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The U.S. Army’s Deactivated Nuclear Power Plant Program
The U.S. Army Corps of Engineers (USACE), Baltimore District, is home to the North Atlantic Division’s Radiological Health Physics Regional (RHPR) Center of Expertise, which is leading the decommissioning of Army reactors.
From 1956 to 1976, the Army’s nuclear power program operated several small nuclear reactors to confirm the feasibility of their meeting military power needs on land. Three Army reactors were deactivated in the 1970s and placed into safe storage awaiting future decommissioning.
L. Mansani, C. Artioli, M. Schikorr, G. Rimpault, C. Angulo, D. De Bruyn
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 241-263
Technical Paper | Accelerators | dx.doi.org/10.13182/NT11-96
Articles are hosted by Taylor and Francis Online.
In order to reduce the volume and the radiotoxicity of the nuclear waste coming from the operation of existing pressurized water reactors, accelerator-driven systems (ADSs) have been envisioned. The Lead-Cooled (Pb) European Facility for Industrial-Scale Transmutation (EFIT) (Pb-EFIT) plant is the first ADS design that has been going into a rather detailed engineering level. It is a lead-cooled, 385-MW(thermal) ADS prototype for minor actinide (MA) transmutation designed to achieve an optimal MA destruction rate of [approximately]42 kg/TWh(thermal).The spallation target unit is located in the center of the diagrid where 800-MeV protons from the accelerator impinge on a free surface of lead exposed to vacuum.The core inlet temperature was set at 400°C to assure a sufficiently large safety margin to lead freezing, and the core outlet temperature was limited to 480°C to allow acceptable corrosion. The ferritic-martensitic 9% Cr steel T91 protected against corrosion with alumina FeCrAlY [GESA (Gepulste Elektronen Strahl Anlage) treatment].The primary circuit is designed for effective natural circulation, i.e., relatively low pressure losses, and the design offers good protection for a heat removal system in case of a blackout accident. The EFIT plant is designed to have a low likelihood and a low degree of core damage, to eliminate the need for off-site emergency responses in case of a severe accident, to use an extensively reliable passive safety system to fulfill the safety functions, and to eliminate the need of alternating-current safety-grade power (no safety-grade diesel generator). Three systems contribute to the decay heat removal (DHR) function of Pb-EFIT: the steam generators, the direct reactor cooling system, and the isolation condenser system.The EFIT plant exhibits four primary pumps; eight steam generator units, each rated at 52 MW, provide heat removal under normal operation. On the secondary side, the water steam ensures a thermal efficiency of [approximately]40% with the superheated vapor secondary circuit, taking into account the electricity required by pumps (from both the primary circuit and the secondary circuits) but without deducing the power required for the accelerator.An estimate of the Pb-EFIT plant cost has been performed based mainly on experience and engineering judgment. A best estimate (base cost and contingency) of about €1890 million, with an overall uncertainty of 22%, has been found.