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Title: Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R&D Project

Abstract

This project characterizes typical two-phase stratified flow conditions in advanced water reactor horizontal pipe sections, following activation of passive cooling systems. It provides (1) a means to educate nuclear engineering students regarding the importance of two-phase stratified flow in passive cooling systems to the safety of advanced reactor systems and (2) describes the experimental apparatus and process to measure key parameters essential to consider when designing passive emergency core cooling flow paths that may encounter this flow regime. Based on data collected, the state of analysis capabilities can be determined regarding stratified flow in advanced reactor systems and the best paths forward can be identified to ensure that the nuclear industry can properly characterize two-phase stratified flow in passive emergency core cooling systems.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Idaho State University, Pocatello, ID
Sponsoring Org.:
USDOE - Office of Nuclear Energy, Science and Technology (NE)
OSTI Identifier:
900897
Report Number(s):
DOE/ID/14500
TRN: US0702972
DOE Contract Number:
FG07-03ID14500
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; COOLING SYSTEMS; DESIGN; ECCS; NUCLEAR ENGINEERING; NUCLEAR INDUSTRY; SAFETY; WATER; LWR Passive Safety; Stratified Horizontal Flow, Condensation-Induced Water Hammer, AP600

Citation Formats

Brian G. Williams, Jim C. P. Liou, Hiral Kadakia, Bill Phoenix, and Richard R. Schultz. Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R&D Project. United States: N. p., 2007. Web. doi:10.2172/900897.
Brian G. Williams, Jim C. P. Liou, Hiral Kadakia, Bill Phoenix, & Richard R. Schultz. Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R&D Project. United States. doi:10.2172/900897.
Brian G. Williams, Jim C. P. Liou, Hiral Kadakia, Bill Phoenix, and Richard R. Schultz. Tue . "Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R&D Project". United States. doi:10.2172/900897. https://www.osti.gov/servlets/purl/900897.
@article{osti_900897,
title = {Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R&D Project},
author = {Brian G. Williams and Jim C. P. Liou and Hiral Kadakia and Bill Phoenix and Richard R. Schultz},
abstractNote = {This project characterizes typical two-phase stratified flow conditions in advanced water reactor horizontal pipe sections, following activation of passive cooling systems. It provides (1) a means to educate nuclear engineering students regarding the importance of two-phase stratified flow in passive cooling systems to the safety of advanced reactor systems and (2) describes the experimental apparatus and process to measure key parameters essential to consider when designing passive emergency core cooling flow paths that may encounter this flow regime. Based on data collected, the state of analysis capabilities can be determined regarding stratified flow in advanced reactor systems and the best paths forward can be identified to ensure that the nuclear industry can properly characterize two-phase stratified flow in passive emergency core cooling systems.},
doi = {10.2172/900897},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Feb 27 00:00:00 EST 2007},
month = {Tue Feb 27 00:00:00 EST 2007}
}

Technical Report:

