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You searched for subject:(DRACS FHR RELAP5 AHTR). Showing records 1 – 30 of 43 total matches.

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The Ohio State University

1. Lin, Hsun-Chia. RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities.

Degree: MS, Nuclear Engineering, 2016, The Ohio State University

 Direct Reactor Auxiliary Cooling System (DRACS), a passive safety system proposed for Fluoride-salt-cooled High-temperature Reactors (FHRs), is driven by natural convection/circulation to remove the decay… (more)

Subjects/Keywords: Nuclear Engineering; DRACS, FHR, RELAP5, AHTR

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APA (6th Edition):

Lin, H. (2016). RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1462889408

Chicago Manual of Style (16th Edition):

Lin, Hsun-Chia. “RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities.” 2016. Masters Thesis, The Ohio State University. Accessed March 21, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1462889408.

MLA Handbook (7th Edition):

Lin, Hsun-Chia. “RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities.” 2016. Web. 21 Mar 2019.

Vancouver:

Lin H. RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities. [Internet] [Masters thesis]. The Ohio State University; 2016. [cited 2019 Mar 21]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1462889408.

Council of Science Editors:

Lin H. RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities. [Masters Thesis]. The Ohio State University; 2016. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1462889408


The Ohio State University

2. Lu, Qiuping. Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs.

Degree: PhD, Nuclear Engineering, 2016, The Ohio State University

 Direct Reactor Auxiliary Cooling System (DRACS) is a passive decay heat removal system proposed for the Fluoride-salt-cooled High-temperature Reactor (FHR) that combines coated particle fuel… (more)

Subjects/Keywords: Nuclear Engineering; FHR, DRACS, passive decay heat removal, LTDF, HTDF

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APA (6th Edition):

Lu, Q. (2016). Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1462544389

Chicago Manual of Style (16th Edition):

Lu, Qiuping. “Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs.” 2016. Doctoral Dissertation, The Ohio State University. Accessed March 21, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1462544389.

MLA Handbook (7th Edition):

Lu, Qiuping. “Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs.” 2016. Web. 21 Mar 2019.

Vancouver:

Lu Q. Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs. [Internet] [Doctoral dissertation]. The Ohio State University; 2016. [cited 2019 Mar 21]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1462544389.

Council of Science Editors:

Lu Q. Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs. [Doctoral Dissertation]. The Ohio State University; 2016. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1462544389

3. Lv, Qiuping. Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs.

Degree: MS, Nuclear Engineering, 2013, The Ohio State University

 The Advanced High Temperature Reactor (AHTR) is one of the advanced rector concepts that have been proposed for Gen IV reactors. The AHTR combines four… (more)

Subjects/Keywords: Nuclear Engineering; AHTR; DRACS; prototypic design; scaling

…Sabharwall, “Design of a Scaled-down DRACS Test Facility for an AHTR,” Transaction of the American… …temperature DRACS Test Facility for an AHTR,” Transactions of the American Nuclear Society, Vol. 106… …safety system, DRACS. However, a detailed design of the DRACS for the baseline 900-MWth PB-AHTR… …FHR output temperatures. FLiBe is selected as the primary salt, the same as in PB-AHTR… …Sabharwall, “A MATLAB Code for Thermal Performance Evaluation of a LowTemperature DRACS Test… 

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APA (6th Edition):

Lv, Q. (2013). Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1357312725

Chicago Manual of Style (16th Edition):

Lv, Qiuping. “Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs.” 2013. Masters Thesis, The Ohio State University. Accessed March 21, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1357312725.

MLA Handbook (7th Edition):

Lv, Qiuping. “Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs.” 2013. Web. 21 Mar 2019.

Vancouver:

Lv Q. Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs. [Internet] [Masters thesis]. The Ohio State University; 2013. [cited 2019 Mar 21]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1357312725.

Council of Science Editors:

Lv Q. Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs. [Masters Thesis]. The Ohio State University; 2013. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1357312725

4. Adams , Imani Noel. Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors.

Degree: MS, Mechanical Engineering, 2013, The Ohio State University

  The Direct Reactor Auxiliary Cooling System (DRACS) is a passive heat removal system proposed for Fluoride Salt-Cooled High-Temperature Reactors (FHRs). It features three coupled… (more)

Subjects/Keywords: Mechanical Engineering; Nuclear Engineering; DRACS; FHR

…Sabharwall, “Design of a Scaled-down Low-temperature DRACS Test Facility for an AHTR,” Transactions… …10 Figure 6 Schematic layout of primary system and DRACS system for FHR (Holcomb… …AHTR also goes by Fluoride-Salt-Cooled High Temperature Reactor (FHR) because of… …all of the AHTR is the direct reactor auxiliary cooling system (DRACS). This is a… …DRACS system for FHR (Holcomb, Cetiner, Flanagan, Peretz, & Yoder, 2009) 2.2… 

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APA (6th Edition):

Adams , I. N. (2013). Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1366464705

Chicago Manual of Style (16th Edition):

Adams , Imani Noel. “Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors.” 2013. Masters Thesis, The Ohio State University. Accessed March 21, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1366464705.

MLA Handbook (7th Edition):

Adams , Imani Noel. “Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors.” 2013. Web. 21 Mar 2019.

Vancouver:

Adams IN. Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors. [Internet] [Masters thesis]. The Ohio State University; 2013. [cited 2019 Mar 21]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1366464705.

Council of Science Editors:

Adams IN. Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors. [Masters Thesis]. The Ohio State University; 2013. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1366464705

5. Gentry, Cole Andrew. Development of a Reactor Physics Analysis Procedure for the Plank-Based and Liquid Salt-Cooled Advanced High Temperature Reactor.

Degree: 2016, University of Tennessee – Knoxville

 Presented in this dissertation is the investigation and development of an adapted lattice physics-to-core simulator two-step procedure based on the SERPENT 2 and NESTLE neutronics… (more)

Subjects/Keywords: FHR; AHTR; MSR; Two-Step; TRISO; Diffusion; Nuclear Engineering

…10 1.5. Challenges of Developing AHTR two-step Procedure… …25 2. Development of AHTR two-step Procedure… …27 2.1. Design Specification of AHTR Core… …72 3. Benchmarking of AHTR two-step Procedure… …________________________________________________________________________ Table 1-1 Diffusion Lengths of AHTR compared to LWR Table 2-1 TRISO Particle Description Table… 

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APA (6th Edition):

Gentry, C. A. (2016). Development of a Reactor Physics Analysis Procedure for the Plank-Based and Liquid Salt-Cooled Advanced High Temperature Reactor. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/3695

Chicago Manual of Style (16th Edition):

Gentry, Cole Andrew. “Development of a Reactor Physics Analysis Procedure for the Plank-Based and Liquid Salt-Cooled Advanced High Temperature Reactor.” 2016. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed March 21, 2019. https://trace.tennessee.edu/utk_graddiss/3695.

MLA Handbook (7th Edition):

Gentry, Cole Andrew. “Development of a Reactor Physics Analysis Procedure for the Plank-Based and Liquid Salt-Cooled Advanced High Temperature Reactor.” 2016. Web. 21 Mar 2019.

Vancouver:

Gentry CA. Development of a Reactor Physics Analysis Procedure for the Plank-Based and Liquid Salt-Cooled Advanced High Temperature Reactor. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2016. [cited 2019 Mar 21]. Available from: https://trace.tennessee.edu/utk_graddiss/3695.

Council of Science Editors:

Gentry CA. Development of a Reactor Physics Analysis Procedure for the Plank-Based and Liquid Salt-Cooled Advanced High Temperature Reactor. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2016. Available from: https://trace.tennessee.edu/utk_graddiss/3695

6. Talukder, MD.Hasib Uddin. Modelling of the PACTEL SBL‐50 Transient Using RELAP5 Computer Code.

Degree: 2012, Chalmers University of Technology

 The main purpose of the current Master of Sciences Thesis was modelling of the PACTEL SBL‐50 transient using RELAP5/MOD 3.3 Patch‐04 system thermal hydraulic computer… (more)

Subjects/Keywords: RELAP5; PACTEL; benchmark; simulation; thermal‐hydraulics

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APA (6th Edition):

Talukder, M. H. U. (2012). Modelling of the PACTEL SBL‐50 Transient Using RELAP5 Computer Code. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/178531-modelling-of-the-pactel-sbl50-transient-using-relap5-computer-code

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Talukder, MD Hasib Uddin. “Modelling of the PACTEL SBL‐50 Transient Using RELAP5 Computer Code.” 2012. Thesis, Chalmers University of Technology. Accessed March 21, 2019. http://studentarbeten.chalmers.se/publication/178531-modelling-of-the-pactel-sbl50-transient-using-relap5-computer-code.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Talukder, MD Hasib Uddin. “Modelling of the PACTEL SBL‐50 Transient Using RELAP5 Computer Code.” 2012. Web. 21 Mar 2019.

Vancouver:

Talukder MHU. Modelling of the PACTEL SBL‐50 Transient Using RELAP5 Computer Code. [Internet] [Thesis]. Chalmers University of Technology; 2012. [cited 2019 Mar 21]. Available from: http://studentarbeten.chalmers.se/publication/178531-modelling-of-the-pactel-sbl50-transient-using-relap5-computer-code.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Talukder MHU. Modelling of the PACTEL SBL‐50 Transient Using RELAP5 Computer Code. [Thesis]. Chalmers University of Technology; 2012. Available from: http://studentarbeten.chalmers.se/publication/178531-modelling-of-the-pactel-sbl50-transient-using-relap5-computer-code

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

7. Wångblad, Mattias. Pressure studies in water jet simulations.

Degree: 2011, Chalmers University of Technology

 This thesis studies the forces on a coolant pipe in wetwell from waterjets after a full scale loss-of-coolant-accident(LOCA) in a nuclear reactor. The waterjets are… (more)

Subjects/Keywords: Keywords:LOCA; nuclear safety; Pressure suppression; RELAP5; FLUENT; Jet impingement

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APA (6th Edition):

Wångblad, M. (2011). Pressure studies in water jet simulations. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/152150-pressure-studies-in-water-jet-simulations

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Wångblad, Mattias. “Pressure studies in water jet simulations.” 2011. Thesis, Chalmers University of Technology. Accessed March 21, 2019. http://studentarbeten.chalmers.se/publication/152150-pressure-studies-in-water-jet-simulations.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Wångblad, Mattias. “Pressure studies in water jet simulations.” 2011. Web. 21 Mar 2019.

Vancouver:

Wångblad M. Pressure studies in water jet simulations. [Internet] [Thesis]. Chalmers University of Technology; 2011. [cited 2019 Mar 21]. Available from: http://studentarbeten.chalmers.se/publication/152150-pressure-studies-in-water-jet-simulations.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Wångblad M. Pressure studies in water jet simulations. [Thesis]. Chalmers University of Technology; 2011. Available from: http://studentarbeten.chalmers.se/publication/152150-pressure-studies-in-water-jet-simulations

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

8. Moore, Eugene James Thomas. Relap5-3d model validation and benchmark exercises for advanced gas cooled reactor application.

Degree: 2006, Texas A&M University

 High-temperature gas-cooled reactors (HTGR) are passively safe, efficient, and economical solutions to the world??s energy crisis. HTGRs are capable of generating high temperatures during normal… (more)

Subjects/Keywords: GAS COOLED REACTOR; RELAP5-3D

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APA (6th Edition):

Moore, E. J. T. (2006). Relap5-3d model validation and benchmark exercises for advanced gas cooled reactor application. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/3996

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Moore, Eugene James Thomas. “Relap5-3d model validation and benchmark exercises for advanced gas cooled reactor application.” 2006. Thesis, Texas A&M University. Accessed March 21, 2019. http://hdl.handle.net/1969.1/3996.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Moore, Eugene James Thomas. “Relap5-3d model validation and benchmark exercises for advanced gas cooled reactor application.” 2006. Web. 21 Mar 2019.

Vancouver:

Moore EJT. Relap5-3d model validation and benchmark exercises for advanced gas cooled reactor application. [Internet] [Thesis]. Texas A&M University; 2006. [cited 2019 Mar 21]. Available from: http://hdl.handle.net/1969.1/3996.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Moore EJT. Relap5-3d model validation and benchmark exercises for advanced gas cooled reactor application. [Thesis]. Texas A&M University; 2006. Available from: http://hdl.handle.net/1969.1/3996

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

9. Anderson, Nolan Alan. Coupling RELAP5-3D and Fluent to analyze a Very High Temperature Reactor (VHTR) outlet plenum.

Degree: 2006, Texas A&M University

 The Very High Temperature Reactor (VHTR) system behavior should be predicted during normal operating conditions and during transient conditions. To predict the VHTR system behavior… (more)

Subjects/Keywords: VHTR; RELAP5-3D; Fluent

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APA (6th Edition):

Anderson, N. A. (2006). Coupling RELAP5-3D and Fluent to analyze a Very High Temperature Reactor (VHTR) outlet plenum. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/4160

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Anderson, Nolan Alan. “Coupling RELAP5-3D and Fluent to analyze a Very High Temperature Reactor (VHTR) outlet plenum.” 2006. Thesis, Texas A&M University. Accessed March 21, 2019. http://hdl.handle.net/1969.1/4160.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Anderson, Nolan Alan. “Coupling RELAP5-3D and Fluent to analyze a Very High Temperature Reactor (VHTR) outlet plenum.” 2006. Web. 21 Mar 2019.

Vancouver:

Anderson NA. Coupling RELAP5-3D and Fluent to analyze a Very High Temperature Reactor (VHTR) outlet plenum. [Internet] [Thesis]. Texas A&M University; 2006. [cited 2019 Mar 21]. Available from: http://hdl.handle.net/1969.1/4160.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Anderson NA. Coupling RELAP5-3D and Fluent to analyze a Very High Temperature Reactor (VHTR) outlet plenum. [Thesis]. Texas A&M University; 2006. Available from: http://hdl.handle.net/1969.1/4160

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of Gothenburg / Göteborgs Universitet

10. Blad, Sofia. Fetal reactivity assessment during intrapartum stress by analysis of the fetal ECG signal.

Degree: 2011, University of Gothenburg / Göteborgs Universitet

 Fetal responses to the stress of labour and delivery are constituted by a combination of changes in neuronal, hormonal and organ based reactions. The aim… (more)

Subjects/Keywords: FHR variability; fetal ECG; Asphyxia; Intrauterine infection; Residual method; STAN

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APA (6th Edition):

Blad, S. (2011). Fetal reactivity assessment during intrapartum stress by analysis of the fetal ECG signal. (Thesis). University of Gothenburg / Göteborgs Universitet. Retrieved from http://hdl.handle.net/2077/24626

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Blad, Sofia. “Fetal reactivity assessment during intrapartum stress by analysis of the fetal ECG signal.” 2011. Thesis, University of Gothenburg / Göteborgs Universitet. Accessed March 21, 2019. http://hdl.handle.net/2077/24626.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Blad, Sofia. “Fetal reactivity assessment during intrapartum stress by analysis of the fetal ECG signal.” 2011. Web. 21 Mar 2019.

Vancouver:

Blad S. Fetal reactivity assessment during intrapartum stress by analysis of the fetal ECG signal. [Internet] [Thesis]. University of Gothenburg / Göteborgs Universitet; 2011. [cited 2019 Mar 21]. Available from: http://hdl.handle.net/2077/24626.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Blad S. Fetal reactivity assessment during intrapartum stress by analysis of the fetal ECG signal. [Thesis]. University of Gothenburg / Göteborgs Universitet; 2011. Available from: http://hdl.handle.net/2077/24626

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Penn State University

11. SOLER-MARTINEZ, MARIA DESAMPARADOS. SEMI-IMPLICIT THERMAL-HYDRAULIC COUPLING OF ADVANCED.

Degree: MS, Nuclear Engineering, 2011, Penn State University

 Being able to predict two-phase phenomena transients is a priority for the computer simulation programs used in nuclear safety assessments of Pressurized Water Reactors. System… (more)

Subjects/Keywords: RELAP5/COBRA-TF; semi-implicit coupling; coupling codes

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APA (6th Edition):

SOLER-MARTINEZ, M. D. (2011). SEMI-IMPLICIT THERMAL-HYDRAULIC COUPLING OF ADVANCED. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/11861

Chicago Manual of Style (16th Edition):

SOLER-MARTINEZ, MARIA DESAMPARADOS. “SEMI-IMPLICIT THERMAL-HYDRAULIC COUPLING OF ADVANCED.” 2011. Masters Thesis, Penn State University. Accessed March 21, 2019. https://etda.libraries.psu.edu/catalog/11861.

MLA Handbook (7th Edition):

SOLER-MARTINEZ, MARIA DESAMPARADOS. “SEMI-IMPLICIT THERMAL-HYDRAULIC COUPLING OF ADVANCED.” 2011. Web. 21 Mar 2019.

Vancouver:

SOLER-MARTINEZ MD. SEMI-IMPLICIT THERMAL-HYDRAULIC COUPLING OF ADVANCED. [Internet] [Masters thesis]. Penn State University; 2011. [cited 2019 Mar 21]. Available from: https://etda.libraries.psu.edu/catalog/11861.

Council of Science Editors:

SOLER-MARTINEZ MD. SEMI-IMPLICIT THERMAL-HYDRAULIC COUPLING OF ADVANCED. [Masters Thesis]. Penn State University; 2011. Available from: https://etda.libraries.psu.edu/catalog/11861


Uppsala University

12. Bjorklund, Karl. Comparison between RELAP5 and TRACE for modelling different loads on pipe systems during transient conditions.

Degree: Physics and Astronomy, 2010, Uppsala University

  This is a M. Eng. degree project at Uppsala University carried out at the Forsmark nuclear power plant in Sweden. The purpose of it… (more)

Subjects/Keywords: RELAP5; TRACE; transient conditions; check valve; pipe loads

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APA (6th Edition):

Bjorklund, K. (2010). Comparison between RELAP5 and TRACE for modelling different loads on pipe systems during transient conditions. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-131950

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Bjorklund, Karl. “Comparison between RELAP5 and TRACE for modelling different loads on pipe systems during transient conditions.” 2010. Thesis, Uppsala University. Accessed March 21, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-131950.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Bjorklund, Karl. “Comparison between RELAP5 and TRACE for modelling different loads on pipe systems during transient conditions.” 2010. Web. 21 Mar 2019.

Vancouver:

Bjorklund K. Comparison between RELAP5 and TRACE for modelling different loads on pipe systems during transient conditions. [Internet] [Thesis]. Uppsala University; 2010. [cited 2019 Mar 21]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-131950.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Bjorklund K. Comparison between RELAP5 and TRACE for modelling different loads on pipe systems during transient conditions. [Thesis]. Uppsala University; 2010. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-131950

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

13. Kauppi, Kalle. Krafter på rörsystem vid transient flöde : En jämförelse mellan RELAP5 och Fluent.

Degree: Energy and Environmental Engineering, 2014, University of Gävle

At Forsmarks Kraftgrupp AB (FKA) forces on pipe systems due to transient flow are frequently calculated as a step to verify their structural integrity.… (more)

Subjects/Keywords: RELAP5; Fluent; Flödessimulering; Reaktionskrafter

…11 Figur 5.4: RELAP5 modellering i SNAP, röd box marekerar rörsträcka för kraftberäkning… …12 Figur 6.1: Randvillkor, jämförelse mellan Fluent och RELAP5… …RELAP5 ......... 16 Figur 6.3:Tryck på ett plan vid utlopp från rörsträckan, jämförelse mellan… …Fluent och RELAP5 ........ 16 Figur 6.4: Massflöde, jämförelse mellan olika tidssteg i Fluent… …17 Figur 6.5: Massflöde, jämförelse mellan olika tidssteg i RELAP5… 

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Kauppi, K. (2014). Krafter på rörsystem vid transient flöde : En jämförelse mellan RELAP5 och Fluent. (Thesis). University of Gävle. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-16229

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Kauppi, Kalle. “Krafter på rörsystem vid transient flöde : En jämförelse mellan RELAP5 och Fluent.” 2014. Thesis, University of Gävle. Accessed March 21, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-16229.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Kauppi, Kalle. “Krafter på rörsystem vid transient flöde : En jämförelse mellan RELAP5 och Fluent.” 2014. Web. 21 Mar 2019.

Vancouver:

Kauppi K. Krafter på rörsystem vid transient flöde : En jämförelse mellan RELAP5 och Fluent. [Internet] [Thesis]. University of Gävle; 2014. [cited 2019 Mar 21]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-16229.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Kauppi K. Krafter på rörsystem vid transient flöde : En jämförelse mellan RELAP5 och Fluent. [Thesis]. University of Gävle; 2014. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-16229

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of Michigan

14. Varuttamaseni, Athi. Bayesian Network Representing System Dynamics in Risk Analysis of Nuclear Systems.

Degree: PhD, Nuclear Engineering & Radiological Sciences, 2011, University of Michigan

 A dynamic Bayesian network (DBN) model is used in conjunction with the alternating conditional expectation (ACE) regression method to analyze the risk associated with the… (more)

Subjects/Keywords: RELAP5; Surrogate; Risk Analysis; Nuclear Engineering and Radiological Sciences; Engineering

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APA (6th Edition):

Varuttamaseni, A. (2011). Bayesian Network Representing System Dynamics in Risk Analysis of Nuclear Systems. (Doctoral Dissertation). University of Michigan. Retrieved from http://hdl.handle.net/2027.42/89759

Chicago Manual of Style (16th Edition):

Varuttamaseni, Athi. “Bayesian Network Representing System Dynamics in Risk Analysis of Nuclear Systems.” 2011. Doctoral Dissertation, University of Michigan. Accessed March 21, 2019. http://hdl.handle.net/2027.42/89759.

MLA Handbook (7th Edition):

Varuttamaseni, Athi. “Bayesian Network Representing System Dynamics in Risk Analysis of Nuclear Systems.” 2011. Web. 21 Mar 2019.

Vancouver:

Varuttamaseni A. Bayesian Network Representing System Dynamics in Risk Analysis of Nuclear Systems. [Internet] [Doctoral dissertation]. University of Michigan; 2011. [cited 2019 Mar 21]. Available from: http://hdl.handle.net/2027.42/89759.

Council of Science Editors:

Varuttamaseni A. Bayesian Network Representing System Dynamics in Risk Analysis of Nuclear Systems. [Doctoral Dissertation]. University of Michigan; 2011. Available from: http://hdl.handle.net/2027.42/89759


University of California – Berkeley

15. Wang, Xin. Coupled neutronics and thermal-hydraulics modeling for pebble-bed Fluoride-Salt-Cooled, High-Temperature Reactor (FHR).

Degree: Nuclear Engineering, 2018, University of California – Berkeley

 Advances in computer abilities, intense competition on the energy market and stringent regulatoryrequirements during the last decade have spurred the development of robust numericalmodels to… (more)

Subjects/Keywords: Nuclear engineering; diffusion; FHR; multiphysics; nuclear reactor; pebble bed; porous media

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APA (6th Edition):

Wang, X. (2018). Coupled neutronics and thermal-hydraulics modeling for pebble-bed Fluoride-Salt-Cooled, High-Temperature Reactor (FHR). (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/40q3985m

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Wang, Xin. “Coupled neutronics and thermal-hydraulics modeling for pebble-bed Fluoride-Salt-Cooled, High-Temperature Reactor (FHR).” 2018. Thesis, University of California – Berkeley. Accessed March 21, 2019. http://www.escholarship.org/uc/item/40q3985m.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Wang, Xin. “Coupled neutronics and thermal-hydraulics modeling for pebble-bed Fluoride-Salt-Cooled, High-Temperature Reactor (FHR).” 2018. Web. 21 Mar 2019.

Vancouver:

Wang X. Coupled neutronics and thermal-hydraulics modeling for pebble-bed Fluoride-Salt-Cooled, High-Temperature Reactor (FHR). [Internet] [Thesis]. University of California – Berkeley; 2018. [cited 2019 Mar 21]. Available from: http://www.escholarship.org/uc/item/40q3985m.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Wang X. Coupled neutronics and thermal-hydraulics modeling for pebble-bed Fluoride-Salt-Cooled, High-Temperature Reactor (FHR). [Thesis]. University of California – Berkeley; 2018. Available from: http://www.escholarship.org/uc/item/40q3985m

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

16. Ashdown, Amanda Jane. Categorizing Fetal Heart Rate Variability with and without Visual Aids.

Degree: MS, Psychology, 2015, Old Dominion University

  This present study examined the ability of clinicians and novices to correctly categorize fetal heart rate (FHR) variability with and without the use of… (more)

Subjects/Keywords: Categorization; Exemplars; Experts; FHR variability; Cognitive Psychology; Obstetrics and Gynecology

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Ashdown, A. J. (2015). Categorizing Fetal Heart Rate Variability with and without Visual Aids. (Thesis). Old Dominion University. Retrieved from 9781321768657 ; https://digitalcommons.odu.edu/psychology_etds/1

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Ashdown, Amanda Jane. “Categorizing Fetal Heart Rate Variability with and without Visual Aids.” 2015. Thesis, Old Dominion University. Accessed March 21, 2019. 9781321768657 ; https://digitalcommons.odu.edu/psychology_etds/1.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Ashdown, Amanda Jane. “Categorizing Fetal Heart Rate Variability with and without Visual Aids.” 2015. Web. 21 Mar 2019.

Vancouver:

Ashdown AJ. Categorizing Fetal Heart Rate Variability with and without Visual Aids. [Internet] [Thesis]. Old Dominion University; 2015. [cited 2019 Mar 21]. Available from: 9781321768657 ; https://digitalcommons.odu.edu/psychology_etds/1.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Ashdown AJ. Categorizing Fetal Heart Rate Variability with and without Visual Aids. [Thesis]. Old Dominion University; 2015. Available from: 9781321768657 ; https://digitalcommons.odu.edu/psychology_etds/1

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of New Mexico

17. Rubio, Floren V. Sonomechanical Enhanced Sparging Techniques for Advanced Reactor Applications.

Degree: Nuclear Engineering, 2018, University of New Mexico

  The fluoride salt cooled high temperature reactor (FHR) is a Generation IV advanced reactor design that has potential to produce efficient, low carbon, and… (more)

Subjects/Keywords: Ultrasonics; Sonomechanical enhancement; Flibe; FHR; Tritium; Scaled experiment; Nuclear Engineering

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APA (6th Edition):

Rubio, F. V. (2018). Sonomechanical Enhanced Sparging Techniques for Advanced Reactor Applications. (Doctoral Dissertation). University of New Mexico. Retrieved from https://digitalrepository.unm.edu/ne_etds/73

Chicago Manual of Style (16th Edition):

Rubio, Floren V. “Sonomechanical Enhanced Sparging Techniques for Advanced Reactor Applications.” 2018. Doctoral Dissertation, University of New Mexico. Accessed March 21, 2019. https://digitalrepository.unm.edu/ne_etds/73.

MLA Handbook (7th Edition):

Rubio, Floren V. “Sonomechanical Enhanced Sparging Techniques for Advanced Reactor Applications.” 2018. Web. 21 Mar 2019.

Vancouver:

Rubio FV. Sonomechanical Enhanced Sparging Techniques for Advanced Reactor Applications. [Internet] [Doctoral dissertation]. University of New Mexico; 2018. [cited 2019 Mar 21]. Available from: https://digitalrepository.unm.edu/ne_etds/73.

Council of Science Editors:

Rubio FV. Sonomechanical Enhanced Sparging Techniques for Advanced Reactor Applications. [Doctoral Dissertation]. University of New Mexico; 2018. Available from: https://digitalrepository.unm.edu/ne_etds/73

18. Budziszewski, Anna. CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5.

Degree: 2012, Chalmers University of Technology

 In the Swedish nuclear power plants a structural verificatio of the pipe systems is a necessity to ensure that the pipes are strong enough to… (more)

Subjects/Keywords: Safety relief valve; Computational Fluid Dynamics; RELAP5; Nuclear engineering; Dynamic layering; UDF

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APA (6th Edition):

Budziszewski, A. (2012). CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/178850-cfd-simulation-of-a-safety-relief-valve-for-improvement-of-a-one-dimensional-valve-model-in-relap5

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Budziszewski, Anna. “CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5.” 2012. Thesis, Chalmers University of Technology. Accessed March 21, 2019. http://studentarbeten.chalmers.se/publication/178850-cfd-simulation-of-a-safety-relief-valve-for-improvement-of-a-one-dimensional-valve-model-in-relap5.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Budziszewski, Anna. “CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5.” 2012. Web. 21 Mar 2019.

