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REACTIVITY LIFETIME 5091.4-5806.1 EFPH. CORE I, SEED 1. Test Results T- 612118-B

Description: The Shippingport Atomic Power Station was operated for 715 EFPH from Ang. 11 to Oct. 7, 1959, in order to determine the performance characteristics reliability, stability, and lifetime variation of the core during rated power operation for an extended period of time. The plant was operated at successively lower power levels of 60, 43, and 17 Mwe to extend the Core I, Seed 1 lifetime. Logs and tables are included which present the events and all recorded data in this period. (D.L.C.)
Date: August 1, 1960
Partner: UNT Libraries Government Documents Department

REACTOR PLANT SELF-ACTUATED RELIEF VALVE OPERATION. CORE 1, SEED 1. Test Results T-643700

Description: The relief valves that were tested included four each in the reactor coolant loop and in the purification system. Test results are tabulated which indicated that all valves operated at or witai the prescribed limits of 2530 plus or minus 50 psig in the "as left" condition. Most of the valves had to be popped and adjusted several times befors the valves would pop at a pressure within the prescribed limitations. Some of the difficulties encountered during the testing are discussed. (B.O.G.)
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department

ENGINEERING MATERIALS LIST. A Catalog of Drawings, Photographs, and Specifications Released by the United States Atomic Energy Commission. Supplement 1: SHIPPINGPORT PRESSURIZED WATER REACTOR

Description: Unclassified Engineering Materials List, TM-4100(lst Rev.), is a catalog of available U. S. Atomic Energy Commission unclassified engineering drawing materials on the peaceful applications of atomic energy. The engineering literature described in this publication includes drawing, specifications, photographs, bill of materials, cost analysis, design criteria, psrts lists, and supporting textual data. This consolidated list m- cludes all materials originally announced in TM-4100, January 1957, and TID-4100, Supplement 1, July 1957, and additional engineering data received and cataloged by TlSE after the original issuances. The entire publication, TID-4100 lst Revision Supplement 1, is devoted to the Shippingport Pressurized Water Reactor. (W.L.H.)
Date: May 1, 1958
Partner: UNT Libraries Government Documents Department

Primary Plant Self-Actuated Relief Valve Operation. Core I, Seed 1. Test Results T-641100-B. Section 1

Description: Tests were made to insure the reliable operation of the self-actuated pressurized steam relief valves and the selfactuated reactor water relief valves within the prescribed pressure settings. Of the six valves tested, four operated within the prescribed operating pressure limitations. Since the actual popping pressure of the other two valves was close to the prescribed operating pressure limitation, no adjustments were made. (W.L.H.)
Date: October 1, 1960
Partner: UNT Libraries Government Documents Department

PERIODIC RADIATION SURVEY. CORE I, SEED 1. Section 3. Test Results T- 612394

Description: Radiation levels inside the concrete enclosures but outside the reactor plant containers after shutdown were determined. Radiation levels in the 1AC, 1BC boiler chamber enclosures and in the reactor chamber enclosure were on the average higher than in previous tests. The highest reading obtained was 7.5 mr/ hr and the lowest reading was 0.03 mr/hr; the mean level was 3.76 mr/hr as compared to 1.37 mr/hr in previous tests. (W.L.H.)
Date: June 17, 1960
Partner: UNT Libraries Government Documents Department

RADIATION LEVELS IN THE VICINITY OF THE PURIFICATION DEMINERALIZERS. CORE 1, SEED 1. Test Results T-641306

Description: BS>A test was performed to determine the activity build-up inside the 1AC and 1BD purification demineralizer concrete enclosure. A maximum radiation level of 1100 mr/hr was detected inside the 1AC demineralizer enclosure at a point 10.0 ft from the top. The maximum radiation level inside the 1BD enclosure was 700 mr/hr at a point 9.5 ft below the top. An analysis of data from five tests indicates that the extent of the activity build-up, as well as the level of activity, is definitely increasing. (W.L.H.)
Date: October 10, 1960
Partner: UNT Libraries Government Documents Department

PERIODIC REACTOR PLANT LEAK RATE TEST. CORE I, SEED 2. Test Results T- 641102

Description: An investigation was conducted to determine the magnitude of reactcr coolant leakage through the reactcr relief valve and the pressurizer relief valves. The pressurizer relief valve leak rate was not significantly different from that found in the previous performance test. The rate in the reactor relief valve decreased considerably. (J.R.D.)
Date: January 20, 1961
Partner: UNT Libraries Government Documents Department

LOAD DUMP TEST. CORE I, SEED 2. Test Results

Description: A test was conducted to determine the performance of the auxiliary govennor of the turbine-generator unit in instantaneous electrical load losses. The effect of the transient induced by such a loss of load on the Reactor Plant was also of interest. Results indicated proper governor operation, and favorable Reactor Plant response. (J.R.D.)
Date: January 31, 1961
Partner: UNT Libraries Government Documents Department

XENON TRANSIENT, 761.3 EFPH. CORE I, SEED 2. Section 1. Test Results T- 612081

Description: >Tests were conducted to determine if there is sufficient excess reactivity in the Shippingpont PWR to override a peak xenon transient and to obtain data for rod worth calculations. Upon completion of 761.3 EFPH of operation on core I, Seed 2, there was sufficient excess reactivity in the core to override the peak xenon transient which occurred 9 hr after station shutdown. At that time the controlling rod group (group II) was at a height of 38.43 in., while groupI rods were fully withdrawn and group-III ard -IV rods were fully inserted. The rod worth values for the groupII rods decreased with increasing EFPH for Core I, Seed 2, for the first 20 in. of rod withdrawal. (J.R.D.)
Date: December 1, 1960
Partner: UNT Libraries Government Documents Department

PERIODIC CALIBRATION OF TEMPERATURE SENSING ELEMENTS. CORE I, SEED 2. Test Results (T-641303-B)

Description: Tests were conducted to determine the direction and magnitude of any short- or long-term drift in core thermocouples, primary loop and pressurizer resistance thermometers, and resistance thermometers located in the secondary side of the boilers for Seed 2 at 2303 EFPH. It was found that drift in the core thermocouples is definite but random. Other findings are discussed and calibration data are presented graphically. (J.R.D.)
Date: April 14, 1961
Partner: UNT Libraries Government Documents Department

XENON TRANSIENT TESTS. CORE I, SEED 2, 149.8 EFPH. Section 1. Test Results T-612081

Description: A test was made to determine if there is sufficient excess reactivity in the core to override a peak xenon transient and to obtain dath for rod-worth calculations. After 149.8 EFPH's of plant operation on seed 2, there was sufficient excess reactivity to override peak xenon. Criticality during peak xenon was maintained with group III and group IV rods inserted, group I rods withdrawn to approximately -69 in., and group II rods withdrawn to approximately - 29 in. The override of peak xenon occurred 8 hr and 45 min after shutdown. (W.L.H.)
Date: October 25, 1960
Partner: UNT Libraries Government Documents Department

XENON TRANSIENT TESTS. CORE I, SEED 2. Section 1. Test Results T-612081

Description: A test was conducted to determine if sufficient excess reactivity exists in the core to override a peak xenon transient, and to obtain data for rod worth calculations. After completlon of 224.7 EFPH of plant operation with Core 1, seed 2 (5053.9 EFPH total Core I operation), there was sufficient reactivity to override the peak xenon transient imposed by a rapid station shutdown from an avernge reactor power level of 105.24%. Data on rod worth and other test results are included. (J.R.D.)
Date: January 30, 1961
Partner: UNT Libraries Government Documents Department