LMFBR Safety and Sodium Boiling

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis LMFBR Safety and Sodium Boiling by :

Download or read book LMFBR Safety and Sodium Boiling written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Within the U.S. Fast Breeder Reactor Safety R and D Work Breakdown Structure for Line of Assurance 2, Limit Core Damage, the influence of sodium boiling upon the progression and termination of accidents is being studied in loss of flow, transient overpower, loss of piping integrity, loss of shutdown heat removal system and local fault situations. The pertinent analytical and experimental results of this research to date are surveyed and compared with the requirements for demonstrating the effectiveness of this line of assurance. A discussion of specific technical issues concerned with sodium boiling and the need for future development work is also presented.

Comparison of One- and Two-dimensional Sodium-boiling Models. [LMFBR].

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Comparison of One- and Two-dimensional Sodium-boiling Models. [LMFBR]. by :

Download or read book Comparison of One- and Two-dimensional Sodium-boiling Models. [LMFBR]. written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Prediction of sodium boiling and dryout in the fuel subassemblies of a Liquid Metal Fast Breeder Reactor (LMFBR) under certain accident aconditions is of paramount importance in LMFBR safety. In the present paper, boiling and dryout calculations performed by two computer codes, one-dimensional (1-D), LOOP-1 and two-dimensional (2-D), THORAX are presented and compared with experimental data.

Two-dimensional Modeling of Sodium Boiling in a Simulated LMFBR Loss-of-flow Test

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Two-dimensional Modeling of Sodium Boiling in a Simulated LMFBR Loss-of-flow Test by :

Download or read book Two-dimensional Modeling of Sodium Boiling in a Simulated LMFBR Loss-of-flow Test written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Loss-of-flow (LOF) accidents are of major importance in LMFBR safety. Tests have been performed to simulate the simultaneous failure of all primary pumps and reactor shutdown systems in a 37-pin electrically heated test bundle installed in the KNS sodium boiling loop at the Institute of Reactor Development, Karlsruhe. The tests simulated LOF conditions of the German prototype LMFBR, the SNR 300. The main objectives of these tests were to characterize the transient boiling development to cladding dryout and to provide data for validation of sodium boiling codes. One particular LOF test, designated L22, at full power was selected as a benchmark exercise for comparison of several codes at the Eleventh Meeting of the Liquid Metal Boiling Working Group (LMBWG) held in Grenoble, France, in October 1984. In this paper, the results of the calculations performed at ORNL with the two-dimensional (2-D) boiling code THORAX are presented.

Quarterly Technical Progress Report

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ISBN 13 :
Total Pages : 62 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Quarterly Technical Progress Report by : Rockwell International. Atomics International Division

Download or read book Quarterly Technical Progress Report written by Rockwell International. Atomics International Division and published by . This book was released on 1970 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:

LMFBR Safety

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis LMFBR Safety by :

Download or read book LMFBR Safety written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The objectives of this project are to: develop a computer program for calculating two-dimensional, transient, natural convection phenomena such as those arising from various sodium spill accidents in Liquid Metal Fast Breeder Reactor (LMFBR) heat transfer equipment vaults, head compartments, containment buildings, and secondary heat transfer systems; develop experimental programs and conduct tests that will characterize the behavior of sodium, sodium oxide, fuel, fission product, and other aerosols as they might be generated by various postulated LMFBR accidents; determine by analysis and experiment the generation and transport of these aerosols; and determine the effects of an accident in an LMFBR involving fuel melting by contacting molten UO2 (a fuel simulant) with stainless steel, sodium, concrete, and various sacrificial materials.

Sodium Boiling Experiments Relevant to Fast Reactor Safety

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ISBN 13 :
Total Pages : 20 pages
Book Rating : 4.:/5 (353 download)

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Book Synopsis Sodium Boiling Experiments Relevant to Fast Reactor Safety by : N. Sheriff

Download or read book Sodium Boiling Experiments Relevant to Fast Reactor Safety written by N. Sheriff and published by . This book was released on 1978 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 680 pages
Book Rating : 4.E/5 ( download)

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Book Synopsis Nuclear Science Abstracts by :

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 680 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Procedures and Instrumentation for Sodium Boiling Experiments in EBR-II.

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (873 download)

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Book Synopsis Procedures and Instrumentation for Sodium Boiling Experiments in EBR-II. by :

Download or read book Procedures and Instrumentation for Sodium Boiling Experiments in EBR-II. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The development of instrumentation capable of detecting localized coolant boiling in a liquid metal cooled breeder reactor (LMFBR) has a high priority in fast reactor safety. The detection must be rapid enough to allow corrective action to be taken before significant damage occurs to the core. To develop and test a method of boiling detection, it is desirable to produce boiling in a reactor and thereby introduce a condition in the reactor the original design concepts were chosen to preclude. The proposed boiling experiments are designed to safely produce boiling in the subassembly of a fast reactor and provide the information to develop boiling detection instrumentation without core damage or safety compromise. The experiment consists of the operation of two separate subassemblies, first, a gamma heated boiling subassembly which produces non-typical but highly conservative boiling and then a fission heated subassembly which simulates a prototypical boiling event. The two boiling subassemblies are designed to operate in the instrumentation subassembly test facility (INSAT) of Experiment Breeder Reactor II (EBR-II).

Sodium Boiling in LMFBR Fuel Assemblies. Progress Report

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (873 download)

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Book Synopsis Sodium Boiling in LMFBR Fuel Assemblies. Progress Report by :

Download or read book Sodium Boiling in LMFBR Fuel Assemblies. Progress Report written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Objective is to improve current understanding of sodium voiding behavior under postulated LMFBR accident conditions. Multi-dimensional computer models are being developed under low flow and low power conditions. The following computer codes are being developed and assessed: NATOF-2D, THERMIT-S-6E, and THERMIT-S-4E. The effect of virtual mass on the characteristics and numerical stability in two-phase flows was studied. (DLC).

Post-test Analysis of Dryout Test 7B' of the W-1 Sodium Loop Safety Facility Experiment with the SABRE-2P Code. [LMFBR].

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Post-test Analysis of Dryout Test 7B' of the W-1 Sodium Loop Safety Facility Experiment with the SABRE-2P Code. [LMFBR]. by :

Download or read book Post-test Analysis of Dryout Test 7B' of the W-1 Sodium Loop Safety Facility Experiment with the SABRE-2P Code. [LMFBR]. written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An understanding of conditions that may cause sodium boiling and boiling propagation that may lead to dryout and fuel failure is crucial in liquid-metal fast-breeder reactor safety. In this study, the SABRE-2P subchannel analysis code has been used to analyze the ultimate transient of the in-core W-1 Sodium Loop Safety Facility experiment. This code has a 3-D simple nondynamic boiling model which is able to predict the flow instability which caused dryout. In other analyses dryout has been predicted for out-of-core test bundles and so this study provides additional confirmation of the model.

Safety Problems of Liquid-metal-cooled Fast Breeder Reactors

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ISBN 13 :
Total Pages : 220 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Safety Problems of Liquid-metal-cooled Fast Breeder Reactors by : C. N. Kelber

Download or read book Safety Problems of Liquid-metal-cooled Fast Breeder Reactors written by C. N. Kelber and published by . This book was released on 1970 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Little Low-power Boiling Never Hurt Anybody. [LMFBR].

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Little Low-power Boiling Never Hurt Anybody. [LMFBR]. by :

Download or read book Little Low-power Boiling Never Hurt Anybody. [LMFBR]. written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Failures in the shutdown heat removal system of an LMFBR might lead to flow stagnation and coolant boiling in the reactor core. At normal operating power, the onset of sodium boiling will lead to film dryout and melting of the cladding and fuel within a few seconds. On the other hand, both calculations and currently available experimental data indicate that at heat fluxes corresponding to decay heat power levels, boiling leads to improved heat removal; and it limits the temperature rise in the fuel pins. Therefore, when setting safety criteria for decay heat removal systems, there is no reason to preclude sodium boiling per se because of heat removal considerations. As an example that illustrates the beneficial impact of coolant boiling, a case involving temporary loss of feedwater and staggered pump failures in a hypothetical, 1000-MWe loop-type reactor was run in the SASSYS-1 code.

Fast Reactor Safety

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Publisher : Elsevier
ISBN 13 : 0323152651
Total Pages : 390 pages
Book Rating : 4.3/5 (231 download)

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Book Synopsis Fast Reactor Safety by : John Graham

Download or read book Fast Reactor Safety written by John Graham and published by Elsevier. This book was released on 2012-12-02 with total page 390 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fast Reactor Safety deals with safety design criteria and methodology for fast reactors. Topics covered include safety evaluation methods, system disturbances, containment, and licensing. The characteristics of fast reactors, including heat ratings and coolants, are also discussed. Comprised of six chapters, this book opens with an overview of methods used to evaluate nuclear safety, along with neutron kinetics, thermal and feedback effects, and fault tree analysis. The reader is then introduced to possible system disturbances in relation to three distinct fast reactor systems: liquid-metal-cooled fast breeder reactors, gas-cooled fast breeder reactors, and steam-cooled fast breeder reactors. The next chapter looks at safety criteria that are set to define the design of a safe plant, together with the safety features that might be included. The remaining chapters focus on the particular problems of a sodium-cooled design; containment building and primary circuit and vessel containment; and licensing of the plant. This monograph is intended for graduates and undergraduates in nuclear engineering who are attending courses in reactor safety.

Two-dimensional Computational Modeling of Sodium Boiling in Simulated LMFBR Fuel-pin Bundles

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Two-dimensional Computational Modeling of Sodium Boiling in Simulated LMFBR Fuel-pin Bundles by :

Download or read book Two-dimensional Computational Modeling of Sodium Boiling in Simulated LMFBR Fuel-pin Bundles written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Extensive sodium boiling tests have been carried out in two simulated LMFBR fuel pin bundles in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility at Oak Ridge National Laboratory. Experimental results from a 19-pin bundle (THORS Bundle 6A) have been previously reported, and experimental results from a 61-pin bundle (THORS Bundle 9) will be reported soon. The results discussed here are from the 19-pin bundle. Preliminary analysis has shown that the computational methods used and conclusions reached are equally valid for the 61-pin bundle, as well as the 19-pin in-reactor Sodium Loop Safety Facility (SLSF) W-1 experiment. The main result of THORS sodium boiling experimentation is that boiling behavior is determined by two-dimensional effects, i.e., the rates of mass, momentum and energy transfer in the direction perpendicular to the axes of the fuel pins.

LMFBR Safety

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ISBN 13 :
Total Pages : 548 pages
Book Rating : 4.3/5 ( download)

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Book Synopsis LMFBR Safety by : J. R. Buchanan

Download or read book LMFBR Safety written by J. R. Buchanan and published by . This book was released on 1976 with total page 548 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Liquid Metal Fast Breeder Reactor (LMFBR) Demonstration Plant

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ISBN 13 :
Total Pages : 284 pages
Book Rating : 4.:/5 (319 download)

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Book Synopsis Liquid Metal Fast Breeder Reactor (LMFBR) Demonstration Plant by : United States. Congress. Joint Committee on Atomic Energy

Download or read book Liquid Metal Fast Breeder Reactor (LMFBR) Demonstration Plant written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1972 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Energy Research Abstracts

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ISBN 13 :
Total Pages : 548 pages
Book Rating : 4.3/5 (129 download)

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Book Synopsis Energy Research Abstracts by :

Download or read book Energy Research Abstracts written by and published by . This book was released on 1978 with total page 548 pages. Available in PDF, EPUB and Kindle. Book excerpt: