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Title: 2006 RERTR international meeting proceedings.


No abstract prepared.

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Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
OSTI Identifier:
Report Number(s):
TRN: US1002703
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: 2006 Reduced Enrichment for Research and Test Reactors International Meeting; Oct. 29, 2006 - Nov. 2, 2006; Cape Town, South Africa
Country of Publication:
United States

Citation Formats

Roglans-Ribas, J., Holland, J., Totev, T., Snelgrove, J., Matos, J., Kim, Y.S., Garner, P., Hanan, N., Hofman, G., and Nuclear Engineering Division. 2006 RERTR international meeting proceedings.. United States: N. p., 2007. Web.
Roglans-Ribas, J., Holland, J., Totev, T., Snelgrove, J., Matos, J., Kim, Y.S., Garner, P., Hanan, N., Hofman, G., & Nuclear Engineering Division. 2006 RERTR international meeting proceedings.. United States.
Roglans-Ribas, J., Holland, J., Totev, T., Snelgrove, J., Matos, J., Kim, Y.S., Garner, P., Hanan, N., Hofman, G., and Nuclear Engineering Division. Wed . "2006 RERTR international meeting proceedings.". United States. doi:.
title = {2006 RERTR international meeting proceedings.},
author = {Roglans-Ribas, J. and Holland, J. and Totev, T. and Snelgrove, J. and Matos, J. and Kim, Y.S. and Garner, P. and Hanan, N. and Hofman, G. and Nuclear Engineering Division},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed May 09 00:00:00 EDT 2007},
month = {Wed May 09 00:00:00 EDT 2007}

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  • No abstract prepared.
  • Following the highly successful ICAPP'05 meeting held in Seoul Korea, the 2006 International Congress on Advances in Nuclear Power Plants brought together international experts of the nuclear industry involved in the operation, development, building, regulation and research related to Nuclear Power Plants. The program covers the full spectrum of Nuclear Power Plant issues from design, deployment and construction of plants to research and development of future designs and advanced systems. The program covers lessons learned from power, research and demonstration reactors from over 50 years of experience with operation and maintenance, structures, materials, technical specifications, human factors, system design andmore » reliability. The program by technical track deals with: - 1. Water-Cooled Reactor Programs and Issues Evolutionary designs, innovative, passive, light and heavy water cooled reactors; issues related to meeting medium term utility needs; design and regulatory issues; business, political and economic challenges; infrastructure limitations and improved construction techniques including modularization. - 2. High Temperature Gas Cooled Reactors Design and development issues, components and materials, safety, reliability, economics, demonstration plants and environmental issues, fuel design and reliability, power conversion technology, hydrogen production and other industrial uses; advanced thermal and fast reactors. - 3. Long Term Reactor Programs and Strategies Reactor technology with enhanced fuel cycle features for improved resource utilization, waste characteristics, and power conversion capabilities. Potential reactor designs with longer development times such as, super critical water reactors, liquid metal reactors, gaseous and liquid fuel reactors, Gen IV, INPRO, EUR and other programs. - 4. Operation, Performance and Reliability Management Training, O and M costs, life cycle management, risk based maintenance, operational experiences, performance and reliability improvements, outage optimization, human factors, plant staffing, outage reduction features, major component reliability, repair and replacement, in-service inspection, and codes and standards. - 5. Plant Safety Assessment and Regulatory Issues Transient and accident performance including LOCA and non-LOCA, severe accident analysis, impact of risk informed changes, accident management, assessment and management of aging, degradation and damage, life extension lessons from plant operations, probabilistic safety assessment, plant safety analysis, reliability engineering, operating and future plants. - 6. Thermal Hydraulic Analysis and Testing Phenomena identification and ranking, computer code scaling applicability and uncertainty, containment thermal hydraulics, component and integral system tests, improved code development and qualification, single and two phase flow; advanced computational thermal hydraulic methods. - 7. Core and Fuel Cycle Concepts and Experiments Core physics, advances in computational reactor analysis, in-core fuel management, mixed-oxide fuel, thorium fuel cycle, low moderation cores, high conversion reactor designs, particle and pebble bed fuel design, testing and reliability; fuel cycle waste minimization, recycle, storage and disposal. - 8. Materials and Structural Issues Fuel, core, RPV and internals structures, advanced materials issues and fracture mechanics, concrete and steel containments, space structures, analysis, design and monitoring for seismic, dynamic and extreme accidents; irradiation issues and materials for new plants. - 9. Nuclear Energy and Sustainability including Hydrogen, Desalination and Other Applications Environmental impact of nuclear and alternative systems, spent fuel dispositions and transmutation systems, fully integrated fuel cycle and symbiotic nuclear power systems, application of advanced designs to non-power applications such as the production of hydrogen, sea water desalination, heating and other co-generation applications. - 10. Near Term Issues (New) Applies to plants that have a significant percentage of their design completed and to issues related to the deployment of these plants in the near term (next couple years). Includes deployment activities such as licensing of sites / projects (such as ESP / COL activities in US), detailed construction plans, use of 3D models, procurement activities/challenges. - 11. Reactor Physics and Analysis (New) Nuclear design methodology and codes, cross-section libraries and lattice physics, Monte Carlo and deterministic transport calculation. - 12. Space Power and Propulsion Large and small space nuclear power systems, nuclear thermal propulsion and bimodal systems, science and technology, missions, life cycle, operation and maintenance, system operation and safety analysis, radiation protection and materials.« less
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