skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: NUCLEAR SUPERHEAT PROJECT FIFTH QUARTERLY PROGRESS REPORT, JULY-SEPTEMBER 1960

Technical Report ·
OSTI ID:4832525

Conceptual Design and Program Evaluation. Reactor design work has reflected requirements for preparation of cost estimates for a 300 Mw(e) Separate Superheat Reactor Plant complex. The major design features of the complex are single pass, light water moderator, and low enrichment UO/sub 2/ annular fuel configuration. The core power density is 37 kw/liter. The average heat flux is 148,000 Btu/hr-ft/sup 2/ with a maximum clad surface temperature of 1250 deg F. Analytical work done to establish the thermal effect of the superheat fuel element for specified rate of change of reactivity of various reactor core conditions, established maximum reactivity insertion rates. The reactivity effects of flooding the steam passages of the process tube were evaluated. The largest reactivity change occurred for the ganged rod case where there was relatively high leakage from small critical portion of the core, which is 8% DELTA k/k but may be reduced by approximately a factor of 2 by utilization of burnable poisons. Fuel Technology. Capsule irradiations performed in the trail cable facility revealed: growth of the outside cladding occurring in each capsule irradiated; the UO/sub 2/ fuel material receding away from a plastically deformed clad after cooling; and axial growth observed in all capsules irradiated. Development work is in progress on low-thermal cross-section processtube designs. This includes corrosion evaluations of zirconium process tubes and thin-wall stainless steel tubes filled with aluminum oxide powder. Samples have been fabricated and are on hand for a second dynamic erosion experiment for UO/sub 2/ powder. Corrosion and Coolant Chemistry. Difficulty has been encountered in maintaining a controlled atmosphere of H/sub 2/O/sub 2/ in the superheat corrosion test loop. Two runs have been performed, one of 780 hr where a non- uniform type of corrosion was noticed. Metallurgic examination of this corrosion specimen is reported. During the second run of 1200 hr operation an electrolytic decomposition element was installed to successfully maintain the gas atmosphere at 16 ppm O/sub 2/ and 2 ppm H/sub 2/ in the influent steam. Heat Transfer. 231 test runs have been completed on the once-through heat transfer experiment. Based on the results, design work on the conceptual design of a once-through coolant superheater is being initiated. The general conclusion drawn from test operating experience is that the once-through reactor can be built to operating beyond the so called ''burnout point'' because convective film coefficients are high enough to maintain the heated wall temperature within design limits. Mechanical Development. Performance tests on a steam dryer as part of a simulated nine-element process-tube fuel assembly were conducted. Satisfactory performnance was obtained from superficial velocity to 5.5 ft/second with inlet moisture not greater than it was by weight. Mixed Spectrumn Superheater Study. The design work has continued to support the conclusions of the initial study that the mixed spectrum superheater concept is feasible and economically attractive. (auth).

Research Organization:
General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
DOE Contract Number:
AT(04-3)-189
NSA Number:
NSA-16-002733
OSTI ID:
4832525
Report Number(s):
GEAP-3581
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English