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GT-MHR COMMERCIALZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMNET REPORT FOR THE PERIOD JULY 1 THROUGH JULY 31, 2003

Description: A271 GT-MHR COMMERCIALZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMNET REPORT FOR THE PERIOD JULY 1 THROUGH JULY 31, 2003. Petten has completed design of the irradiation test rig for the HFR-EU2 test and has completed design and machining of the H-451 graphite sleeves which will be used to contain the HFR-EU2 fuel compacts. A plan, entitled ''Screening Tests for Selection of VHTR Advanced Fuel,'' has been drafted and has completed internal review. This screening program plan is a major portion of the Development Plan for Advanced High Temperature Coated-Particle currently under preparation.
Date: July 1, 2003
Creator: Shenoy, A. S.
Partner: UNT Libraries Government Documents Department
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GT-MHR Commercialization Study Technical Progress and Cost Management Report: June 2003

Description: A271 GT-MHR COMMERCIALZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD JUNE 1 THROUGH JUNE 30, 2003. Petten was provided with irradiation dimensional change data for both fuel compacts and H-451 graphite for design of the graphite sleeves that hold the fuel compacts to be irradiated in HFR-EU2. The Fuel Sample Product Specification for the Fuel Performance Irradiation Test Capsule MHR-2 was completed and approved. A Work Breakdown Structure was prepared for the development and qualification of advanced coated-particle fuels capable of meeting anticipated fuel performance requirements and work was initiated on preparation of schedules and a cost estimates for the test matrices.
Date: June 1, 2003
Creator: Shenoy, A. S.
Partner: UNT Libraries Government Documents Department
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GT-MHR Commercialization Study Technical Progress and Cost Management Report: May 2003

Description: A271 GT-MHR COMMERCIALZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD MAY 1 THROUGH MAY 31, 2003. Petten advised GA the start of the HFR-EU2 irradiation is being delayed until late July 2004. HFR-EU1 (pebble fuel) is also delayed until February/March 2004. The reason for the delays was implementation of new financial regulations at Petten that delayed the contracts for capsule fabrication. Review of the MHR-2 Fuel Product Specification was completed. Revision of the specification to incorporate the review results is in progress. Detailed test matrices have been drafted for capsule irradiation tests and for post-irradiation heating tests proposed for development and qualification of advanced coated-particle fuels capable of meeting anticipated VHTR fuel performance requirements.
Date: May 1, 2003
Creator: Shenoy, A. S.
Partner: UNT Libraries Government Documents Department
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GT-MHR COMMERCIALIZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD AUGUST 1 THROUGH AUGUST 31, 2003

Description: OAK A271 GT-MHR COMERCIALZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD AUGUST 1 THROUGH AUGUST 31, 2003. In the process of fabricating the MHR-1 irradiation test capsule, Petten has advised that three thermocouples (out of 24) and the Self Powered Neutron detector were damaged during high temperature brazing with the upper capsule lid. Procurement of new TCs and SPN is in process but there will be a delay in the irradiation test of about nine weeks. Startup of the irradiation is now projected to be July or August 2004. In preparation for performing the nuclear design analysis activities required by the advanced fuel studies task, a complete 3-D nuclear design analysis is first being performed of the GT-MHR reference design. This will serve as the baseline for studies of the advanced fuel nuclear design performance.
Date: August 1, 2003
Creator: SHENOY, A.S.
Partner: UNT Libraries Government Documents Department
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GT-MHR Commercialization Study Technical Progress and Cost Management Report: September 2003

Description: OAK B202 Efforts are in process with GA Contracts and DOE-ID Contracts to set up a new I-NERI contract for CY-2004 and beyond for this test. A decision has not yet been made by DOE-ID concerning if this new contract can be sole-sourced to GA. Work continued on preparation for comparative nuclear analyses of cores containing coated particles with TRISO (IPyC/SiC/OPyC) coatings and TRIZO (IPyC/ZrC/OPyC) coatings. Comparison of the nuclear characteristics for 600 MW (th) cores using these two fuels will determine the impact on the core nuclear design of using coated particles where ZrC has been substituted for the SiC layer in TRISO coatings and set an upper bound for the other fuel particle designs where ZrC is used.
Date: September 1, 2003
Creator: Shenoy, A. S.
Partner: UNT Libraries Government Documents Department
open access

