problem is suggested. Based on preliminary pressure-temperature data the following deflections were derived: Movement of horizontal beam tubes = 0.046 in. Movement of Engineering facility tubes = 0.117 in. Vertical motion of the vessel at the horizontal beam tubes due to thermal expansion may be eliminated by locating the supports in that plane. That also will reduce the expansion at the point where the slant tubes pierce the vessel wall.