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Tuesday, May 19, 2020 | History

3 edition of Identification and evaluation of PWR in-vessel severe accident management strategies found in the catalog.

Identification and evaluation of PWR in-vessel severe accident management strategies

J. S Dukelow

Identification and evaluation of PWR in-vessel severe accident management strategies

by J. S Dukelow

  • 305 Want to read
  • 23 Currently reading

Published by Supt. of Docs., U.S. G.P.O. [distributor] .
Written in English


The Physical Object
FormatUnknown Binding
ID Numbers
Open LibraryOL10109600M
ISBN 100160365864
ISBN 109780160365867
OCLC/WorldCa27730429

Long term SBO in a pressurized water reactor (PWR) leads to severe accident sequences, assuming that existing plant means (systems, equipment and procedures) are used for accident mitigation. Therefore the main objective was to study the accident management strategies for SBO scenarios (with different reactor coolant pumps (RCPs) leaks assumed. Michal asks Nichita are what inspired him to write the book and how Rouben became involved in the project. Nichita notes that he sees the book as a companion to be used in addition to a text - book in the teaching of a reactor physics course. To read this interview, turn to page The second book, by Ann Winters, is a biography titled. Un-File Size: 24MB.

Sodium Fast Reactors with Closed Fuel Cycle delivers a detailed discussion of an important technology that is being harnessed for commercial energy production in many parts of the world. Presenting the state of the art of sodium-cooled fast reactors with closed fuel cycles, this book: Offers in-depth coverage of reactor physics, materials, design, safety analysis, validations, engineering. Severe accident management (SAM) strategies are coming into the focus of nuclear safety investigations after the Fukushima accident. The main goal of these strategies is to prevent the release of radioactive fission products in the environment.

Code uses include analyses required to support rulemaking and licensing, audit calculations, evaluation of accident-mitigation strategies, evaluation of operator guidelines, and experiment-planning analysis. Relap5 has also been used as the basis of a nuclear plant analyzer. He has over journal articles, book chapters, conference papers, and technical reports, and has taught 35 short courses in the field of verification and validation. He recently co-authored, with Christopher Roy, the book Verification and Validation in Scientific Computing published by Cambridge University Press.


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Identification and evaluation of PWR in-vessel severe accident management strategies by J. S Dukelow Download PDF EPUB FB2

@article{osti_, title = {Identification and evaluation of PWR in-vessel severe accident management strategies}, author = {Dukelow, J S and Harrison, D G and Morgenstern, M}, abstractNote = {This reports documents work performed the NRC/RES Accident Management Guidance Program to evaluate possible strategies for mitigating the consequences of PWR severe accidents.

Get this from a library. Identification and evaluation of PWR in-vessel severe accident management strategies. [J S Dukelow; D G Harrison; M H Morgenstern; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Pacific Northwest Laboratory.].

The severe accident at the Fukushima-Daiichi nuclear power plant (NPP) has led to a worldwide review of nuclear safety approaches and is bringing a refocussing of R&D in the field.

@article{osti_, title = {Application of MELCOR Code to a French PWR MWe Severe Accident Sequence and Evaluation of Models Performance Focusing on In-Vessel Thermal Hydraulic Results}, author = {De Rosa, Felice}, abstractNote = {In the ambit of the Severe Accident Network of Excellence Project (SARNET), funded by the European Union, 6.

Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes focused on in-vessel severe accident phenomena; with a. This paper first presents the phenomenology associated to the transient molten pool stratification and the model implemented in the severe accident integral code ASTEC (Accident Source Term Evaluation Code) to evaluate this kinetics.

Then, evaluations are presented, based on a typical PWR reactor configuration. LEVEL 2 PSA METHODOLOGY AND SEVERE ACCIDENT MANAGEMENT Prepared by the CNRA Working Group on Inspection Practices (WGIP) plenum and even the steam generator can have a significant effect upon in-vessel severe accident Severe Accident Management Strategies, NEA/CSNI/R(95)3, Stockholm, File Size: 1MB.

Introduction. Comprehensive reviews on severe accident (SA) phenomenology have been published from time to time. The most recent and important one is “Bal Raj Sehgal, Nuclear Safety in Light Water Reactors: Severe Accident Phenomenology, SARNET, ”The current review attempts to focus on the chemistry under SA conditions, updated after the Fukushima Daiichi Nuclear Power.

As a result of the research enhanced after the TMI-2 accident, there has been a significant increase in the ability to understand and model severe accident (SA) phenomena and to apply the resulting SA codes to the analysis of plants during SA ant trends have been identified through a wide range of experiments, examination of the TMI-2 core and vessel (), as well as analysis.

Most of the actors involved in severe accident research in Europe, plus Canada, Korea and the United States (41 partners), will network in SARNET2 (Severe Accident Research NETwork of Excellence - Phase 2) their capacities of research in order to resolve important pending issues on postulated severe accidents of existing and future Nuclear Power Plants (NPPs).

This paper depicts an approach to demonstrate the equipment survivability under severe accident conditions by taking passive pressurized water reactor CAP as an instance, including screening of severe accident sequences, determination of bounding environment conditions within containment, equipments identification used for severe accident Author: Jinquan Yan, Shanhu Xue, Lin Tian, Wei Lu.

TMSR Fuel Cycle Evaluation Under a Screening and Decision-Making Framework. Wu Jian-hui, Chen Jin-gen, Research on Severe Accident Management Strategies of Spent Fuel Pool.

Jiang Pingting, Liu Chunrong, Liu Wang, In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches. Mixing During a PWR Severe Accident”, NUREG, May Ref. 5: “CFD Predictions of Severe Accident Steam Generator Flows in a 1/7th Scale Pressurized Water Reactor”, Tenth International Conference on Nuclear Engineering, ICONE, AprilArlington, Virginia.

Thermal Fatigue in Stratified Flows. Severe Accident Research and Management in Nordic Countries - A Status Report: Tools for forming strategies for remediation of forests and park areas in northern Europe after radioactive contamination: background and techniques: A Study on Hydrogen Deflagration for Selected Severe Accident Sequences in.

Invited lectures - 2. Safety Improvements of Operating PWR Reactors in EU. Stanislav Rožman, Janez Krajnc, Božidar Krajnc. 1 Nuklearna elektrarna Krško, Vrb Krško, Slovenia. After Fukushima accident instress tests were required to be carried out on nuclear power plants and EU countries have developed and submitted to ENSREG the so called National Action.

Plant Layout for a MWe Direct Brayton Cycle GFR (English) Evaluation of In-Vessel Severe Accident Management Strategies by Using SCDAP/RELAP5. Park, R.-J. / Hong, S.-W. / Kim, S.-B. / Kim, Material Identification in Finite Cylindrical Geometries Using the Schwinger Inverse Method.

TITLE: ACCIDENT SEQUENCE EVALUATION FY 85 FY 86 FY 87 CONTRACTOR: Idaho National BUDGET Engineering Laboratory OBJECTIVE: Provides updated LWR accident sequence information for the NRC reference plan and extend the information for all operating and near-term operating plants to support NRC/IDCOR interface on severe accident.

Comparison of Severe Accident Results by Using MAAP5 and MAAP4 Codes. Te-Chuan Wang. ICONE ; Assessment of Early-Phase Accident Management Strategies in a Station Blackout Scenario for VVER Reactors.

Polina Tusheva, Analysis of PRHRS for an Integral Pressurized Water Reactor Using RELAP5/MOD Xuhua Ye, Minjun Peng. Evaluation of Power Peaking Factor in VVER Using MCNP (English) Plant-Specific Severe Accident Management Strategies Development for Pressurized Heavy Water Reactor.

Choi, Y. / Park, Development of a 1D Pressurized Water Reactor Benchmark Specification. Douglass, S. / Rahnema, F. Severe accident management strategies aim at protecting the containment during the accident progression: the L2 PSA teams shall identify precisely what is needed for this purpose (reactor building integrity, pipes and penetration tightness, primary circuit depressurization equipment, containment venting, instrumentation, recombiners, valves.

Full text of "Development of fission-products transport model in severe-accident scenarios for SCDAP/RELAPS" See other formats.A special session was devoted to the EU IVMR (In-Vessel Melt Retention Severe Accident Management Strategy for Existing and Future NPPs) project.

The review meeting was jointly organized by KIT from Germany and CEA from France in Puerto de la Cruz in Spain from Development of Hydrogen Treatment System in Severe Accident: Part 2 — Study on Reaction Characteristic of a Hydrogen Processing Unit Chikako Iwaki, Daigo Kittaka, Toshihiro Yoshii, Motoshige Yagyu, Masato Okamura, Masashi Tanabe, Fumihiko Ishibashi.