DYNAMIC RESPONSE OF REACTOR PLANT TO LOAD CHANGES. SECTION I. FIRST PERFORMANCE. CORE 1, SEED 1

Title: DYNAMIC RESPONSE OF REACTOR PLANT TO LOAD CHANGES. SECTION I. FIRST PERFORMANCE. CORE 1, SEED 1

Full Record
Other Related Research

Abstract

Studies were made to determine the responses of the plant when subjected to load transients exceeding the design magnitudes, and to determine the maximum load changes, positive or negative, that the plant can sustain. The reactor plant responded satisfactorily to all load changes. The only limits exceeded were the pressurizer high and low level alarm points. The magnitude of the transients and the time required for the plant to return to equilibrium was dependent upon the size of the load change. The pressurizer spray was effective in reducing reactor coolant pressure positive surges; however, this resulted in larger negative surges than when the spray valve was closed. (W.L.H.)

Publication Date:: Sun Nov 01 00:00:00 EST 1959

Research Org.:: Duquesne Light Co., Shippingport, Penna.

OSTI Identifier:: 4213806

Report Number(s):: AECU-4516

NSA Number:: NSA-14-004936

Resource Type:: Technical Report

Resource Relation:: Other Information: Test Results DL-S-250 (T-612390). Orig. Receipt Date: 31-DEC-60

Country of Publication:: Country unknown/Code not available

Language:: English

Subject:: REACTOR TECHNOLOGY; POWER; POWER PLANTS; PRESSURE; REACTIVITY; SHIPPINGPORT; TRANSIENTS; VARIATIONS

Citation Formats


                    . DYNAMIC RESPONSE OF REACTOR PLANT TO LOAD CHANGES. SECTION I. FIRST PERFORMANCE. CORE 1, SEED 1.  Country unknown/Code not available: N. p., 1959. 
        Web.

Copy to clipboard


                    . DYNAMIC RESPONSE OF REACTOR PLANT TO LOAD CHANGES. SECTION I. FIRST PERFORMANCE. CORE 1, SEED 1.  Country unknown/Code not available.

Copy to clipboard


                    . 1959.  
        "DYNAMIC RESPONSE OF REACTOR PLANT TO LOAD CHANGES. SECTION I. FIRST PERFORMANCE. CORE 1, SEED 1".  Country unknown/Code not available.

Copy to clipboard


                    
@article{osti_4213806,

  title        = {DYNAMIC RESPONSE OF REACTOR PLANT TO LOAD CHANGES. SECTION I. FIRST PERFORMANCE. CORE 1, SEED 1},

  author       = {},

  abstractNote = {Studies were made to determine the responses of the plant when subjected to load transients exceeding the design magnitudes, and to determine the maximum load changes, positive or negative, that the plant can sustain. The reactor plant responded satisfactorily to all load changes. The only limits exceeded were the pressurizer high and low level alarm points. The magnitude of the transients and the time required for the plant to return to equilibrium was dependent upon the size of the load change. The pressurizer spray was effective in reducing reactor coolant pressure positive surges; however, this resulted in larger negative surges than when the spray valve was closed. (W.L.H.)},

  doi          = {},

  url          = {https://www.osti.gov/biblio/4213806},
  journal      = {},
number       = ,

  volume       = ,

  place        = {Country unknown/Code not available},

  year         = {Sun Nov 01 00:00:00 EST 1959},

  month        = {Sun Nov 01 00:00:00 EST 1959}

}

Copy to clipboard

Technical Report:

Other availability

Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that may hold this item. Keep in mind that many technical reports are not cataloged in WorldCat.

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

DYNAMIC RESPONSE OF REACTOR PLANT TO LOAD SWINGS. CORE 1, SEED 2. Test Results T-643738

Technical Report

A test was conducted to determine the dynamic response of the reactor plant to load swings, the effects of magnitude and rate of load change on the plant, the effects of temperature coefficient and rod motion on various parameters during the transient, and the capability of the pressurizer spray to reduce the magnitude of positive pressure surges. Data on plant response are included. (J.R.D.)
Development of the ANL plant dynamics code and control strategies for the supercritical carbon dioxide Brayton cycle and code validation with data from the Sandia small-scale supercritical carbon dioxide Brayton cycle test loop.

Technical Report Moisseytsev, A; Sienicki, J

Significant progress has been made in the ongoing development of the Argonne National Laboratory (ANL) Plant Dynamics Code (PDC), the ongoing investigation and development of control strategies, and the analysis of system transient behavior for supercritical carbon dioxide (S-CO{sub 2}) Brayton cycles. Several code modifications have been introduced during FY2011 to extend the range of applicability of the PDC and to improve its calculational stability and speed. A new and innovative approach was developed to couple the Plant Dynamics Code for S-CO{sub 2} cycle calculations with SAS4A/SASSYS-1 Liquid Metal Reactor Code System calculations for the transient system level behavior onmore »« less
https://doi.org/10.2172/1040687

Full Text Available
RAPID STATION SHUTDOWN. CORE 1, SEED 2. Test Results T-643729

Technical Report

A test was made to determine the dynamic response of the reactor plant to a rapid station shutdown and to prepare the station for low-power physics testing. The reactor plant sustained a complete loss of station load at an average of 0.85 Mw/sec, using pressurizer spray, manual rod insertion, and the decay heat removal system to control the transient. The highest temperature recorded during the transient was a T/sub h/ of 521 deg F on the 1A loop 2.5 min after initiation of the shutdown. (W.L.H.)
LOSS OF LEVEL IN D/P CELL REFERENCE CHAMBERS. SECTION I. FIRST PERFORMANCE. CORE 1, SEED 1

Technical Report

Investigations were made to determine the reason for the decrease in the liquid levels of the reference chambers serving the reactor plant remote liquid level indicators. The remote gages and the local liquid level gages agreed closely for the Reactor Plant Component Cooling Water Expansion Tank and the Coolant Discharge and Vent System flash tank and blow-off tank. There appeared to be no loss of water from the D/P cell reference chambers for these two systems over the period of the test. There was no definite indication of leakage from the Valve Operating system reference chamber, however, the differences betweenmore »« less
PERIODIC REACTOR PLANT LEAK RATE TEST. CORE 1, SEED 2. Test Results T- 641102. First Issue, JUNE 14, 1961

Technical Report

Tests were performed on the Shippingport PWR to determine the magnitude and location of coolant system leakages. The total leakage from pressurizer relief and reactor relief valves was 62.1 gal/hr. The total plant leakage was 19.3 gal/hr. (T.F.H.)
https://doi.org/10.2172/4014030

Full Text Available

Similar Records