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Preliminary Safety Evaluation Of The Advanced Burner Test Reactor
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Book Synopsis Preliminary Safety Evaluation of the Advanced Burner Test Reactor by : T. H. Fanning
Download or read book Preliminary Safety Evaluation of the Advanced Burner Test Reactor written by T. H. Fanning and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Results of a preliminary safety evaluation of the Advanced Burner Test Reactor (ABTR) pre-conceptual design are reported. The ABTR safety design approach is described. Traditional defense-in-depth design features are supplemented with passive safety performance characteristics that include natural circulation emergency decay heat removal and reactor power reduction by inherent reactivity feedbacks in accidents. ABTR safety performance in design-basis and beyond-design-basis accident sequences is estimated based on analyses. Modeling assumptions and input data for safety analyses are presented. Analysis results for simulation of simultaneous loss of coolant pumping power and normal heat rejection are presented and discussed, both for the case with reactor scram and the case without reactor scram. The analysis results indicate that the ABTR pre-conceptual design is capable of undergoing bounding design-basis and beyond-design-basis accidents without fuel cladding failures. The first line of defense for protection of the public against release of radioactivity in accidents remains intact with significant margin. A comparison and evaluation of general safety design criteria for the ABTR conceptual design phase are presented in an appendix. A second appendix presents SASSYS-1 computer code capabilities and modeling enhancements implemented for ABTR analyses.
Book Synopsis Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, for U.S. Department of Energy, Fast Flux Test Facility, Project No. 448 by : U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
Download or read book Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, for U.S. Department of Energy, Fast Flux Test Facility, Project No. 448 written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1978 with total page 434 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design: Appendices by :
Download or read book Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design: Appendices written by and published by . This book was released on 1994 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission in the Matter New England Power Company, NEP Nuclear Generating Station, Unit Nos. 1 and 2, Docket Nos. STN 50-568 and STN 50-569 by : U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
Download or read book Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission in the Matter New England Power Company, NEP Nuclear Generating Station, Unit Nos. 1 and 2, Docket Nos. STN 50-568 and STN 50-569 written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1978 with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Supplement No. 3 to the Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, in the Matter of Public Service Electric and Gas Company, Et Al., Salem Nuclear Generating Station, Unit 2, Docket No. 50-311 by : U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
Download or read book Supplement No. 3 to the Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, in the Matter of Public Service Electric and Gas Company, Et Al., Salem Nuclear Generating Station, Unit 2, Docket No. 50-311 written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1978 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Preliminary Safety Analysis Report on the Argonne Advanced Research Reactor by : L. W. Fromm
Download or read book Preliminary Safety Analysis Report on the Argonne Advanced Research Reactor written by L. W. Fromm and published by . This book was released on 1968 with total page 638 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, in the Matter of Public Service Company of Oklahoma, Et Al., Black Fox Station, Units 1 and 2, Docket Nos. Stn. 50-556 and Stn. 50-557 by : U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
Download or read book Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, in the Matter of Public Service Company of Oklahoma, Et Al., Black Fox Station, Units 1 and 2, Docket Nos. Stn. 50-556 and Stn. 50-557 written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1978 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Criticality Safety Evaluation for the Advanced Test Reactor U-Mo Demonstration Elements by :
Download or read book Criticality Safety Evaluation for the Advanced Test Reactor U-Mo Demonstration Elements written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Reduced Enrichment Research Test Reactors (RERTR) fuel development program is developing a high uranium density fuel based on a (LEU) uranium-molybdenum alloy. Testing of prototypic RERTR fuel elements is necessary to demonstrate integrated fuel performance behavior and scale-up of fabrication techniques. Two RERTR-Full Size Demonstration fuel elements based on the ATR-Reduced YA elements (all but one plate fueled) are to be fabricated for testing in the Advanced Test Reactor (ATR). The two fuel elements will be irradiated in alternating cycles such that only one element is loaded in the reactor at a time. Existing criticality analyses have analyzed Standard (HEU) ATR elements (all plates fueled) from which controls have been derived. This criticality safety evaluation (CSE) documents analysis that determines the reactivity of the Demonstration fuel elements relative to HEU ATR elements and shows that the Demonstration elements are bound by the Standard HEU ATR elements and existing HEU ATR element controls are applicable to the Demonstration elements.
