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Title: Next Generation Nuclear Plant Methods Technical Program Plan

Abstract

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended tomore » be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.« less

Authors:
; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
911934
Report Number(s):
INL/EXT-06-11804-Rev.3
TRN: US0800224
DOE Contract Number:  
AC07-99ID13727
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 - SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS, 22 - GENERAL STUDIES OF NUCLEAR REACTORS; ACCIDENTS; DESIGN; FISSION PRODUCTS; LICENSING; PERFORMANCE; STRESS ANALYSIS; TRANSIENTS; TRANSPORT; VALIDATION; VHTR REACTOR; Gen-IV; neutronic behavior; software tools; thermal fluid behavior; Very High Temperature Reactor

Citation Formats

Schultz, Richard R., Ougouag, Abderrafi M., Nigg, David W., Gougar, Hans D., Johnson, Richard W, Terry, William K., Oh, Chang H., McEligot, Donald W., Johnsen, Gary W., McCreery, Glenn E., Yoon, Woo Y., Sterbentz, James W., Herring, J. Steve, Taiwo, Temitope A., Wei, Thomas Y. C., Pointer, William D., Yang, Won S., Farmer, Michael T., Khalil, Hussein S., and Feltus, Madeline A.. Next Generation Nuclear Plant Methods Technical Program Plan. United States: N. p., 2010. Web. doi:10.2172/911934.
Schultz, Richard R., Ougouag, Abderrafi M., Nigg, David W., Gougar, Hans D., Johnson, Richard W, Terry, William K., Oh, Chang H., McEligot, Donald W., Johnsen, Gary W., McCreery, Glenn E., Yoon, Woo Y., Sterbentz, James W., Herring, J. Steve, Taiwo, Temitope A., Wei, Thomas Y. C., Pointer, William D., Yang, Won S., Farmer, Michael T., Khalil, Hussein S., & Feltus, Madeline A.. Next Generation Nuclear Plant Methods Technical Program Plan. United States. doi:10.2172/911934.
Schultz, Richard R., Ougouag, Abderrafi M., Nigg, David W., Gougar, Hans D., Johnson, Richard W, Terry, William K., Oh, Chang H., McEligot, Donald W., Johnsen, Gary W., McCreery, Glenn E., Yoon, Woo Y., Sterbentz, James W., Herring, J. Steve, Taiwo, Temitope A., Wei, Thomas Y. C., Pointer, William D., Yang, Won S., Farmer, Michael T., Khalil, Hussein S., and Feltus, Madeline A.. Wed . "Next Generation Nuclear Plant Methods Technical Program Plan". United States. doi:10.2172/911934. https://www.osti.gov/servlets/purl/911934.
@article{osti_911934,
title = {Next Generation Nuclear Plant Methods Technical Program Plan},
author = {Schultz, Richard R. and Ougouag, Abderrafi M. and Nigg, David W. and Gougar, Hans D. and Johnson, Richard W and Terry, William K. and Oh, Chang H. and McEligot, Donald W. and Johnsen, Gary W. and McCreery, Glenn E. and Yoon, Woo Y. and Sterbentz, James W. and Herring, J. Steve and Taiwo, Temitope A. and Wei, Thomas Y. C. and Pointer, William D. and Yang, Won S. and Farmer, Michael T. and Khalil, Hussein S. and Feltus, Madeline A.},
abstractNote = {One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.},
doi = {10.2172/911934},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Dec 01 00:00:00 EST 2010},
month = {Wed Dec 01 00:00:00 EST 2010}
}

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