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Code Validation With Ebr Ii Test Data
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Book Synopsis Code Validation with EBR-II Test Data by :
Download or read book Code Validation with EBR-II Test Data written by and published by . This book was released on 1992 with total page 27 pages. Available in PDF, EPUB and Kindle. Book excerpt: An extensive system of computer codes is used at Argonne National Laboratory to analyze whole-plant transient behavior of the Experimental Breeder Reactor 2. Three of these codes, NATDEMO/HOTCHAN, SASSYS, and DSNP have been validated with data from reactor transient tests. The validated codes are the foundation of safety analyses and pretest predictions for the continuing design improvements and experimental programs in EBR-II, and are also valuable tools for the analysis of innovative reactor designs.
Book Synopsis Code Validation with EBR-II Test Data by : J. P. Herzog
Download or read book Code Validation with EBR-II Test Data written by J. P. Herzog and published by . This book was released on 1991 with total page 27 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis SASSYS-1 Computer Code Verification with EBR-II Test Data by :
Download or read book SASSYS-1 Computer Code Verification with EBR-II Test Data written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The EBR-II natural circulation experiment, XX08 Test 8A, is simulated with the SASSYS-1 computer code and the results for the latter are compared with published data taken during the transient at selected points in the core. The SASSYS-1 results provide transient temperature and flow responses for all points of interest simultaneously during one run, once such basic parameters as pipe sizes, initial core flows, and elevations are specified. The SASSYS-1 simulation results for the EBR-II experiment XX08 Test 8A, conducted in March 1979, are within the published plant data uncertainties and, thereby, serve as a partial verification/validation of the SASSYS-1 code.
Book Synopsis Validation of the HOTCHAN Code for Analyzing the EBR-II Driver Following Loss of Flow Without Scram by :
Download or read book Validation of the HOTCHAN Code for Analyzing the EBR-II Driver Following Loss of Flow Without Scram written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of experiments involving unprotected (no scram) loss-of-primary flow (LOF) down to natural convection was successfully conducted in February 1985 on the Experimental Breeder Reactor-II (EBR-II). The predicted and measured behavior of a special instrumented assembly, the XX09 fueled INSAT, is compared for the most severe test in the group to demonstrate the validation of the thermal-hydraulic code HOTCHAN. The particular test of interest in this paper was initiated at full power by tripping the primary and secondary pumps. These tests were part of the Shutdown Heat Removal Tests (SHRT) being conducted in EBR-II. The reactor and balance of plant are extensively instrumented and measurements were recorded by a data acquisition system. The reactor and plant response confirm predictions that the driver fuel cladding can survive temperatures above the eutectic threshold for the transient following a station blackout without scramming the reactor. The incore data provide an additional basis for validation of the recently developed HOTCHAN code for analyzing the thermal-hydraulic behavior of specific fuel subassemblies. In this paper the analytical model for HOTCHAN will be described as well as its relationship to the NATDEMO code. The predicted behavior of the hottest driver subassembly is also discussed and compared with XX09 results.
Book Synopsis Dynamics and Control in Nuclear Power Stations by : British Nuclear Energy Society
Download or read book Dynamics and Control in Nuclear Power Stations written by British Nuclear Energy Society and published by Thomas Telford. This book was released on 1992 with total page 214 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume covers a wider view of the aspects of control of nuclear power stations by taking into consideration the plant as a whole and the protection systems employed therein. Authors with world-wide experience consider all the aspects of dynamics and control in the context of both fast and thermal power stations. The topics discussed include both the methods of development and applications within - analysis of plant behaviour, validation of mathematical models, plant testing, design and implementation of controls.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Results and Implications of the EBR-II Inherent Safety Demonstration Tests by :
Download or read book Results and Implications of the EBR-II Inherent Safety Demonstration Tests written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: On April 3, 1986 two milestone tests were conducted in Experimental Breeder Reactor-2 (EBR-II). The first test was a loss of flow without scram and the second was a loss of heat sink without scram. Both tests were initiated from 100% power and in both tests the reactor was shut down by natural processes, principally thermal expansion, without automatic scram, operator intervention or the help of special in-core devices. The temperature transients during the tests were mild, as predicted, and there was no damage to the core or reactor plant structures. In a general sense, therefore, the tests plus supporting analysis demonstrated the feasibility of inherent passive shutdown for undercooling accidents in metal-fueled LMRs. The results provide a technical basis for future experiments in EBR-II to demonstrate inherent safety for overpower accidents and provide data for validation of computer codes used for design and safety analysis of inherently safe reactor plants.
Book Synopsis Validation and Application of a Physics Database for Fast Reactor Fuel Cycle Analysis by :
Download or read book Validation and Application of a Physics Database for Fast Reactor Fuel Cycle Analysis written by and published by . This book was released on 1994 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: An effort has been made to automate the execution of fast reactor fuel cycle analysis, using EBR-II as a demonstration vehicle, and to validate the analysis results for application to the IFR closed fuel cycle demonstration at EBR-II and its fuel cycle facility. This effort has included: (1) the application of the standard ANL depletion codes to perform core-follow analyses for an extensive series of EBR-II runs, (2) incorporation of the EBR-II data into a physics database, (3) development and verification of software to update, maintain and verify the database files, (4) development and validation of fuel cycle models and methodology, (5) development and verification of software which utilizes this physics database to automate the application of the ANL depletion codes, methods and models to perform the core-follow analysis, and (6) validation studies of the ANL depletion codes and of their application in support of anticipated near-term operations in EBR-II and the Fuel Cycle Facility. Results of the validation tests indicate the physics database and associated analysis codes and procedures are adequate to predict required quantities in support of early phases of FCF operations.
Download or read book Nuclear Safety written by and published by . This book was released on 1986 with total page 618 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Minet Validation Study Using EBR-II Transient Data by :
Download or read book Minet Validation Study Using EBR-II Transient Data written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The MINET code, developed to simulate large and complex thermal-hydraulic systems, such as balance of plant, was used to simulate an EBR-II test transient. MINET calculations agreed well with measured parameters, confirming the validity of the basic MINET methodology and key component models.
Download or read book Nuclear Reactors written by Chad L. Pope and published by BoD – Books on Demand. This book was released on 2022-09-14 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt: Worldwide interest in nuclear reactors continues to increase and significant focus has been placed on advanced nuclear reactors intended to produce electricity and process heat. However, there is limited literature on the importance of research reactors and certain specialized reactor analysis topics. Thus, this book addresses these topics over three sections: “Nuclear Reactors for Spacecraft Propulsion”, “Research Reactors”, and “Select Reactor Analysis Techniques”. It provides detailed information on the use of nuclear reactors for spacecraft propulsion, presents research conducted on reactors in Idaho, USA, and discusses reactor analysis topics such as cyber-informed engineering for nuclear reactor digital instrumentation and control, the effect of plenum gas on fuel temperature, and more.
Book Synopsis Comprehensive Nuclear Materials by :
Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1985 with total page 272 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutronics Methods for Transient and Safety Analysis of Fast Reactors by : Marchetti, Marco
Download or read book Neutronics Methods for Transient and Safety Analysis of Fast Reactors written by Marchetti, Marco and published by KIT Scientific Publishing. This book was released on 2017-03-02 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis SASSYS/EBR-II Primary and Secondary System Models by : James P. Herzog
Download or read book SASSYS/EBR-II Primary and Secondary System Models written by James P. Herzog and published by . This book was released on 1993 with total page 250 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal Hydraulics of Severe Accidents by : R. M. Singer
Download or read book Thermal Hydraulics of Severe Accidents written by R. M. Singer and published by . This book was released on 1992 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1984-03 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt:
