DIVISION OF REACTOR DEVELOPMENT PROGRAMS MONTHLY REPORT, JUNE 1959
ABS>4 2 4 3 8 3 7 7 9 8 6 ment, and data are given on one hour hold times across the UO/sub 2/-PuO/sub 2/ composition limits. Observations made during metallographic examination are discussed, and results of sintering UO/sub 2/ are examined. Preliminary examination of a full-length Zircaloy-clad wire-wrappcd dummy element after thermal cycling in the Elmo-7 loop at 1530 psig is reported. Further tests using a Mark I-B 19-rod cluster were completed and the cluster is being examined. Production of Al -Pu billets by the PuO/sub 2/- Al-cryolite reduction process is reported. Data on intection casting using various core materials are discussed, and fuels for future PRTR and PCTR loadings are being studied. Preliminary results of Zircaloy-2 clad fuel elemert magnetic force butt welding were evaluated, and results are encouraging. Sintered and compacted powders produced by a vibration system were found to be ertirely acceptable. Effects of swaging on various types of cladding are being evaluated, and a method of testing Zircaloy-2 tubes prior to swaging was developed. In fuel evaluation a 3 ft long UO/sub 2/ rod and tube element which ruptured after reinsertion in ETR was examined. Results indicate that the failure may be due to restriction of the outer cladding coolant annulus by one or more thermocouples. Observations on an irradiated cored and sintered U0/sub 2/ fuel element after failure are listed. Test results of two 18 in. long 7-rod UO/sub 2/ cluster elements indicate that no ruptures occurred in a KER loop test. Corrosion studics include those for allowable Zr concentrations in HNO/sub 3/--HF PRTR fuel element etch bath and a dynamic bath for etching and autoclaving PRTR rod clusters. Rupture testing of simulated Al-Pu fuel elements is reported in a 30-hr, 300 test. No swelling or deposit buildup was noted. All PRTR Zircaloy tacket tubing was examined by use of a fluorescert penetrant dye. Heat transfer experiments are reported in which the heat flux at which boiling burnout in PRTR is expected are reported. Progress in mechanical equipment developmert is summarized. Included are data on a 405-hr test of a PRTR primary process pump, results of calandria mock-up tests, seal testing results, and results of Inconel X loop tests. Compilation of data and charts of input reactivity for the various transient cases to be studied on the analog computer were completed. The various cases are described. Hazard studies for various PRTR mechanical failures are summarized. Included are consideration of the effects of 14-in. header failure, maximum pressure of a shroud tube following a process tube rupture, and flow decay and equilibrium conditions following complete loss of a single primary coolant pump. A summary of the PRTR construction phase status is given along with discussion of other design progress related to PRTR and the Pu fabrication plant. Activities in PRTR planning included work on a PRTR technical manual, an operations handbook, and design of a data processing system. Tests indicate that loss of Pu to the NH/sub 4/F--NH/sub 4/NO/sub 3/ decladding solution can be reduced by treatment of the Pu core with HNO/sub 3/ before it is encased. Reduction of UO/sub 2/Cl/sub 2/ resulting from exposure of UO/sub 2/ and U/sub 3/O/sub 8/ to molten chloride salt is being studied. Reduction is complete; the UO/sub 2/ appears as a crystalline particle in the 30 to 300 mesh range. Other developments include preliminary Hg isotope separation, fabrication of an automatic ball mill feed controller, fluid bed ion exchange studies, and investigation of certain boiling metal characteristics. Simulated swelling experiments by measuring the diffusion of rare gases in uranium are in progress along with experiments to determine U pore size distribution Results of graphite oxidation experiments using CC2 are
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-13-019681
- OSTI ID:
- 4221595
- Report Number(s):
- HW-61084
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
Similar Records
DIVISION OF REACTOR DEVELOPMENT PROGRAMS MONTHLY REPORT FOR MARCH 1959
DIVISION OF REACTOR DEVELOPMENT PROGRAMS MONTHLY REPORT FOR MAY 1959
Related Subjects
ALUMINUM ALLOYS- CHROMIUM ALLOYS- ETR- INCONEL ALLOYS- NICKEL ALLOYS- NIOBIUM ALLOYS- PCTR- PLUTONIUM- PRTR- REACTORS- RECYCLING- REPROCESSING- TESTING- TITANIUM ALLOYS- TUBES
ALUMINUM ALLOYS- CORROSION- DEFORMATION- ETR- FAILURES- PCTR- PLUTONIUM- PLUTONIUM ALLOYS- PRTR- REACTORS- RECYCLING- REPROCESSING- TESTING
ALUMINUM ALLOYS- ETR- PCTR- PLUTONIUM- PLUTONIUM ALLOYS- PRODUCTION- PRTR- REACTORS- RECYCLING- REPROCESSING
ALUMINUM FLUORIDES- CRYOLITE- ETR- PCTR- PLUTONIUM- PLUTONIUM OXIDES- PRTR- REACTORS- RECYCLING- REDUCTION- REPROCESSING- SODIUM FLUORIDES
AMMONIA- ETR- LOSSES- NITRIC ACID