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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 Laboratory (INL)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
1009143
Report Number(s):
INL/EXT-06-11804
TRN: US1101734
DOE Contract Number:
DE-AC07-05ID14517
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

Richard R. Schultz, Abderrafi M. Ougouag, David W. Nigg, Hans D. Gougar, Richard W. Johnson, William K. Terry, Chang H. Oh, Donald W. McEligot, Gary W. Johnsen, Glenn E. McCreery, Woo Y. Yoon, James W. Sterbentz, J. Steve Herring, Temitope A. Taiwo, Thomas Y. C. Wei, William D. Pointer, Won S. Yang, Michael T. Farmer, Hussein S. Khalil, and Madeline A. Feltus. Next Generation Nuclear Plant Methods Technical Program Plan. United States: N. p., 2010. Web. doi:10.2172/1009143.
Richard R. Schultz, Abderrafi M. Ougouag, David W. Nigg, Hans D. Gougar, Richard W. Johnson, William K. Terry, Chang H. Oh, Donald W. McEligot, Gary W. Johnsen, Glenn E. McCreery, Woo Y. Yoon, James W. Sterbentz, J. Steve Herring, Temitope A. Taiwo, Thomas Y. C. Wei, William D. Pointer, Won S. Yang, Michael T. Farmer, Hussein S. Khalil, & Madeline A. Feltus. Next Generation Nuclear Plant Methods Technical Program Plan. United States. doi:10.2172/1009143.
Richard R. Schultz, Abderrafi M. Ougouag, David W. Nigg, Hans D. Gougar, Richard W. Johnson, William K. Terry, Chang H. Oh, Donald W. McEligot, Gary W. Johnsen, Glenn E. McCreery, Woo Y. Yoon, James W. Sterbentz, J. Steve Herring, Temitope A. Taiwo, Thomas Y. C. Wei, William D. Pointer, Won S. Yang, Michael T. Farmer, Hussein S. Khalil, and Madeline A. Feltus. Wed . "Next Generation Nuclear Plant Methods Technical Program Plan". United States. doi:10.2172/1009143. https://www.osti.gov/servlets/purl/1009143.
@article{osti_1009143,
title = {Next Generation Nuclear Plant Methods Technical Program Plan},
author = {Richard R. Schultz and Abderrafi M. Ougouag and David W. Nigg and Hans D. Gougar and Richard W. Johnson and William K. Terry and Chang H. Oh and Donald W. McEligot and Gary W. Johnsen and Glenn E. McCreery and Woo Y. Yoon and James W. Sterbentz and J. Steve Herring and Temitope A. Taiwo and Thomas Y. C. Wei and William D. Pointer and Won S. Yang and Michael T. Farmer and Hussein S. Khalil and Madeline A. Feltus},
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 = {10.2172/1009143},
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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