DIVISION OF REACTOR DEVELOPMENT PROGRAMS MONTHLY REPORT FOR FEBRUARY 1959
Hydrogen absorption and sintering properties of PWR grade UO/sub 2/ -PuO/ sub 2/ systems were investigated. The induction melting facility for Al-Pu alloy preparation and casting was activated, and Al-U extrusions were made using a 280- ton press. Development is reported in fuel element die casting, as well as progress in Mark I fuel element design engineering. Fabrication of PRTR fuel elements continued with emphasis on quality improvement. Fabrication development included a technique for welding rectangular Zircaloy ribs to Zircaloy sheet. Evaluation of swaged UO/sub 2/ samples after MTR irradiation is reported. Exploration of ultrasonic agitation for use in Zircaloy etching baths was conducted. Various design tests sueh as cold PRTR pump performance, test of an injection pump, reactor piping structural integrity tests, and Zr tube burst tests are reported. Design analysis is reported in such areas as PRTR tube design and control instrumentation. Development of plutonium oxalate disk filters was continued, and a method of producing a steady filter pressure drop and volume flowthrough is reported. Data on heavy water moderated cluster latiices were correlated, and reasons for discrepancies are given. Nuclear safety in handling PRTR fuel elemcnts was studied, and recommendations for handling equipment modification were made. 6.4 days was established as the discharge interval for spike elements in PRTR. A report on cycle analysis was completed in which the reactivity worth of Pu and U-235 is examined. A single- pass fuel cycle code for IBM-709 was developed and an IBM-650 analysis of effects of varying the composition of Pu feed as well as the special effects of Pu stainless steel cladding is reported. Weight loss studies of graphite CO/sub 2/ oxidation were continued as well as development of test methods for coated graphite properties determination. Criteria for safe storage of 1.8% U-235 enriched UO/sub 2/ fuel elements are listed. Theoretical studies to predict values of thermal utilization for various lattice spacings in PCTR were conducted, and modifications for the expressions for use when a control rod is present are being developed. Effects of ultrasonic Lamb waves were explored including investigation of thcir effects on adhesives and welds. Development of radiant heat spray calcination was continued and runs with an 8-in. design are reported in which the operation technique was aimed at optimizing conditions. Supporting studies in the 3-in. column are also reported. (For preceding period see HW-59179 ) (J.R.D.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- W-31-109-ENG-52
- NSA Number:
- NSA-13-011447
- OSTI ID:
- 4276385
- Report Number(s):
- HW-59600
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
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