Nuclear Power Technology Development Section

TECDOC-1382

Evaluation of the High-Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of HTTR and HTR-10

The TECDOC documents a first set of high-temperature gas-cooled reactor core physics and thermal-hydraulic benchmarks, comparing code-to-code and code-to-experiement results. Experimental data is based on critical tests related to the startup of the HTTR and HTR-10 test reactors.

TECDOC-1365

Review of National Accelerator Driven System Programmes for Partitioning And Transmutation

With the objective of assessing the progress in the development of hybrid systems for P&T, as well as their potential role relative to future direction of the nuclear power worldwide development, the TECDOC presents a review of P&T related R&D programmes in Member States.

TECDOC-1362

Guidance for the Evaluation of Innovative Nuclear Reactors and Fuel Cycles. Re-port of phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

The TECDOC provides a Methodology for the Assessment of Innovative Nuclear Energy Systems as based on the defined set of Basic Principles, User Requirements, Criteria, and recommendations structured along the areas of Economics, Sustainability and Environment, Safety, Waste Management, Proliferation Resistance and Cross Cutting (infrastructure, institutional, legal, social, human resource) Issues.

TECDOC-1356

Emerging Nuclear Energy and Transmutation Systems: Core Physics and Engineering Aspects

The TECDOC reviews the status of research and development activities in the area of hybrid systems for energy generation and transmutation, discusses specific scientific and technical issues covering the various R&D topics of these systems, and identifies activities in response to the open issues.

TECDOC-1349

Potential of thorium-based fuel cycles to constrain plutonium and reduce the long-lived waste toxicity

The TECDOC is the final report of an IAEA coordinated research project (CRP) initiated in 1995. This CRP examined different fuel cycle options in which plutonium can be recycled with thorium with the goal of plutonium incineration. The CRP also investigated the radio-toxicity accumulation in, and the transmutation potential of thorium-based cycles in current, advanced, and innovative nuclear power reactors.

TECDOC-1348

Power reactor and sub-critical blanket systems with lead and lead-bismuth as coolant and/or target material

The TECDOC presents a review of the R&D performed in the Member States in critical and sub-critical transmutation concepts, with emphasis on heavy liquid metal properties, and the experimental and analytical codes and data validation work

TCS-23

Boiling Water Reactor Simulator: Workshop Material

Workshop material presenting the Boiling Water Reactor (BWR) Simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada

TCS-22

Pressurized Water Reactor Simulator: Workshop Material

Workshop material presenting the Pressurized Water Reactor (PWR) Simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada