2012 trek fuel ex 7 specs

2012 Trek Fuel EX 7 Bike (discontinued)

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2012 Trek Fuel EX 9.7 E

A 26″ carbon frame full suspension trail bike with high-end components.

For This Bike

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A bike with lower gearing will be easier to ride up steep hills, while a higher top end means it will pedal faster down hills.

Fuel EX 9.7 E

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5'0" – 5'7"

5'5" – 5'11"

5'9" – 6'3"

6'1" – 6'6"

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• 5'10", size L, Fits large

Jul 2013 · Jenn Hill

Jenn's long termer of choice this year is Trek's Fuel EX 9.8.

Read Review

Jan 2013 · Dirt HQ

Here’s a bike that looks good and has been made into a bike that’s fun to ride, the 2013 Trek Fuel EX 9.8...

Nov 2012 · Alan Muldoon

New for 2013 is Trek’s latest incarnation of the ever-popular Fuel Ex, priced from £1,400. We swung a leg over the latest models in the Dolomites to see how the bike has evolved.

[SV_VIMEO id=”48633979″] While most of the mountain bike industry is busy burying the 26″ wheel with barrow loads of big wheels, Trek are one of the few companies who have actually invested in the 26″ trail bike market for 2013. The revamped Fuel EX line up is more capable than ever. It really is the …

An amazingly capable trail bike - there aren't many situations the EX can't handle. Gorgeous construction. Reliable spec and we love the Reverb Stealth seat post! Pretty good value too.

Rear shock tune feels a little too firm when 'Trail' mode is engaged. Fork is noisy. Would be better without a triple ring crankset.

By Kevin Rouse Photos: Sterling Lorence and Dan Milner Believe it or not, the singletrack trail category makes up a whopping 78-percent of Trek's sales in

Mar 2012 · Mike Davis

Revised geometry and the addition of a through-axle fork have given the Trek Fuel EX a distinct attacking edge for 2012, but without detracting from the user-friendly poise for which it’s deservedly popular. . .

Apr 2011 · MBA Action

Trek's top-of-the-line, 4.7-inch-travel, carbon fiber Fuel EX trailbikes have impressed us with their lightweight and plush suspension performance. For

Last updated June 29 Not listed for 2,477 days

Russia establishes special site to fabricate fuel for China’s CFR-600

!{Model.Description}

A special production site to fabricate fuel for China’s CFR-600 fast reactor under construction has been established at Russia’s Mashinostroitelny Zavod (MSZ - Machine-Building Plant) in Elektrostal (Moscow region), part of Rosatom’s TVEL Fuel Company. 

As part of the project, MSZ had upgraded existing facilities fo the production of fuel for fast reactors, TVEL said on 3 March. Unique equipment has been created and installed, and dummy CFR-600 fuel assemblies have already been manufactured for testing.

The new production site was set up to service an export contract between TVEL and the Chinese company CNLY (part of China National Nuclear Corporation - CNNC) for the supply of uranium fuel for CFR-600 reactors. Construction of the first CFR-600 unit started in Xiapu County, in China's Fujian province in late 2017 followed by the second unit in December 2020. The contract is for the start-up fuel load, as well as refuelling for the first seven years. The start of deliveries is scheduled for 2023.

“The Russian nuclear industry has a unique 40 years of experience in operating fast reactors, as well as in the production of fuel for such facilities,” said TVEL President Natalya Nikipelova. “The Fuel Division of Rosatom is fulfilling its obligations within the framework of Russian-Chinese cooperation in the development of fast reactor technologies. These are unique projects when foreign design fuel is produced in Russia. Since 2010, the first Chinese fast neutron reactor CEFR has been operating on fuel manufactured at the Machine-Building Plant, and for the supply of CFR-600 fuel, a team of specialists from MSZ and TVEL has successfully completed a complex high-tech project to modernise production,” she explained.

A special feature of the new section is its versatility: this equipment will be used to produce fuel intended for both the Chinese CFR-600 and CEFR reactors and the Russian BN-600 reactor of the Beloyarsk NPP. In the near future, the production of standard products for the BN-600 will begin.

The contract for the supply of fuel for the CFR-600 was signed in December 2018 as part of a governmental agreement between Russia and China on cooperation in the construction and operation of a demonstration fast neutron reactor in China. This is part of a wider comprehensive programme of cooperation in the nuclear energy sector over the coming decades. This includes serial construction of the latest Russian NPP power units with generation 3+ VVER-1200 reactors at two sites in China (Tianwan and Xudabao NPPs). A package of intergovernmental documents and framework contracts for these projects was signed in 2018 during a meeting between Russian President Vladimir Putin and Chinese President Xi Jinping.

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Trek Fuel EX 7 E

• AUS $ NZD $ USD $ CAD $ GBP £ EUR €

Colour / Crystal Pearl White

Size / 15.5, 17.5, 18.5, 19.5, 21.5"

At a glance

Where to buy.