Book Synopsis Preliminary Core Design Studies for the Advanced Burner Reactor Over a Wide Range of Conversion Ratios by :
Download or read book Preliminary Core Design Studies for the Advanced Burner Reactor Over a Wide Range of Conversion Ratios written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A consistent set of designs for 1000 MWt commercial-scale sodium-cooled Advance Burner Reactors (ABR) have been developed for both metal and oxide-fueled cores with conversion ratios from breakeven (CR=1.0) to fertile-free (CR=0.0). These designs are expected to satisfy thermal and irradiation damage limits based on the currently available data. The very low conversion ratio designs require fuel that is beyond the current fuel database, which is anticipated to be qualified by and for the Advanced Burned Test Reactor. Safety and kinetic parameters were calculated, but a safety analysis was not performed. Development of these designs was required to achieve the primary goal of this study, which was to generate representative fuel cycle mass flows for system studies of ABRs as part of the Global Nuclear Energy Partnership (GNEP). There are slight variations with conversion ratio but the basic ABR configuration consists of 144 fuel assemblies and between 9 and 22 primary control assemblies for both the metal and oxide-fueled cores. Preliminary design studies indicated that it is feasible to design the ABR to accommodate a wide range of conversion ratio by employing different assembly designs and including sufficient control assemblies to accommodate the large reactivity swing at low conversion ratios. The assemblies are designed to fit within the same geometry, but the size and number of fuel pins within each assembly are significantly different in order to achieve the target conversion ratio while still satisfying thermal limits. Current irradiation experience would allow for a conversion ratio of somewhat below 0.75. The fuel qualification for the first ABR should expand this experience to allow for much lower conversion ratios and higher bunrups. The current designs were based on assumptions about the performance of high and very high enrichment fuel, which results in significant uncertainty about the details of the designs. However, the basic fuel cycle performance trends such as conversion ratio and mass flow parameters are less sensitive to these parameters and the current results should provide a good basis for static and dynamic system analysis. The conversion ratio is fundamentally a ratio of the macroscopic cross section of U-238 capture to that of TRU fission. Since the microscopic cross sections only change moderately with fuel design and isotopic concentration for the fast reactor, a specific conversion ratio requires a specific enrichment. The approximate average charge enrichment (TRU/HM) is 14%, 21%, 33%, 56%, and 100% for conversion ratios of 1.0, 0.75, 0.50, 0.25, and 0.0 for the metal-fueled cores. The approximate average charge enrichment is 17%, 25%, 38%, 60%, and 100% for conversion ratios of 1.0, 0.75, 0.50, 0.25, and 0.0 for the oxide-fueled core. For the split batch cores, the maximum enrichment will be somewhat higher. For both the metal and oxide-fueled cores, the reactivity feedback coefficients and kinetics parameters seem reasonable. The maximum single control assembly reactivity faults may be too large for the low conversion ratio designs. The average reactivity of the primary control assemblies was increased, which may cause the maximum reactivity of the central control assembly to be excessive. The values of the reactivity coefficients and kinetics parameters show that some values appear to improve significantly at lower conversion ratios while others appear far less favorable. Detailed safety analysis is required to determine if these designs have adequate safety margins or if appropriate design modifications are required. Detailed system analysis data has been generated for both metal and oxide-fueled core designs over the entire range of potential burner reactors. Additional data has been calculated for a few alternative fuel cycles. The systems data has been summarized in this report and the detailed data will be provided to the systems analysis team so that static and dynamic system analyses can be performed.
Book Synopsis Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design: Appendices by :
Download or read book Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design: Appendices written by and published by . This book was released on 1994 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis PRELIMINARY SAFETY ANALYSIS REPORT ON THE ARGONNE ADVANCED RESEARCH REACTOR. by :
Download or read book PRELIMINARY SAFETY ANALYSIS REPORT ON THE ARGONNE ADVANCED RESEARCH REACTOR. written by and published by . This book was released on 1968 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design. Volume 1: Main Report by :
Download or read book Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design. Volume 1: Main Report written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR [section] 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.
Book Synopsis Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design. Supplement 1 by :
Download or read book Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design. Supplement 1 written by and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report supplements the final safety evaluation report (FSER) for the US Advanced Boiling Water Reactor (ABWR) standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1503 in July 1994 to document the NRC staff's review of the US ABWR design. The US ABWR design was submitted by GE Nuclear Energy (GE) in accordance with the procedures of Subpart B to Part 52 of Title 10 of the Code of Federal Regulations. This supplement documents the NRC staff's review of the changes to the US ABWR design documentation since the issuance of the FSER. GE made these changes primarily as a result of first-of-a-kind-engineering (FOAKE) and as a result of the design certification rulemaking for the ABWR design. On the basis of its evaluations, the NRC staff concludes that the confirmatory issues in NUREG-1503 are resolved, that the changes to the ABWR design documentation are acceptable, and that GE's application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the US ABWR design.
Book Synopsis Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, in the Matter of Westinghouse Electric Corporation Reference Safety Analysis Report, RESAR-414, Docket No. STN 50-572 by : U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
Download or read book Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, in the Matter of Westinghouse Electric Corporation Reference Safety Analysis Report, RESAR-414, Docket No. STN 50-572 written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1978 with total page 348 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Interim Safety Evaluation Report by the Office of Nuclear Reactor Regulation, United States Nuclear Regulatory Commission, in the Matter of the San Diego Gas and Electric Company, Sundesert Nuclear Plan, Units 1 and 2, Docket Nos. 50-582 and 50-583 by : U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
Download or read book Interim Safety Evaluation Report by the Office of Nuclear Reactor Regulation, United States Nuclear Regulatory Commission, in the Matter of the San Diego Gas and Electric Company, Sundesert Nuclear Plan, Units 1 and 2, Docket Nos. 50-582 and 50-583 written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1978 with total page 324 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design. Volume 2: Appendices by :
Download or read book Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design. Volume 2: Appendices written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR [section] 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.
Book Synopsis Interim Safety Evaluation Report by the Office of Nuclear Reactor Regulation, United States Nuclear Regulatory Commission, in the Matter of the Detroit Edison Company, Enrico Fermi Atomic Power Plant, Unit 2, Docket No. 50-341 by : U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
Download or read book Interim Safety Evaluation Report by the Office of Nuclear Reactor Regulation, United States Nuclear Regulatory Commission, in the Matter of the Detroit Edison Company, Enrico Fermi Atomic Power Plant, Unit 2, Docket No. 50-341 written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1977 with total page 214 pages. Available in PDF, EPUB and Kindle. Book excerpt:
