83 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Shippingport"  
Results: 1 - 24 next
open access

Reactivity Lifetime. Test Results DL-S-225(T-612118). Section I, First Performance

Description: The performance, reliability, and reactivity lifetime of the Shippingport PWR are determined under normal steady state conditions. These characteristics are studied over a period of 1011 EFPH, at a power level of about 60 Mw(e). Flux tilts that occurred during this time, as well as the means employed for their suppression, are described. (T.F.H.)
Date: October 24, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Modified Purification System Performance Test. Core 1, Seed 2. Test Results T-641124-A. Section 2

Description: The effectiveness of purification in controlling plant radioactivation rates was determined through comparison of the actual effects produced from plant operation with and without purification. With the purification system in service, there was no appreciable difficulty in maintaining the reactor coolant within reference water specifications. In addition, there was no discernible increase of crud deposition in the coolant system as determined by direct radiation measurements of the purification… more
Date: July 21, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hydrogen Distribution and Leak Rate From the Reactor Coolant System. Test Evaluation-RNI-31A

Description: Hydrogen is injected into the coolant to a concentration of about 60 cc/ kg. The decrease in H concentration is measured as a function of time, and of the point of addition. The H may be added at the inlet or outlet sides of eithe: of two ion exchangers. The decontamination factors of these ion exchangers are not affected by the presence of the H. The time required for the H concentration to drop to half its original value varies between 118 and 172 hr. (T.F.H.)
Date: August 1, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

REACTIVITY LIFETIME. TEST RESULTS DL-S-225(T-612118A). Section I, Second Performance

Description: The performance, reliability, stability, and reactivity lifetime variations of the Shippingport PWR are determined under normal steady state conditions. These characteristics are studied over a period of 758 EFPH, at a power level of about 60 Mw(e). Flux-tilt corrections and plant operations during this time are described. (T.F.H.)
Date: March 1, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radiation Levels in the Vicinity of the Purification Demineralizers. Core 1, Seed 2. Test Evaluation T-641306

Description: Measurements were made to determine the extent of activity build-up inside the 1 AC and 1 BD punification demineralizer concrete enclosures. Radiation levels were obtained at 6-in. intervals from 6 to 17.5 ft below the top of the concrete shield on the 1 AC demineralizer and from 0.5 tc 24.5 ft on the 1 BD dendneralizer by lowering the probe through the 3-in. pipe on top of the concrete enclosure. The results indicated that the long-lived activity in the purification demineralizers had decrease… more
Date: May 25, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Measurements of Dissolved Hydrogen Concentration. Core I, Seed 1. Test Results T-612395-A

Description: Measurements were undertaken to compare the performance of a hydrogen- palladium diffusion coil to a palladium resistance wire assembly in measuring hydrogen concentration and to obtain data to evaluate a Swartout Palladium Resistance Gage electronic readout unit. No comparison could be made since the instruments were never in satisfactory service at the same time. The data taken with each instrument are compared with data determined by laboratory analysis. A review of the data indicated that t… more
Date: October 17, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Controlled Safety Test Rod Withdrawal Transients (During Start-Up). Core I, Seed 2. Efph-8054.1 Core 1 (Total) 2248.0 Seed 2. Section 1. Test Results T-612393-C

Description: Tests were conducted to obtain data on the dynamic response of the Reactor Plant to various startup rod withdrawal transients. Results were compared with those obtained in simulator studies. (auth)
Date: January 31, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Valve Operating System Performance Test. Core 1, Seed 2. Test Results T- 641114

Description: A test was run on the Shippingport Pressurized Water Reactor on June 15, 1960, to determine whether or not the pressure snd water flask volume of the valve operating system are sufficient to meet requirements under both normal and emergency conditions. The system was found to be satisfactory. A two-hour leak test indicated leakage. (D.L.C.)
Date: March 14, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Periodic Calibration of Temperature Sensing Elements. Core 1, Seed 1. Test Results T-641303

