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contributor authorR. Vijayashree
contributor authorR. Veerasamy
contributor authorSudheer Patri
contributor authorP. Chellapandi
contributor authorG. Vaidyanathan
contributor authorS. C. Chetal
contributor authorBaldev Raj
date accessioned2017-05-09T00:37:31Z
date available2017-05-09T00:37:31Z
date copyrightOctober, 2010
date issued2010
identifier issn1528-8919
identifier otherJETPEZ-27138#102921_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/143091
description abstractPrototype fast breeder reactor is U–PuO2 fueled sodium cooled pool type fast reactor and it is currently under construction at Kalpakkam, India. Prototype fast breeder reactor is equipped with two independent fast acting and diverse shutdown systems. A shutdown system comprises of sensors, logic circuits, drive mechanisms, and neutron absorbing rods. The two shutdown systems of prototype fast breeder reactor are capable of bringing down the reactor to cold shutdown state independent of the other. The absorber rods of the second shutdown system of prototype fast breeder reactor are called as diverse safety rods (DSRs) and their drive mechanisms are called as diverse safety rod drive mechanisms (DSRDMs). DSRs are normally parked above active core by DSRDMs. On receiving scram signal, the electromagnet of DSRDM is de-energized and it facilitates fast shutdown of the reactor by dropping the DSR into the active core. For the development of prototypes of DSR and DSRDM, three phases of testing, namely, individual component testing, integrated functional testing in room temperature, and endurance testing at high temperature sodium, were done. The electromagnet of DSRDM has been separately tested at room temperature, in furnace, and in sodium. Specimens simulating the contact conditions between electromagnet and armature of DSR have been tested to rule out self-welding possibility. The prototype of DSR has been tested in flowing water to determine the pressure drop and drop time. The functional testing of the integrated prototype DSRDM and DSR in aligned and misaligned conditions in air/water has been completed. The performance testing of the integrated system in sodium has been done in three campaigns. During the third campaign of sodium testing, the performance of the system has been verified with 30 mm misalignment at various temperatures. The third campaign has qualified the system for 10 years of operation in reactor. This paper presents design, development, testing, and qualification of the prototype DSR and DSRDM. Salient design specifications for both DSRDM and DSR are listed initially. The conceptual and detailed design features are explained with the help of figures. Details on material of construction are given at appropriate places. Test plans and criteria for endurance testing in sodium for qualification of DSRDM and DSR for operation in reactor are briefed. Brief explanation of test setups and typical test results are also given.
publisherThe American Society of Mechanical Engineers (ASME)
titleDesign, Development, Testing and Qualification of Diverse Safety Rod and Its Drive Mechanism for a Prototype Fast Breeder Reactor
typeJournal Paper
journal volume132
journal issue10
journal titleJournal of Engineering for Gas Turbines and Power
identifier doi10.1115/1.4001059
journal fristpage102921
identifier eissn0742-4795
keywordsEngineering prototypes
keywordsDesign
keywordsTesting
keywordsElectromagnets
keywordsMechanisms
keywordsSodium
keywordsSafety AND Water
treeJournal of Engineering for Gas Turbines and Power:;2010:;volume( 132 ):;issue: 010
contenttypeFulltext


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