GT-MHR COMMERCIALIZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD NOVEMBER 1 THROUGH NOVEMBER 30, 2003

Description: OAK-B135 A copy of the original Memorandum of Understanding (MOU) between the US and the US for the HFR-EU2 (formally MHR-1) fuel irradiation test was sent to DOE-HQ. The startup of the HFR-EU2 test will likely be delayed until September 2004 depending on completion and check out of the fission gas sweep loop. The initial core nuclear design study using advanced fuel was completed for a Very High Temperature Reactor (VHTR). This study assessed the nuclear effects of replacing the silicon carbide layer of the TRISO particle with a zirconium carbide layer (TRIZO particle). The study determined that zirconium behaves like a non-burnable poison and to achieve fuel cycle lengths equivalent to those with TRISO fuel, the fixed burnable poison would have to be adjusted. The core nuclear design study is documented in report General Atomics report number PC-000514. A test plan was completed that describes a series of screening tests to provide the technical basis for selecting and qualifying an advanced coated-particle fuel for the VHTR. The test plan is documented in General Atomics report number PC-000510.
Date: December 1, 2003
Creator: Shenoy, A. S.
Partner: UNT Libraries Government Documents Department
open access

GT-MHR COMMERCIALIZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD DECEMBER 1 THROUGH DECEMBER 31,2003

Description: OAK-B135 A complete set of detail drawings of the HRF-EU2 irradiation assembly was received from Petten. Petten has also indicated that the compacts were loaded into the assembly during December. The HFR-EU2 Irradiation Safety Test Report (to be prepared by the Petten Authority) has not been completed. During December, the following report was completed: ''Development Plan for Advanced High Temperature Coated-Particle Fuels'' General Atomics Report No. PC-00051. This report completes the work scope of Task 10, Advanced Fuel Studies.
Date: January 1, 2004
Creator: Shenoy, A. S.
Partner: UNT Libraries Government Documents Department
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Design requirements for high-temperature metallic component materials in the US modular HTGR

Description: The modular high temperature gas-cooled reactor (MHTGR) is a 350 MW(t) second generation reactor system design which during normal operation circulates helium with a mixed mean coal and hot temperature of 260/sup 0/C (500/sup 0/C) and 690/sup 0/C (1270/sup 0/F), respectively. The design incorporates passive design features which allow the plant to be safely shutdown and cooled with no active systems or operator action being required. A key feature of this concept is the capability of the residual heat removal by passive conduction cooldown from the core to the reactor cavity via an uninsulated vessel. The MHTGR uses a number of metallic components. A description of these components and their design requirements are presented in this paper.
Date: June 1, 1988
Creator: Shenoy, A. S. & Betts, W. S.
Partner: UNT Libraries Government Documents Department
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Optimization of the gas turbine-modular helium reactor using statistical methods to maximize performance without compromising system design margins

Description: This paper describes a statistical approach for determining the impact of system performance and design uncertainties on power plant performance. The objectives of this design approach are to ensure that adequate margin is provided, that excess margin is minimized, and that full advantage can be taken of unconsumed margin. It is applicable to any thermal system in which these factors are important. The method is demonstrated using the Gas Turbine Modular Helium Reactor as an example. The quantitative approach described allows the characterization of plant performance and the specification of the system design requirements necessary to achieve the desired performance with high confidence. Performance variations due to design evolution, inservice degradation, and basic performance uncertainties are considered. The impact of all performance variabilities is combined using Monte Carlo analysis to predict the range of expected operation.
Date: July 1, 1995
Creator: Lommers, L. J.; Parme, L. L. & Shenoy, A. S.
Partner: UNT Libraries Government Documents Department
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H2-MHR Pre-Conceptual Design Report: SI-Based Plant; HTE-Based Plant

Description: Hydrogen and electricity are expected to dominate the world energy system in the long term. The world currently consumes about 50 million metric tons of hydrogen per year, with the bulk of it being consumed by the chemical and refining industries. The demand for hydrogen is expected to increase, especially if the U.S. and other countries shift their energy usage towards a hydrogen economy, with hydrogen consumed as an energy commodity by the transportation, residential, and commercial sectors. However, there is strong motivation to not use fossil fuels in the future as a feedstock for hydrogen production, because the greenhouse gas carbon dioxide is a byproduct and fossil fuel prices are expected to increase significantly. For electricity and hydrogen production, an advanced reactor technology receiving considerable international interest is a modular, passively-safe version of the high-temperature, gas-cooled reactor (HTGR), known in the U.S. as the Modular Helium Reactor (MHR), which operates at a power level of 600 MW(t). For electricity production, the MHR operates with an outlet helium temperature of 850 C to drive a direct, Brayton-cycle power-conversion system (PCS) with a thermal-to-electrical conversion efficiency of 48 percent. This concept is referred to as the Gas Turbine MHR (GT-MHR). For hydrogen production, the process heat from the MHR is used to produce hydrogen. This concept is referred to as the H2-MHR.
Date: April 19, 2006
Creator: Richards, Matt; Shenoy, A. S.; Brown, L. C.; Buckingham, R. T.; Harvego, E. A.; Peddicord, K. L. et al.
Partner: UNT Libraries Government Documents Department
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