Specifications

• Frame Alpha Platinum Aluminum w/ABP Convert, Full Floater, E2 tapered head tube, internal front derailleur cable routing, magnesium EVO Link, replaceable derailleur hanger, 120mm travel
• Wheels Formula DC51 15mm alloy front hub, Shimano M525 alloy rear hub; Bontrager Duster Disc 32-hole rims, Tubeless Ready
• Wheel Size 26"
• Tires Bontrager XR4 Expert, 26x2.2"
• Crank Shimano M552, 42/32/24
• Front Derailleur Shimano Deore
• Rear Derailleur Shimano SLX M663 Shadow
• Shifters Shimano Deore M591, 10 speed
• Brakeset Avid Elixir 3 hydraulic disc brakes
• Handlebar Bontrager Low Riser, 31.8mm, 15mm rise, 9 degree sweep
• Saddle Bontrager Evoke 2, chromoly rails
• Seatpost Bontrager SSR, 31.6mm, 20mm offset
• Stem Bontrager Race Lite, 31.8mm
• Headset FSA NO.57E, E2, ACB sealed bearings

Q: What size wheels does the 2012 Trek Fuel EX 7 E have?

The 2012 Trek Fuel EX 7 E has 26" wheels.

Q: What size 2012 Trek Fuel EX 7 E should I get?

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Study of modified VVER and typical PWR fuel in the HBWR reactor (Norway)

• Published: 21 December 2012
• Volume 113 , pages 171–178, ( 2013 )

Cite this article

• B. Yu. Volkov 1 ,
• W. Wiesenack 1 ,
• V. V. Yakovlev 2 ,
• E. P. Ryazantsev 2 ,
• A. K. Panyushkin 3 ,
• A. V. Ivanov 3 ,
• O. V. Kryukov 3 ,
• P. I. Lavrenyuk 4 &
• Yu. V. Pimenov 4  

126 Accesses

3 Citations

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Two experiments studying the standard and modified VVER fuel fabricated at the Machine-Building Plant (in Elektrostal) and PWR fuel produced according to the typical specifications were performed on the HBWR research reactor (Halden, Norway) from 1995 to 2005. The objective of these experiments was to study the effect of the structural-technological parameters on the behavior of VVER fuel in comparison with the typical PWR fuel. These studies made it possible to expand the in-reactor data base on the behavior of VVER uranium oxide fuel as well as to develop recommendations for improving the technology of its production in order to increase fuel stability under irradiation.

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Fuel for VVER and PWR: Current Status and Prospects

D. L. Zverev, O. B. Samoilov, … S. A. Zotov

Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor

M. V. Kormilitsyn, L. A. Kormilitsyna, … T. D. Shchepetina

PWR Fuel Cycle Increased Enrichment, Combination of Burnable Absorbers

B. Yu. Volkov, E. P. Ryazantsev, V. V. Yakovlev, et al., “Studies of the behavior of VVER and PWR irradiated in the HBWR reactor (Halden, Norway),” At. Énerg. , 111 , No. 6, 342–348 (2011).

Google Scholar  

B. Volkov, E. Ryazantzev, and V. Yakovlev, The Thermal and Mechanical Behaviour of Modified WWER Fuel Compared with PWR Specification Fuel in IFA-503.2 , HWR-637, December 2000.

B. Volkov and T. Tverberg, “Irradiation performance of modified WWER fuel compared with typical PWR fuel in the Halden Reactor Test,” in: 4th Int. Conf. on WWER Fuel Performance, Modelling, and Experimental Support , Bulgaria, Varna, Oct. 15, 2001, pp. 186–196.

B. Volkov and E. Kolstad, “Review of WWER fuel and material tests in the Halden reactor,” in: 6th Int. Conf. on WWER Fuel Performance, Modelling and Experimental Support , Bulgaria, Albena, Sept. 19–23, 2005, pp. 214–221.

K. Vinjamuru and D. Owen, “Helium fill gas absorption in pressurized UO2 fuel rods during irradiation,” Nucl. Technol ., 47 , No. 1, 119–124 (1980).

G. Small, “Densification of uranium dioxide at low burnup,” J. Nucl. Mater. , 148 , No. 3, 302–315 (1987).

Article   MathSciNet   ADS   Google Scholar  

M. Freshley et al., “Irradiation-induced densification of UO2 pellet fuel,” ibid ., 62 , No. 2, 138–166 (1976).

W. Wiesenack and T. Tverberg, “Thermal performance of high burnup fuel – in-pile temperature data and analysis,” in: Int. Topical Meeting on LWR Fuel Performance , Utah, USA, April 10–3, 2000, pp. 626–633.

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Halden Reactor Project, Halden, Norway

B. Yu. Volkov & W. Wiesenack

National Research Center Kurchatov Institute, Moscow, Russia

V. V. Yakovlev & E. P. Ryazantsev

Machine-Building Plant, Elektrostal, Moscow Oblast, Russia

A. K. Panyushkin, A. V. Ivanov & O. V. Kryukov

TVEL Company, Moscow, Russia

P. I. Lavrenyuk & Yu. V. Pimenov

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Translated from Atomnaya Énergiya, Vol. 113, No. 3, pp. 140–145, September, 2012.

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Volkov, B.Y., Wiesenack, W., Yakovlev, V.V. et al. Study of modified VVER and typical PWR fuel in the HBWR reactor (Norway). At Energy 113 , 171–178 (2013). https://doi.org/10.1007/s10512-012-9613-7

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Received : 14 February 2012

Published : 21 December 2012

Issue Date : January 2013

DOI : https://doi.org/10.1007/s10512-012-9613-7

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