Accomplishments

FY 2010

Completed the first Advanced Gas Reactor fuel irradiation experiment, performed post-irradiation examinations of the irradiated fuel specimens, and commence irradiation of the first fuel produced in large-scale production equipment.

Continued irradiation of the first Advanced Graphite Creep test experiment to provide data for nuclear graphite qualification.

Continued the development of advanced gas reactor system-simulation software and initiate bilateral cooperation with Japan on the use of their experimental gas reactor as a test facility for code validation, operational experience, and as an instrumentation and controls test bed.

Continued the study of liquid salt properties and materials issues associated with its use as a high temperature medium for intermediate energy transport loops.

Continued development of high temperature steam electrolysis as a hydrogen production technology that is compatible with the NGNP.

Continued international R&D collaborations through the Generation IV International Forum (GIF), IAEA, and bi-lateral agreements.

 

FY 2011

Sponsor an independent review of NGNP activities by the Nuclear Energy Advisory Committee to inform a decision on readiness to proceed with Phase 2 of the NGNP Project.

Select the technology to be used for NGNP and enter into a cost-sharing public-private partnership to conduct the R&D, design and licensing activities leading to NRC issuance of a Combined Operating License.

Continue the irradiation in the INL Advanced Test Reactor (ATR) of the first NGNP fuel produced in commercial scale production equipment and complete post-irradiation examination of the first NGNP fuel removed from ATR in November 2009.

Continue selection and characterization of NGNP graphite and composite materials, including the irradiation of the first graphite test experiment in ATR and the assembly of High-Temperature Vessel irradiation experiments planned for Oak Ridge.

Continue environmental, mechanical property, and joining method (e.g. welding) studies for selected heat exchanger and reactor pressure vessel materials for code-case data package development and qualification.

Continue topical report analysis and respond to Requests for Additional Information from the NRC, pending the availability of design data.

Complete Regulatory Gap Analysis that will review existing NRC rules and regulations and identify their applicability to gas reactors.

Continue international R&D collaborations through the GIF on fuels, materials, modeling and process heat applications.

Use existing test facilities (High-Temperature Test Reactor in Japan) and construction of separate effects and integral effects test experiments for validating NGNP thermal-fluid behavior and the capability of the passive system to remove decay heat.

Conduct research on process heat applications, including system interface requirements and materials compatibility issues, for coupling NGNP to various non-electric applications.

Continue fuel performance modeling, fabrication modeling, and fission product transport.

 

FY 2012

Continue the Design and Development activities from FY 2011.

Provided technical data for the independent review of NGNP activities by the Nuclear Energy Advisory Committee to inform a decision on readiness to proceed with Phase 2 of the NGNP Project.

Forward a decision package to Secretary in early June 2011 timeframe.

The decision package will include NEAC NRT sub-committee report and other documents necessary to justify the proposed course of action.

NGNP R&D and program plans will be revised as necessary based on Secretarial decision.