This report details activities of the Hanford Atomic Products Department for the month of October 1966.

None

None

None

None

Daily check of 325 stack filters on 5/9/66 revealed contamination released to the atmosphere within the operating area. Investigation indicated that about 0.4 Ci (mostly Ce-144) had been released as a result of steam jet transfer of some Ce-141-144 from a cask to a storage vault in 325-A. on 5/9/66. A further release of about 0.2 Ci vas indicated by survey of stack filters 5/12/66 following completion ot the transfer. Actions taken include vehicle smears, ground surveys around the 300 area fence line, and smears of the 329 loading dock. Daily check or 325 stack filters on 5-9-66 shoved an increase from about 8000 c/m (GM) Friday afternoon to about 450 mrads/hr (CP) Monday afternoon. Vehicle smears on 4-12 shift 5/9/66, ground surveys around the 300 Area fence line, and smears of the 329 loading dock have not revealed any contamination spread. Inventory in 325A (5/10/66) includes about 3 x 10{sup 6} Ci Ce-141-144 and about 3 x 10{sup 6} Ci Pm-147.

None

SNAP 10FS-3 was the first flight-qualified SNAP reactor system to be operated in a simulated space environment. Prestart-up qualification testing, automatic start-up, endurance period performance, extended operation test and reactor shutdown are described as they affected, or were affected by, overall reactor performance. Performance of the reactor control system and the diagnostic instrumentation is critically evaluted.

This report analyses the crude oils from many oilfields within the U.S.

A previously reported cation exchange process for the recovery of Pu from sump water was studied in order to improve the procedure. The flowsheet calls for adjustment to 0.03M HNO/sub 3/, the addition of NH/sub 4/HSO/sub 3/ for Pu reduction, the addition of Al/sup 3 +/ to complex F/sup -/, followed by passage of the solution through a column of Dowex 50W, X-8 resin. Distribution coefficients were measured between the resin and synthetic sump solutions under a variety of possible simulated flowsheet conditions. By far the highest distribution coefficients were obtained with Pu(III) without the addition of Al. Results with Pu(IV) varied from borderline to unsatisfactory depending on conditions. It is concluded that the process will be satisfactory if the Al addition is eliminated. (JGB)

The ''handbook'' density for LiAlO/sub 2/ is 2.55 g/cc. Recent data show that it should be revised to 2.62 g/cc. In the future densities reported as percent of theoretical should be based on 2.62 g/cc as being 100 percent. Values quoted on this basis will be more realistic. In order to avoid confusion it will be necessary to state which number percent of theoretical density are based upon--that is, ''2.62 g/cc = 100 percent,'' or ''2.55 g/cc = 100 percent.'' For the convenience of those working directly with the material, a conversion chart is included along with a table which gives density (g/cc) versus percent density based on 2.62 g/cc.

The design of a Phase II dummy hydraulic core for the CSE reactor simulator is described. The core will be a scale model having features typical of PWR or BWR reactor cores, and will include control rods and associated support mechanisms, fuel elements, a thermal shield, top and bottom core guide and support plates, and flow baffles. The core and simulator vessel will be instrumented to provide measurement of temperature, static and differential pressures, forces on core components, and rarefaction wave pressures during high temperature, high pressure blowdown studies.

In recent years there has been an increased interest in the use of transuranium isctopes for special power applications. Moreover, as the civilian power reactor economy expands, a large quantity of such isotopes will be formed in reactors using slightly enriched uranium fuel and, more particularly, in reactors which recycle the higher isotopes they form. This report, consisting mainly of computer printouts, indicates the yields of transuranium isotopes from different fueling methods. Since water reactors will be the predominate type of power reactor for at least a decade, most of the values presented here are derived from simulated water reactors.

None

This note refers to the classification of two letters on reactor water flow.

This is the second semiannual issue of reactor and power operations data for the Hanford Production Reactors. Summary data from the first issue (1) are repeated for comparison. Experience during each succeeding six months period will be added to these data in later reports until two full years of operating experience are shown. For comparison purposes, the two years of experience will then continue to be shown by dropping and adding a six months period with each semiannual issue. This report is for the period ending June 30, 1966.

Letter with the subject line "Reply to teletype from C. H. Reichardt" providing a reply to questions about the possible release of radioactive barium during processing of irradiated fuel. A discussion is also provided on fission product volatilization from melting or burning fuel.

This report for March 1966, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations.

The programmed long outage which started May 1 was concluded on June 6. During this outage, the sixth heat exchanger cell was tied in, the auxiliary steam boiler was completely overhauled, four steam generators were equipped with isolation valves, extensive replacements of the process tube resistance temperature detectors were made, the reactor was re-orificed, a leaking reactor gas seal was repaired, extensive preventive maintenance was done, and numerous smaller pieces of work were accomplished. After startup, testing of the WPPSS generating station equipment was resumed. Electric power up to 320 Mw was generated, generator trip-offs were executed, and data on the reactor plant response were taken. Both the generating station and the reactor plant behaved excellently. The sixth cell installations performed as designed. Electrical power generation is now limited to about 400 Mw by the unavailability of a step down transformer on the BPA system at Vantage. Elevation of the generated power level to the rated 800 Mw will be possible in the early autumn when transformer delivery is expected by BPA. Three scrams from relatively low power levels occurred during the June 6 startup, which may be regarded as being associated with returning the plant to service after a …

Submitted herewith are source and special nuclear material composition of ending reports for the month of May 1966. Production processes and products and weapons process and products are accounted along with nonproduction reactors R&D.

Data acquired from the temperature monitoring of Columbia River during 1963 through 1965 is presented.

This document is an inventory of the nuclear materials held on site at HAPO.

The reactor was manually scrammed from 3870 Mw on January 4 due to a rupture suspect. The failure was subsequently identified as a fretting type on the inner surface of a single tube test fuel element. The evidence indicates that a buggy spring support vibrating against the inner spring of the fuel caused the clad perforation. The remaining column of single tube fuel was discharged. The reactor operated at 3730 Mw until January 7, when the loss of instrument air supply caused the reactor to scram. Upon reinstatement of the instrument air supply the reactor was started up on January 8 and achieved 4000 Mw operation on January 10. After the startup on January 8, the plant operated at essentially full power until January 13. At this time a scram occurred due to loss of header pressure on the steam supply to the drive turbines. The scram was found to have been due to energizing an improperly wired control panel which was a part of the tie-in of the sixth cell work. While the reactor was down, heat exchanger 3B was hydrostatically tested and repaired. A leak in the auxiliary plant boiler was also repaired and an inspection of the …

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. Samples of the effluent from each reactor are obtained each weekday during operation and analyzed for P{sup 32}, As{sup 76}, Np{sup 239}, and Cr{sup 51}.