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  • OAK B204 The overall goal of this three-year research project was to develop a new scientific design of a compact modular 200 MWe and a full size 1200 MWe simplified boiling water reactors (SBWR). Specific objectives of this research were: (1) to perform scientific designs of the core neutronics and core thermal-hydraulics for a small capacity and full size simplified boiling water reactor, (2) to develop a passive safety system design, (3) improve and validate safety analysis code, (4) demonstrate experimentally and analytically all design functions of the safety systems for the design basis accidents (DBA) and (5) to developmore » the final scientific design of both SBWR systems, 200 MWe (SBWR-200) and 1200 MWe (SBWR-1200). The SBWR combines the advantages of design simplicity and completely passive safety systems. These advantages fit well within the objectives of NERI and the Department of Energy's focus on the development of Generation III and IV nuclear power. The 3-year research program was structured around seven tasks. Task 1 was to perform the preliminary thermal-hydraulic design. Task 2 was to perform the core neutronic design analysis. Task 3 was to perform a detailed scaling study and obtain corresponding PUMA conditions from an integral test. Task 4 was to perform integral tests and code evaluation for the DBA. Task 5 was to perform a safety analysis for the DBA. Task 6 was to perform a BWR stability analysis. Task 7 was to perform a final scientific design of the compact modular SBWR-200 and the full size SBWR-1200. A no cost extension for the third year was requested and the request was granted and all the project tasks were completed by April 2003. The design activities in tasks 1, 2, and 3 were completed as planned. The existing thermal-hydraulic information, core physics, and fuel lattice information was collected on the existing design of the simplified boiling water reactor. The thermal-hydraulic design were developed. Based on a detailed integral system scaling analysis, design parameters were obtained and designs of the compact modular 200 MWe SBWR and the full size 1200 MWe SBWR were developed. These reactors are provided with passive safety systems. A new passive vacuum breaker check valve was designed to replace the mechanical vacuum beaker check valve. The new vacuum breaker check valve was based on a hydrostatic head, and was fail safe. The performance of this new valve was evaluated both by the thermal-hydraulic code RELAP5 and by the experiments in a scaled SBWR facility, PUMA. In the core neutronic design a core depletion model was implemented to PARCS code. A lattice design for the SBWR fuel assemblies was performed. Design improvements were made to the neutronics/thermal-hydraulics models of SBWR-200 and SBWR-1200, and design analyses of these reactors were performed. The design base accident analysis and evaluation of all the passive safety systems were completed as scheduled in tasks 4 and 5. Initial conditions for the small break loss of coolant accidents (LOCA) and large break LOCA using REALP5 code were obtained. Small and large break LOCA tests were performed and the data was analyzed. An anticipated transient with scram was simulated using the RELAP5 code for SBWR-200. The transient considered was an accidental closure of the main steam isolation valve (MSIV), which was considered to be the most significant transient. The evaluation of the RELAP5 code against experimental data for SBWR-1200 was completed. In task 6, the instability analysis for the three SBWR designs (SBWR-1200, SBWR-600 and SBWR-200) were simulated for start-up transients and the results were similar. Neither the geysering instability, nor the loop type instability was predicted by RAMONA-4B in the startup simulation following the recommended procedure by GE. The density wave oscillation was not observed at all because the power level used in the simulation was not high enough. A study was made of the potential instabilities by imposing an unrealistically high power ramp in a short time period, as suggested by GE. RAMONA-4B predicted core flow oscillations, of small amplitude, similar to that of the TRACG prediction by GE.« less
  • The computer program which was developed to apply the multi-attribute utility (MAU) methodology to the selection of LWR safety R and D programs and proposals is described. An overview of the MAU method is presented, followed by a description of the steps incorporated in developing individual modules for use in the multi-attribute utility package (MAUP). Each module is described complete with usage information and an example of computer output.
  • This report documents a developed methodology for selecting LWR-safety R and D projects and a demonstration of this methodology. The work reported here was conducted under the LWR Safety R and D Selection Methodology Development Program, Sandia P.O. 42-8240 during fiscal year 1980. The program was initiated in mid April 1979 and had the objective to develop and demonstrate a methodology for selecting R and D projects in decision situations of the DOE LWR Safety Technology Program. The developed methodology and demonstration were urged by inadequacies in existing methods and the unconfirmed reliability of these methods to handle the decisionmore » situations of interest. The developed methodology provides analytical tools for probabilistic cost and benefit analysis to aid project selection for these situations. The methodology is not confined to monetary benefits and has been applied with the expected reduction in public risk as a measure of the benefit of an R and D project. Characteristics of the methodology and results of its application are summarized.« less
  • The objective of the LWR R and D Selection Methodology Program is to develop and demonstrate an R and D selection methodology appropriate for LWR safety technology. This report documents the development work from the program beginning in April, 1979 to the end of Fiscal Year 1979. The scope of work for this period included three tasks; methodology review (Task 1), measures development (Task 2), and methodology development for the first phase of application (Task 3). The accomplishments of these tasks are presented.
  • The results of work done to develop a methodology for selecting LWR safety R and D programs and proposals is described. A critical survey of relevant decision analysis methods is provided including the specifics of multiattribute utility theory. This latter method forms the basis of the developed selection methodology. Details of the methodology and its use are provided along with a sample illustration of its application.