Description: A test was made to determine the direction and magnitude of any drift in the temperature-sensing elements and the receiver-indicating units for the reactor coolknt loop and pressurizer resistance thermometers. A test was also made to determine the difference between the measured value of the neutron flux with the reactor shut down, as determined by BF/sub 3/ counters, and the neutron flux due to the Po-Be source. (W.L.H.)
Date: May 29, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Primary Plant Self-Activated Relief Valve Operation. Core I, Seed 2. Section 1. Test Results T-641100-B

Description: The operation of self-actuated pressurizer steam relief valve of the Shippingport PWR was tested within a prescribed setting of 2300 plus or minus 50 psig. The valve popped at 2265 psig and reseated at 2190 psig, with a time lapse of 12.9 seconds between popping and reseating. Leak rates before and after popping of the valve were 0.70 gallons/ hour and 1.35 gallons/hour, respectively. The valve performed reliably in that it popped within the prescribed setting and reseated with no observable va… more
Date: March 13, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Examination of Components for Crud and Corrosion 1-B Heat Exchanger Handhole Area. Core I, Seed 1. Test Results T-612080

Description: The extent and location of corrosion, crud deposits, and defects in the ends of the 1-B heat exchanger after removing the handhole covers were determined. There was no visual evidence of pitting or corrosion inside the ends of the heat exchanger. A radiochemical analysis of a smear sample taken from the inside of number one handhole showed the presence of the following isotopes- Fe/sup 59/, Co/ sup 58/, s1>s, and Zr/sup 95/. A radiation survey performed in four handholes indicated a maximum lev… more
Date: October 16, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

RADIATION SURVEY OF BEWI AND ASEWI REFUELING. CORE 1, SEED 1. Test Results T-643709

Description: The radiation survey of the Blanket Exit Water Instrumentation assemblies Core I, Seed 1 was performed on January 15 and 16, 1960, approximately 100 days after reactor shutdown at 5806 EFPH. The observed radiation levels varied with height from 150 to 500 mr/hr; the highest activity was found at the bottom of both support tubes of each of the four assemblies monitored, which, in operation, would be located 5 in. above the top of the blanket fuel assembly. The two inner port Blanket Exit Water I… more
Date: April 24, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Shipping Container Test. Core I, Seed 1. Section 1. Test Results T-643717-A

Description: A test was performed at the Shippingport PWR, whose purpose was to determine the amount of heat the fuel shipping container cooling system was capable of removing while in a state of equilibrium. Studies were also conducted to determine if after four hours of operation, the increase of the internal wall temperature was less than 30 deg F, and finally, to determine the effects of loss of cooling water from the fuel shipping container. (auth)
Date: April 24, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Control Rod Drive Mechanism, Precritical and Initial Critical Tests. Core I, Seed 2. Section 2. Test Results T-550010

Description: The control rod drive mechanisms and associated instrumentation in the Shippingport PWR were in satisfactory operating condition. Deficiencies that were observed during the test and subsequently corrected were: no positive indication of movement in rods 11, 82, 62, 53, and 14, as shown on the rod position indicating lights; and the bottom indicator coil for rod 81 was connected improperly. After the deficiencies were corrected, the test was rerun for the rods in question and all operated satisf… more
Date: June 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Examination of Components for Crud and Corrosion. Core I, Seed 2. Test Results T-612080

Description: >An examination was made to observe the extent and location of corrosion, crud deposits, and defects in components of the PWR pnimary fluid system and its auxiliaries. A gamma spectrum of the four-inch line upstream from the two pressurizer self-actuated relief valves showed the presence of Mn/sup 54/ and Co/sup 60/. From the gamma spectrum and the gross gamma activity, the Co/sup 60/ was found to be 5.03 x 10/sup 3/ dpm/mg or about 70 per cert of the gross gnmma activity. (J.R.D.)
Date: January 20, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen