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Aerobic granular reactor





Encyclopedia results for Aerobic granular reactor

  1. S4G reactor

    Unreferenced stub auto yes date December 2009 The S4G reactor is a United States Naval reactor naval reactor used by the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on warship s. The S4G designation stands for S Submarine platform 4 Fourth generation Nuclear reactor core core designed by the contractor G General Electric was the contracted designer This nuclear reactor is the shipboard equivalent of the S3G reactor . It was installed in a dual configuration on the USS Triton SSRN 586 USS Triton SSRN 586 with two reactors and two five blade propellers, which was the first ship to make a submerged Operation Sandblast circumnavigation of the world. United States Naval reactor DEFAULTSORT S4g Reactor Category United States naval reactors Nuclear energy stub USN stub ...   more details



  1. S1B reactor

    unreferenced date August 2011 The S1B reactor is a United States Naval reactor naval reactor used by the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on SSBN X future follow on submarine OHIO Replacement Program submarine s. The S1B designation stands for S Submarine platform 1 First generation Nuclear reactor core core designed by the contractor B Bechtel Bechtel Marine Propulsion Corporation is the contracted designer This pressurized water reactor style nuclear reactor , designed by Knolls Atomic Power Laboratory , is designed to have increased energy density. This reactor is designed to operate for 40 years without refueling. References Reflist United States Naval reactor Category United States naval reactors Nuclear energy stub USN stub ...   more details



  1. Reactor vessel

    thumb right The reactor vessel used in the first commercial nuclear power plant, the Shippingport Atomic Power Station . Photo from 1956. In a nuclear power plant , the reactor vessel is a pressure vessel containing the Nuclear reactor coolant and Nuclear reactor core reactor core . Not all power reactors have a reactor vessel. Power reactors are generally classified by the type of coolant rather than by the configuration of the reactor vessel used to contain the coolant. The classifications are Light water reactor Includes the Pressurized water reactor PWR , Boiling Water Reactor BWR . Vast majority of nuclear power reactors are of this type. Graphite moderated reactor Includes the Chernobyl accident Chernobyl Reactor RBMK that has a highly unusual reactor configuration compared to the vast majority of nuclear powerplants in Russia or around the world. Gas cooled thermal reactor Includes the Advanced gas cooled reactor AGR , the Gas Cooled Fast Breeder Reactor or GCFR, and the High temperature gas cooled reactor HTGR . An example of a Gas Cooled Reactor is the British Magnox . Heavy water reactor Utilize heavy water, or water with a higher than normal proportion of the hydrogen ... as a main component, but not necessarily as a coolant in this case. An example of a heavy water reactor is Canada s CANDU reactor. Liquid metal cooled reactor Utilize a liquid metal, such as sodium or a lead bismuth alloy to cool the reactor core. Molten Salt Reactor Salts, typically fluorides of the alkali ... reactors with high temperatures and low pressures, reducing pressure exerted on the reactor vessel versus water steam cooled designs. Of the main classes of reactor with a pressure vessel, the PWR ... to extend its life. Annealing of PWR reactor vessels to extend their working life is a complex ... of PWRs. Components of a PWR Reactor Pressure Vessel PWR Nuclear Reactor Pressure Vessels share some features regardless of design. Reactor Vessel Body The reactor vessel body is the largest ...   more details



  1. S2W reactor

    Refimprove date December 2009 The S2W reactor is a United States Naval reactor naval reactor used by the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on warship s. The S2W designation stands for S Submarine platform 2 Second generation Nuclear reactor core core designed by the contractor W Westinghouse Electric 1886 Westinghouse was the contracted designer This nuclear reactor is the shipboard equivalent of the prototype S1W reactor , with minor design changes, that was installed on the USS Nautilus SSN 571 . As installed in Nautilus it generated convert 13400 hp MW . It was originally designated STR. ref cite book title Cold War submarines the design and construction of U.S. and Soviet submarines author Norman Polmar, Kenneth J. Moore publisher Brassey s ref After Nautilus was Ship decommissioning decommissioned , the reactor equipment was removed. The submarine is now moored and displayed as a museum ship at the Naval Submarine Base New London in Groton, Connecticut . References Reflist United States Naval reactor DEFAULTSORT S2w Reactor Category United States naval reactors Nuclear energy stub USN stub ...   more details



  1. S6W reactor

    Unreferenced stub auto yes date December 2009 The S6W reactor is a United States Naval reactor naval reactor used by the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on warship s. The S6W designation stands for S Submarine platform 6 Sixth generation Nuclear reactor core core designed by the contractor W Westinghouse Electric 1886 Westinghouse was the contracted designer This pressurized water reactor was prototyped in the land based S8G reactor S8G plant at Knolls Atomic Power Laboratory s Kesselring Site in Milton town , New York West Milton, NY starting in March 1994. It has a shaft horsepower of 45,000 shp. The three ships of the Seawolf class submarine Seawolf SSN 21 class Seawolf class submarine were built with S6W reactors. United States Naval reactor DEFAULTSORT S6w Reactor Category United States naval reactors Nuclear energy stub USN stub pl S6W Advanced Fleet Reactor ...   more details



  1. D1G reactor

    Unreferenced date December 2009 The D1G reactor was a prototype United States Naval reactor naval reactor designed for the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on warship s. The D1G designation stands for D Destroyer platform 1 First generation Nuclear reactor core core designed by the contractor G General Electric was the contracted designer This prototype nuclear reactor was constructed for the United States Department of Energy s Office of Naval Reactors as part of the Naval Nuclear Propulsion Program. The reactor was built by General Electric and operated by the Knolls Atomic Power Laboratory at the Kesselring Site Operation in Milton town , New York West Milton, New York . It was used for testing components and as a training tool for the Nuclear Power Training Unit. The reactor operated from 1962 to 1996, when it was shut down in March of that year. It was later defuelled, with the pressure vessel eventually removed in 2002. The reactor vessel containment vessel which housed both the primary nuclear reactor and secondary steam plant systems is referred to as the DIG ball due to its unique shape a Horton Sphere . The sphere was originally constructed by Chicago Bridge and Iron Works to house the liquid metal cooled reactor of the USS Seawolf SSN 575 USS Seawolf SSN 575 , with the dome designed to contain a liquid sodium explosion. United States Naval reactor DEFAULTSORT D1g Reactor Category United States naval reactors Category Domes Nuclear energy stub USN stub ...   more details



  1. S2G reactor

    Unreferenced stub auto yes date December 2009 S2G redirects here. For the aircraft, see Grumman S 2 Tracker The S2G reactor was a United States Naval reactor naval reactor used by the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on warship s, and the only liquid metal cooled reactor yet deployed by the US Navy. The S2G designation stands for S Submarine platform 2 Second generation Nuclear reactor core core designed by the contractor G General Electric was the contracted designer An S2G was the initial power plant of USS Seawolf SSN 575 USS Seawolf SSN 575 . This was one of three sodium cooled fast reactor s ordered for the Seawolf program at the same time as three PWR units were ordered to support the USS Nautilus SSN 571 USS Nautilus SSN 571 program In each case, one reactor was land based for training and research, one intended for installation on a submarine, and one spare. The land based unit corresponding to S2G was S1G reactor . Persistent superheater problems on Seawolf caused the superheaters to be bypassed, resulting in mediocre performance. This and concern for the dangers posed by liquid sodium coolant led to the PWR type being selected instead as the standard US naval reactor type, and the S2G on Seawolf was replaced by the spare S2Wa reactor from the Nautilus program. United States Naval reactor DEFAULTSORT S2g Reactor Category United States naval reactors Category Liquid metal fast reactors Nuclear energy stub USN stub ...   more details



  1. Granular cell tumor

    Infobox Disease Name Granular cell tumor Image Granular Cell Tumor.jpg Caption 2 cm tumor presented as an abdominal wall mass in a middle aged woman DiseasesDB ICD10 D36.1 ILDS D36.170 ICD9 ICDO ICDO 9582 0 OMIM MedlinePlus eMedicineSubj eMedicineTopic MeshID File Granular cell tumor 3 skin.jpg thumb Histopathologic image of granular cell tumor of the skin Granular cell tumor is a tumor that can develop on any skin or mucosal surface, but occurs on the tongue 40 of the time. It is also known as Abrikossoff s tumor , ref name Bolognia Granular cell myoblastoma , ref name Bolognia Granular cell nerve sheath tumor , ref name Bolognia and Granular cell schwannoma . ref name Bolognia cite book author Rapini, Ronald P. Bolognia, Jean L. Jorizzo, Joseph L. title Dermatology 2 Volume Set publisher Mosby location St. Louis year 2007 pages 1796, 1804 isbn 1 4160 2999 0 oclc doi accessdate ref Pathology Granular cell tumors show similarity to neural tissue, as can be demonstrated by immunohistochemistry and ultrastructural evidence using electron microscopy . Multiple granular cell tumors may seen ... first4 DG. last5 McGillivray first5 BC. title Multiple granular cell tumors are an associated feature ... 9 month Feb year 2009 doi 10.1111 j.1399 0004.2008.01100.x PMID 19054014 ref Epidemiology Granular ... 10 . ref Kahn, Michael A. Basic Oral and Maxillofacial Pathology. Volume 1. 2001. ref Granular ... lysosomes in the cytoplasm . Granular cell tumors are typically solitary and are rarely larger than ... is rare and comprises only 2 of all granular cell tumors. ref Fanburg Smith JC, Meis Kindblom JM, et al. Malignant granular cell tumor of soft tissue diagnostic criteria and clinicopathologic correlation ... for malignant lesions. Benign granular cell tumors have a recurrence rate of 2 to 8 when resection margin s are deemed clear of tumor infiltration. When the resection margins of a benign granular ... and appendages by morphology DEFAULTSORT Granular Cell Tumor Category Oral neoplasia Category Dermal ...   more details



  1. S1G reactor

    Unreferenced date December 2009 The S1G reactor is a United States Naval reactor naval reactor used by the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on warship s. The S1G designation stands for S Submarine platform 1 First generation Nuclear reactor core core designed by the contractor G General Electric was the contracted designer This nuclear reactor was constructed by General Electric as a prototype for the USS Seawolf SSN 575 USS Seawolf SSN 575 submarine. It was a liquid metal cooled reactor using pure sodium to cool the core instead of water, because the higher temperature of liquid sodium compared to pressurized water enabled the production of more superheated steam in the Steam generator nuclear power steam generators . This resulted in a more efficient thermal cycle, yielding more Horsepower Shaft horsepower shaft horsepower for a given reactor size. The reactor design had problems because of limited operating temperature constraints. The major disadvantage of this concept was the ignition of sodium when exposed to air. S1G was used for testing and training. Eventually a sodium leak resulted in a fire, and the facility was shut down. In the meantime, the S1W reactor S1W and S2W reactor S2W pressurized water reactor s, conceived for the USS Nautilus SSN 571 USS Nautilus SSN 571 , had demonstrated their superior reliability. The S1G reactor facility and its Horton Sphere were later reused for the D1G reactor D1G prototype destroyer reactor. United States Naval reactor DEFAULTSORT S1g Reactor Category United States naval reactors Category Liquid metal fast reactors Nuclear energy stub USN stub ...   more details



  1. Hybrid reactor

    See Hybrid nuclear fusion for the proposed nuclear reactor. Unreferenced stub auto yes date December 2009 A hybrid reactor is an anaerobic digester that combines a UASB reactor with an anaerobic filter . This combination is an advanced form enabling improved solid retention time in the treatment of waste water. See also Anaerobic digester types Environmental technology DEFAULTSORT Hybrid Reactor Category Anaerobic digester types Waste stub ...   more details



  1. Arc reactor

    Arc reactor may refer to an apparatus for producing Buckminsterfullerene C sub 60 sub and other fullerenes , with or without metal doping Plasma arc waste disposal reactor, a kind of waste processing system Iron Man s armor Arc reactor Arc reactor , the fictional power source in the Iron Man film powering not only an electromagnet keeping shrapnel out of Tony Stark s heart, but also the Iron Man suit of armor disambig ...   more details



  1. Reactor operator

    A reactor operator or nuclear reactor operator is an individual at a nuclear power plant who is responsible for directly controlling a nuclear reactor from a control panel and is the only individual at a nuclear power plant who can directly alter significant amounts of reactivity nuclear reactor reactivity . The reactor operator occupies a position of great responsibility that may require him or her to start up a nuclear reactor, shut down a critical mass critical nuclear reactor, monitor reactor parameters, or respond to a casualty of the nuclear reactor. All reactor operators are required to be licensed ... naval reactors . United States Civilian Reactor Operator Licensing There are two types of civilian reactor operators licensed by the NRC reactor operators RO and senior reactor operators SRO . ref cite ... ref Reactor Operator A reactor operator is an individual who has met the licensing requirements of 10 CFR 55 and NUREG 1021 for being a reactor operator. These requirements include A high school ... power plant where the individual is licensed Completion of the nuclear power plant s reactor operator training program Supervised manipulation of the controls of the nuclear reactor for certain operations affecting reactor power level A successful medical examination meeting NRC requirements Passing the NRC Generic Fundamentals Examination Passing the nuclear power plant s reactor operator test ... and plant evolutions in an approved simulator. A reactor operator is licensed to manipulate the controls of a nuclear reactor which may alter reactivity and change the power level. Typically, this means that a reactor operator is qualified to remotely operate control rods and other remote actions required to control the reactor as desired within regulatory requirements . Senior Reactor Operator A senior reactor operator is an individual who has met the licensing requirements of 10 CFR 55 and NUREG 1021 for being a senior reactor operator. These requirements are similar to the requirements for a reactor ...   more details



  1. Reactor building

    Unreferenced auto yes date December 2009 Orphan date December 2009 A reactor building is a general term for a building that houses a reactor of some type. In particular, it often refers to a building containing a nuclear reactor . This can also be used to refer to pressure sealed buildings containing nuclear reactor s, though it would be more correct to call them containment building s. Although some buildings containing nuclear reactor s are containment building s, not all are. For instance, the Soviet RBMK reactors were not housed in containment building s. This greatly increased the severity of the Chernobyl accident on April 26, 1986. See also List of nuclear reactors Category Nuclear power plant components DEFAULTSORT Reactor Building Nuclear energy stub ...   more details



  1. KN-3 reactor

    Unreferenced date December 2009 The KN 3 reactor is the nuclear fission nuclear reactor reactor used in pairs to power the Kirov class battlecruiser Kirov class battlecruisers . The reactor was also intended to be used on the Soviet aircraft carrier Ulyanovsk Ulyanovsk class of supercarrier s. It is a pressurized water reactor PWR , using enriched uranium enriched uranium 235 fuel to produce megawatt 300 MW of power. DEFAULTSORT Kn 3 Reactor Category Soviet naval reactors Category Pressurized water reactors Navy stub Nuclear energy stub Soviet stub de Kirow Klasse Antrieb ...   more details



  1. Halden Reactor

    File Haldenreaktoren.jpg thumb right 300 px From the Halden Reactor nuclear plant The Halden Reactor is a nuclear reactor located in Halden , Norway and dedicated for research. The reactor became operative in 1958, and is operated by the Institute for Energy Technology . The reactor is a Boiling water reactor BWR moderated by heavy water . ref name snl cite encyclopedia title Haldenreaktoren first Trygve last Holtebekk first2 Magne last2 Guttormsen encyclopedia Store norske leksikon editor Henriksen, Petter publisher Kunnskapsforlaget location Oslo url http www.snl.no Haldenreaktoren language Norwegian accessdate 19 March 2011 ref References Reflist coord missing Norway Category Nuclear energy in Norway Category Buildings and structures in stfold Category Nuclear reactors no Haldenreaktoren ...   more details



  1. S8G reactor

    The S8G reactor is a United States Naval reactor naval reactor used by the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on warship s. The S8G designation stands for S Submarine platform 8 Eighth generation Nuclear reactor core core designed by the contractor G General Electric was the contracted designer This nuclear reactor utilizes natural circulation ref cite web url http ship.bsu.by main.asp?id 100092 title accessdate 2006 03 12 language Russian ref ref cite web url http www.submarinesonstamps.co.il openhist.php?ID 269 title The Ohio, US Navy s nuclear powered ballistic missile submarine accessdate 2006 03 12 archiveurl http web.archive.org web 20060720075350 http www.submarinesonstamps.co.il openhist.php?ID 269 Bot retrieved archive archivedate 2006 07 20 ref ref cite web url http tech.military.com equipment viewEquipment.do?eq id 89213 title Military.com Equipment Guide registration required accessdate 2006 03 12 quote ...relying on...natural circulation reactor.... ref which is capable of operating at a significant fraction of full power without reactor coolant pump s. The S8G reactor was designed by General Electric for use on the Ohio class submarine Ohio class SSGN SSBN 726 class submarines. A land based prototype of the reactor plant was built at Knolls Atomic Power Laboratory s Kesselring Site in Milton town , New York West Milton, NY . The prototype was used for testing and crew training throughout the 1980s. In 1994, the core was replaced with an S6W reactor , designed for the then new ... with a automatic reactor fill system that can flood the reactor compartment with borated water in the event of a loss of coolant accident, or electric power failure to the reactor. References references United States Naval reactor nuclear energy stub USN stub Category United States naval reactors no S8G atomreaktor pl S6W Advanced Fleet Reactor ...   more details



  1. VM reactor

    The various types of the VM reactor series are nuclear fission nuclear pressurized water reactor s PWR . They are used singly or in pairs to power the Soviet Navy s submarine s. Series The VM A reactor was the nuclear fission nuclear reactor reactor used in pairs to power the Soviet Navy s Project 658 and 701 Hotel class submarine Hotel , Project 659 and 675 Echo class submarine Echo , and Project 627 November class submarine November first generation submarines. It was a pressurized water reactor PWR , using 20 enriched uranium enriched uranium 235 fuel to produce megawatt 70 MW of power. This is the reactor that powered the Soviet submarine K 19 K 19 . The VM 4 reactor is a nuclear fission nuclear reactor reactor using 20 enriched uranium enriched uranium 235 fuel to produce 70 90 megawatt MW of power. It is used singly to power the Project 670 and Charlie class submarine Charlie submarines in pairs to power the Project 671 and Victor class submarine Victor , Project 667 , , and Delta class submarine Delta , and Project 667 , , , and Yankee class submarine Yankee second generation submarines. The VM 5 reactor was the nuclear fission nuclear reactor reactor used in a pair to power the Soviet Navy s Project 661 Papa class submarine Papa second generation submarine. It was a pressurized water reactor PWR using enriched uranium enriched uranium 235 fuel to produce megawatt 177 MW of power. nuclear energy stub submarine stub Category Soviet naval reactors Category Pressurized water reactors de WM Reaktor ru ...   more details



  1. Dragon reactor

    Dragon was a high temperature gas cooled reactor at Winfrith in England operated by UKAEA . Its purpose was to test fuel and materials for the European high temperature reactor programme, and was built and managed as an Organisation for Economic Co operation and Development OECD Nuclear Energy Agency NEA international project. Dragon used helium gas as coolant and coated particle fuel. ref Rainer Simon, http www.iasmirt.org iasmirt 2 SMiRT18 S05 2.pdf The Primary Circuit of the Dragon High Temperature Reactor Experiment , 18th International Conference on Structural Mechanics in Reactor Technology, August 2005 ref The Dragon complex consists of the reactor and various buildings constructed in the late 1950s early 1960s to support operations. The reactor is presently in care and maintenance. Construction started in 1959 and was completed in 1962. Operation started in 1965 with a power output of 20MW. The reactor operated until 1976 and was partially decommissioned in 2005. ref http www.nda.gov.uk stakeholders newsletter winfrith dragon.cfm?renderforprint 1& ref References reflist coord 50.6840 2.2694 type landmark region GB display title Category Nuclear research reactors nuclear energy stub ...   more details



  1. S4W reactor

    The S4W reactor is a United States Naval reactor naval reactor used by the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on warship s. The S4W designation stands for S Submarine platform 4 Fourth generation Nuclear reactor core core designed by the contractor W Westinghouse Electric 1886 Westinghouse was the contracted designer This nuclear reactor was a variant of the Submarine Fleet Reactor SFR with the horizontal steam generator nuclear power steam generator s pioneered in S1W reactor S1W and S2W reactor S2W . Two boats of the Skate class submarine Skate class were built with S4W reactors USS Swordfish SSN 579 USS Swordfish SSN 579 ref SSN579 and USS Seadragon SSN 584 USS Seadragon SSN 584 ref SSN584 . During later overhauls, the S4W reactors in both subs were replaced with S5W reactors ref attack . References div class references small note SSN579 http navysite.de ssn ssn579.htm navysite.de USS Swordfish SSN 579 note SSN584 http navysite.de ssn ssn584.htm navysite.de USS Seadragon SSN 584 note attack http www.combatindex.com hardware hardware sea sub ssn main.html CombatIndex.com Nuclear Attack Submarines div United States Naval reactor nuclear energy stub USN stub Category United States naval reactors ...   more details



  1. CIRUS reactor

    CIRUS Canada India Research Utility Services is a research nuclear reactor reactor at the Bhabha Atomic Research Center BARC in Trombay near Mumbai , India . CIRUS was supplied by Canada in 1954, but uses heavy water deuterium supplied by the United States . It is the second oldest reactor in India. It is modeled on the Canadian Chalk River NRX National Research X perimental NRX reactor. ref name nti cite web title Canadian Indian Reactor, U.S. CIRUS work Nuclear Threat Initiative url http www.nti.org e research profiles India Nuclear 2103 2603.html accessdate 2007 04 09 Dead link date October 2010 bot H3llBot ref The 40  MW reactor burns natural uranium fuel, while using heavy water as a neutron moderator moderator . ref name barc cite web title CIRUS REACTOR work Bhabha Atomic Research Center url http www.barc.ernet.in webpages reactors cirus.html accessdate 2007 04 09 ref It is a tank reactor type with a core size of 3.14  m H 2.67  m D . It first went critical mass critical July 10, 1960. ref name barc The reactor is not under IAEA safeguards which did not exist when the reactor was sold , although Canada stipulated, and the U.S. supply contract for the heavy water explicitly ... nuclear test. ref name gulfnews cite news last Gopal first Neena title PM to announce Cirus reactor ... operation in 2003. The reactor was brought back into operation two years late in 2005. During refurbishing, a low temperature vacuum evaporation based desalination unit was also coupled to the reactor to serve as demonstration of using waste heat from a research reactor for sea desalination. Even if the reactor has a life of twenty more years, India had declared that this reactor would be shut ... The reactor was shut down on 31 December 2010. ref name dnaindia cite news title Research N reactor ... mumbai report research n reactor cirus to shutdown permanently on december 31 1482987 ... 28 N 72 55 07 E display title DEFAULTSORT Cirus reactor Category Canada India relations Category Nuclear ...   more details



  1. VT-1 reactor

    Unreferenced stub auto yes date December 2009 The VT 1 reactor was the nuclear fission nuclear reactor reactor used in a pair to power Soviet submarine K 27 as part of the Soviet Navy s Project 645 . It is a liquid metal cooled reactor LMR , using enriched uranium highly enriched uranium 235 fuel to produce 73 megawatt MW of power. K 27 was a November class submarine November class first generation nuclear submarine, and the only one of its class fitted with liquid metal cooled reactors. However the seven member Alfa class submarine Alfa class were subsequently fitted with liquid metal cooled reactors. DEFAULTSORT Vt 1 Reactor Category Soviet naval reactors Category Liquid metal fast reactors Submarine stub Nuclear energy stub ...   more details



  1. OK-550 reactor

    The OK 550 reactor is the nuclear fission nuclear reactor reactor used to power three of the seven boats of the Soviet Navy s Project 705 Lira or Alfa class submarine Alfa in NATO designation fourth generation submarines. It is a liquid metal cooled reactor LMR , using enriched uranium highly enriched uranium 235 fuel to produce megawatt 155 MWt of power. OK 550 has three separate steam circulation loops, and was used in the boats built at Severodvinsk . See also BM 40A reactor External links http www.fas.org man dod 101 sys ship row rus 705.htm Project 705 Lira Alfa class at the Federation of American Scientists website. Category Soviet naval reactors Category Liquid metal fast reactors submarine stub nuclear energy stub ...   more details



  1. Maria reactor

    Image Reaktor Maria w Swierku.jpg thumb right The Maria reactor Image Reaktor Maria w czasie budowy.jpg thumb right The reactor during construction Image Reaktor11.jpg thumb rigth Cherenkov radiation viewed in the interior of the Maria reactor The Maria reactor is Poland s second research nuclear reactor and the only one still in use. It is located at wierk Otwock , near Warsaw and named in honor of Maria Sk odowska Curie . It is the only reactor of Polish design. Maria is a multifunctional research tool, with a notable application in production of radioisotope s, research with utilization of neutron beams, neutron therapy , and neutron activation analysis . It operates about 4000 hours annually, usually in blocks of 100 hours. Technical description The technical details of the reactor are given in the reference. ref Reaktor Maria at the website of the Polish Institute of Atomic Energy pl Instytut Energii Atomowej POLATOM http www.cyf.gov.pl reaktor ang.html English http www.iea.cyf.gov.pl reaktor.html Polish ref Maria is a pool reactor pool type reactor with a power of 20 to 30 MW thermal . Despite it being a pool reactor, it contains channels aluminum tubes individually connected to the primary coolant. The water pool provides cooling for elements e.g., fuel elements that are not otherwise ... can be viewed. The reactor is housed in a Containment building sealed containment . History Construction began on June 16, 1970 and the reactor was activated on December 18, 1974. With the shutdown of the Ewa reactor in 1995 it became Poland s only research nuclear reactor. Production of medical radioisotopes ... ease the isotope shortages due to shutdowns of the Canadian National Research Universal Reactor NRU reactor and the Dutch Petten nuclear reactor ref Adam Wawrzy ski, Reaktor Maria ratuje wiat ... reactor List of nuclear reactors References Reflist Commons category Maria Reactor Poland stub coord 52.1228 N 21.3439 E source kolossus plwiki display title DEFAULTSORT Maria Reactor Category Nuclear ...   more details



  1. A3W reactor

    The A3W reactor is a United States Naval reactor naval reactor used by the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on warship s. Like all operational U.S. naval reactors it was a pressurized water reactor PWR design. The A3W designation stands for A Aircraft carrier platform 3 Third generation Nuclear reactor core core designed by the contractor W Westinghouse Electric 1886 Westinghouse was the contracted designer The reactor was intended for use aboard USS John F. Kennedy CV 67 USS John F. Kennedy . This four nuclear reactor reactor design was intended to reduce the cost involved in the construction and operation, as compared with the USS Enterprise CVN 65 Enterprise and its eight nuclear reactors. Early in the construction, the United States Secretary of the Navy had the plans changed to save money, and fossil fuel boilers were installed on the Kennedy. Because the plans for the ship did not include a funnel ship funnel , the funnel on the Kennedy protrudes out from the ship at an angle. The return to nuclear power for carriers came with the Nimitz class aircraft carrier Nimitz class s A4W reactor s two reactor per ship design. While the two reactor configuration, with each core providing a much greater thermal output, is relatively less expensive than earlier designs, the power plant still represents about half the total cost of the ship. United States Naval reactor Category United States naval reactors Category Articles lacking sources from June 2009 Category All articles lacking sources nuclear energy stub USN stub ar A3W ...   more details



  1. S6G reactor

    The S6G reactor is a United States Naval reactor naval reactor used by the United States Navy to provide electricity generation and Nuclear marine propulsion propulsion on warship s. The S6G designation stands for S Submarine platform 6 Sixth generation Nuclear reactor core core designed by the contractor G General Electric was the contracted designer This nuclear reactor was designed by General Electric for use on the Los Angeles class submarine Los Angeles class attack submarines. The S6G reactor plant consists of the reactor coolant , Steam generator nuclear power steam generation , and other support systems that supply steam to the engine room. The 688 class engine room also contains the steam turbine s that generate electricity and drive the Propeller Marine propeller shaft. ref http www.fas.org man dod 101 sys ship eng reactor.html Nuclear Propulsion ref While exact specifications are classified, the S6G reactor can propel a Los Angeles class submarine at over convert 15 kn km h when surfaced and over convert 25 kn km h while submerged. Design and operational support for the S6G is provided by Knolls Atomic Power Laboratory KAPL . ref http www.knollslab.com whatwedo.html KAPL What We Do ref The S6G reactor plant was originally designed to use the D1G reactor D1G 2 core , similar to the D2G reactor used on the Bainbridge class cruiser Bainbridge class guided missile cruiser, which is rated at 148 Megawatt MW . All Los Angeles class submarines from USS Providence SSN 719 on were built with a D2W core rated at 165 MW, as opposed to the older 150 MW cores found on older ships. The D1G 2 cores are being replaced with D2W cores when the ships are refueled. References Reflist United States Naval reactor nuclear energy stub USN stub Category United States naval reactors no S6G atomreaktor pl Reaktor S6G ...   more details




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