Vancouver:

Budziszewski A. CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5. [Internet] [Thesis]. Chalmers University of Technology; 2012. [cited 2019 Mar 21]. Available from: http://studentarbeten.chalmers.se/publication/178850-cfd-simulation-of-a-safety-relief-valve-for-improvement-of-a-one-dimensional-valve-model-in-relap5.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Budziszewski A. CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5. [Thesis]. Chalmers University of Technology; 2012. Available from: http://studentarbeten.chalmers.se/publication/178850-cfd-simulation-of-a-safety-relief-valve-for-improvement-of-a-one-dimensional-valve-model-in-relap5

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

19. Thorén, Louise. CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5.

Degree: 2012, Chalmers University of Technology

 In the Swedish nuclear power plants a structural verification of the pipe systems is a necessity to ensure that the pipes are strong enough to… (more)

Subjects/Keywords: Safety relief valve; Computational Fluid Dynamics; RELAP5; Nuclear engineering; Dynamic layering; UDF

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Thorén, L. (2012). CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/159588-cfd-simulation-of-a-safety-relief-valve-for-improvement-of-a-one-dimensional-valve-model-in-relap5

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Thorén, Louise. “CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5.” 2012. Thesis, Chalmers University of Technology. Accessed March 21, 2019. http://studentarbeten.chalmers.se/publication/159588-cfd-simulation-of-a-safety-relief-valve-for-improvement-of-a-one-dimensional-valve-model-in-relap5.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Thorén, Louise. “CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5.” 2012. Web. 21 Mar 2019.

Vancouver:

Thorén L. CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5. [Internet] [Thesis]. Chalmers University of Technology; 2012. [cited 2019 Mar 21]. Available from: http://studentarbeten.chalmers.se/publication/159588-cfd-simulation-of-a-safety-relief-valve-for-improvement-of-a-one-dimensional-valve-model-in-relap5.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Thorén L. CFD simulation of a safety relief valve for improvement of a one-dimensional valve model in RELAP5. [Thesis]. Chalmers University of Technology; 2012. Available from: http://studentarbeten.chalmers.se/publication/159588-cfd-simulation-of-a-safety-relief-valve-for-improvement-of-a-one-dimensional-valve-model-in-relap5

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

20. Ferrouk, Mohamed. Contribution à l'étude de la crise d'ébullition à faible titre calefaction.

Degree: 2009, Université M'Hamed Bougara Boumerdès

139 p. : ill. ; 30 cm

Les systèmes faisant intervenir le phénomène d’ébullition en fonctionnement normal dissipent et permettent d’extraire de grande quantité de… (more)

Subjects/Keywords: Fux thermique critique; Flux de chaleur non uniforme; Code RELAP5; Conditions locales

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Ferrouk, M. (2009). Contribution à l'étude de la crise d'ébullition à faible titre calefaction. (Thesis). Université M'Hamed Bougara Boumerdès. Retrieved from http://dlibrary.univ-boumerdes.dz:8080123456789/1832

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Ferrouk, Mohamed. “Contribution à l'étude de la crise d'ébullition à faible titre calefaction.” 2009. Thesis, Université M'Hamed Bougara Boumerdès. Accessed March 21, 2019. http://dlibrary.univ-boumerdes.dz:8080123456789/1832.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Ferrouk, Mohamed. “Contribution à l'étude de la crise d'ébullition à faible titre calefaction.” 2009. Web. 21 Mar 2019.

Vancouver:

Ferrouk M. Contribution à l'étude de la crise d'ébullition à faible titre calefaction. [Internet] [Thesis]. Université M'Hamed Bougara Boumerdès; 2009. [cited 2019 Mar 21]. Available from: http://dlibrary.univ-boumerdes.dz:8080123456789/1832.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Ferrouk M. Contribution à l'étude de la crise d'ébullition à faible titre calefaction. [Thesis]. Université M'Hamed Bougara Boumerdès; 2009. Available from: http://dlibrary.univ-boumerdes.dz:8080123456789/1832

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

21. Ferrouk, Mohamed. Contribution à l'étude de la crise d'ébullition à faible titre calefaction.

Degree: 2009, Université M'Hamed Bougara Boumerdès

139 p. ; ill. ; 30 cm

Les systèmes faisant intervenir le phénomène d’ébullition en fonctionnement normal dissipent et permettent d’extraire de grande quantité de… (more)

Subjects/Keywords: Fux thermique critique; Flux de chaleur non uniforme; Code RELAP5; Conditions locales

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Ferrouk, M. (2009). Contribution à l'étude de la crise d'ébullition à faible titre calefaction. (Thesis). Université M'Hamed Bougara Boumerdès. Retrieved from http://dlibrary.univ-boumerdes.dz:8080/jspui/handle/123456789/774

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Ferrouk, Mohamed. “Contribution à l'étude de la crise d'ébullition à faible titre calefaction.” 2009. Thesis, Université M'Hamed Bougara Boumerdès. Accessed March 21, 2019. http://dlibrary.univ-boumerdes.dz:8080/jspui/handle/123456789/774.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Ferrouk, Mohamed. “Contribution à l'étude de la crise d'ébullition à faible titre calefaction.” 2009. Web. 21 Mar 2019.

Vancouver:

Ferrouk M. Contribution à l'étude de la crise d'ébullition à faible titre calefaction. [Internet] [Thesis]. Université M'Hamed Bougara Boumerdès; 2009. [cited 2019 Mar 21]. Available from: http://dlibrary.univ-boumerdes.dz:8080/jspui/handle/123456789/774.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Ferrouk M. Contribution à l'étude de la crise d'ébullition à faible titre calefaction. [Thesis]. Université M'Hamed Bougara Boumerdès; 2009. Available from: http://dlibrary.univ-boumerdes.dz:8080/jspui/handle/123456789/774

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


The Ohio State University

22. Shay, Nikolas W. Electrochemical Sensor Development for Fluoride Molten Salt Redox Control.

Degree: MS, Mechanical Engineering, 2017, The Ohio State University

 Investment in nuclear technology is experiencing a revitalization as nuclear power becomes uniquely poised to take the burden left by phasing out fossil fuels to… (more)

Subjects/Keywords: Mechanical Engineering; Nuclear Engineering; molten salt; FHR; redox control; electrochemical sensor; fluoride molten salt; flinak

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APA (6th Edition):

Shay, N. W. (2017). Electrochemical Sensor Development for Fluoride Molten Salt Redox Control. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu149265579014054

Chicago Manual of Style (16th Edition):

Shay, Nikolas W. “Electrochemical Sensor Development for Fluoride Molten Salt Redox Control.” 2017. Masters Thesis, The Ohio State University. Accessed March 21, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu149265579014054.

MLA Handbook (7th Edition):

Shay, Nikolas W. “Electrochemical Sensor Development for Fluoride Molten Salt Redox Control.” 2017. Web. 21 Mar 2019.

Vancouver:

Shay NW. Electrochemical Sensor Development for Fluoride Molten Salt Redox Control. [Internet] [Masters thesis]. The Ohio State University; 2017. [cited 2019 Mar 21]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu149265579014054.

Council of Science Editors:

Shay NW. Electrochemical Sensor Development for Fluoride Molten Salt Redox Control. [Masters Thesis]. The Ohio State University; 2017. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu149265579014054


University of California – Berkeley

23. Cisneros, Anselmo Tomas. Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR).

Degree: Nuclear Engineering, 2013, University of California – Berkeley

 The Fluoride salt cooled High temperature Reactor (FHR) is a class of advanced nuclear reactors that combine the robust coated particle fuel form from high… (more)

Subjects/Keywords: Nuclear engineering; Advanced Reactor Design; Equilibrium Depletion; FHR; Liquid Salt; Pebble Bed Reactor

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APA (6th Edition):

Cisneros, A. T. (2013). Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR). (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/55h9183p

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Cisneros, Anselmo Tomas. “Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR).” 2013. Thesis, University of California – Berkeley. Accessed March 21, 2019. http://www.escholarship.org/uc/item/55h9183p.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Cisneros, Anselmo Tomas. “Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR).” 2013. Web. 21 Mar 2019.

Vancouver:

Cisneros AT. Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR). [Internet] [Thesis]. University of California – Berkeley; 2013. [cited 2019 Mar 21]. Available from: http://www.escholarship.org/uc/item/55h9183p.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Cisneros AT. Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR). [Thesis]. University of California – Berkeley; 2013. Available from: http://www.escholarship.org/uc/item/55h9183p

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


North-West University

24. Cilliers, Charl. Thermal-fluid simulation of nuclear steam generator performance using Flownex and RELAP5/mod3.4 / Charl Cilliers.

Degree: 2012, North-West University

 The steam generator plays a primary role in the safety and performance of a pressurized water reactor nuclear power plant. The cost to utilities is… (more)

Subjects/Keywords: Nuclear engineering; pressurized water reactor; U-tube steam generator; Flownex; RELAP5; thermal-fluid simulation

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Cilliers, C. (2012). Thermal-fluid simulation of nuclear steam generator performance using Flownex and RELAP5/mod3.4 / Charl Cilliers. (Thesis). North-West University. Retrieved from http://hdl.handle.net/10394/9777

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Cilliers, Charl. “Thermal-fluid simulation of nuclear steam generator performance using Flownex and RELAP5/mod3.4 / Charl Cilliers. ” 2012. Thesis, North-West University. Accessed March 21, 2019. http://hdl.handle.net/10394/9777.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Cilliers, Charl. “Thermal-fluid simulation of nuclear steam generator performance using Flownex and RELAP5/mod3.4 / Charl Cilliers. ” 2012. Web. 21 Mar 2019.

Vancouver:

Cilliers C. Thermal-fluid simulation of nuclear steam generator performance using Flownex and RELAP5/mod3.4 / Charl Cilliers. [Internet] [Thesis]. North-West University; 2012. [cited 2019 Mar 21]. Available from: http://hdl.handle.net/10394/9777.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Cilliers C. Thermal-fluid simulation of nuclear steam generator performance using Flownex and RELAP5/mod3.4 / Charl Cilliers. [Thesis]. North-West University; 2012. Available from: http://hdl.handle.net/10394/9777

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of New Mexico

25. Drumm, Amy. Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR).

Degree: Nuclear Engineering, 2015, University of New Mexico

 The purpose of this work was to develop and validate a design tool for the transients that are of interest in designing the decay heat… (more)

Subjects/Keywords: Numerical Methods; Fluoride salt-cooled High-temperature Reactor (FHR); Validation Study; Thermal Hydraulics

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Drumm, A. (2015). Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR). (Masters Thesis). University of New Mexico. Retrieved from http://hdl.handle.net/1928/25738

Chicago Manual of Style (16th Edition):

Drumm, Amy. “Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR).” 2015. Masters Thesis, University of New Mexico. Accessed March 21, 2019. http://hdl.handle.net/1928/25738.

MLA Handbook (7th Edition):

Drumm, Amy. “Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR).” 2015. Web. 21 Mar 2019.

Vancouver:

Drumm A. Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR). [Internet] [Masters thesis]. University of New Mexico; 2015. [cited 2019 Mar 21]. Available from: http://hdl.handle.net/1928/25738.

Council of Science Editors:

Drumm A. Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR). [Masters Thesis]. University of New Mexico; 2015. Available from: http://hdl.handle.net/1928/25738

26. Holmström, Joakim. Analysis of Fast Pressure Transients using RELAP5 and TRACE.

Degree: 2014, Chalmers University of Technology

 Simulations of water hammer transients are important e.g. regarding structural analysis of piping systems in a nuclear power plant. This project aims to validate TRACE… (more)

Subjects/Keywords: TRACE; RELAP5; SNAP; water hammer; vapourous cavitation; condensation; steam collapse; system codes; validation; modelling; interfacial heat transfer; inertial swing check valve.

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Holmström, J. (2014). Analysis of Fast Pressure Transients using RELAP5 and TRACE. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/209407-analysis-of-fast-pressure-transients-using-relap5-and-trace

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Holmström, Joakim. “Analysis of Fast Pressure Transients using RELAP5 and TRACE.” 2014. Thesis, Chalmers University of Technology. Accessed March 21, 2019. http://studentarbeten.chalmers.se/publication/209407-analysis-of-fast-pressure-transients-using-relap5-and-trace.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Holmström, Joakim. “Analysis of Fast Pressure Transients using RELAP5 and TRACE.” 2014. Web. 21 Mar 2019.

Vancouver:

Holmström J. Analysis of Fast Pressure Transients using RELAP5 and TRACE. [Internet] [Thesis]. Chalmers University of Technology; 2014. [cited 2019 Mar 21]. Available from: http://studentarbeten.chalmers.se/publication/209407-analysis-of-fast-pressure-transients-using-relap5-and-trace.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Holmström J. Analysis of Fast Pressure Transients using RELAP5 and TRACE. [Thesis]. Chalmers University of Technology; 2014. Available from: http://studentarbeten.chalmers.se/publication/209407-analysis-of-fast-pressure-transients-using-relap5-and-trace

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

27. Cook, William McKinley. Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D.

Degree: 2014, Texas A&M University

 This thesis work involves the use of the RELAP5-3D thermal hydraulic code to model flow for a typical pressurized water reactor (PWR). A model using… (more)

Subjects/Keywords: RELAP; RELAP5-3D; PWR; GSI-191; Three-Dimensional Nodalization; LOCA; Thermal Hydraulics; Nuclear Reactor; Safety Analysis

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Cook, W. M. (2014). Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/158626

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Cook, William McKinley. “Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D.” 2014. Thesis, Texas A&M University. Accessed March 21, 2019. http://hdl.handle.net/1969.1/158626.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Cook, William McKinley. “Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D.” 2014. Web. 21 Mar 2019.

Vancouver:

Cook WM. Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D. [Internet] [Thesis]. Texas A&M University; 2014. [cited 2019 Mar 21]. Available from: http://hdl.handle.net/1969.1/158626.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Cook WM. Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D. [Thesis]. Texas A&M University; 2014. Available from: http://hdl.handle.net/1969.1/158626

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

28. Ghrist, Melissa Renee. Zero gravity two-phase flow regime transition modeling compared with data and relap5-3d predictions.

Degree: 2009, Texas A&M University

 This thesis compares air/water two-phase flow regime transition models in zero gravity with data and makes recommendations for zero gravity models to incorporate into the… (more)

Subjects/Keywords: Flow regime; RELAP5-3D; Zero Gravity

…1 1.2 Introduction to RELAP5-3D… …9 II RELAP5-3D FLOW REGIME MAPPING… …46 IV RELAP5-3D MODEL AND RESULTS… …47 4.2 RELAP5-3D Flow Regime Output… …8 Figure 4: Schematic of Horizontal Flow Regime Map Used in RELAP5-3D (Ref 6)… 

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APA (6th Edition):

Ghrist, M. R. (2009). Zero gravity two-phase flow regime transition modeling compared with data and relap5-3d predictions. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2353

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Ghrist, Melissa Renee. “Zero gravity two-phase flow regime transition modeling compared with data and relap5-3d predictions.” 2009. Thesis, Texas A&M University. Accessed March 21, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2353.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Ghrist, Melissa Renee. “Zero gravity two-phase flow regime transition modeling compared with data and relap5-3d predictions.” 2009. Web. 21 Mar 2019.

Vancouver:

Ghrist MR. Zero gravity two-phase flow regime transition modeling compared with data and relap5-3d predictions. [Internet] [Thesis]. Texas A&M University; 2009. [cited 2019 Mar 21]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2353.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Ghrist MR. Zero gravity two-phase flow regime transition modeling compared with data and relap5-3d predictions. [Thesis]. Texas A&M University; 2009. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2353

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of Illinois – Chicago

29. Bersano, Andrea. Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors.

Degree: 2017, University of Illinois – Chicago

 With reference to innovative heat exchangers to be used in passive safety system of Gen- eration IV nuclear reactors and Small Modular Reactors it is… (more)

Subjects/Keywords: Generation IV nuclear reactors; passive systems; RELAP5; heat transfer in nuclear plants; Decay Heat Removal system; bayonet heat exchanger

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Bersano, A. (2017). Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors. (Thesis). University of Illinois – Chicago. Retrieved from http://hdl.handle.net/10027/21981

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Bersano, Andrea. “Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors.” 2017. Thesis, University of Illinois – Chicago. Accessed March 21, 2019. http://hdl.handle.net/10027/21981.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Bersano, Andrea. “Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors.” 2017. Web. 21 Mar 2019.

Vancouver:

Bersano A. Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors. [Internet] [Thesis]. University of Illinois – Chicago; 2017. [cited 2019 Mar 21]. Available from: http://hdl.handle.net/10027/21981.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Bersano A. Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors. [Thesis]. University of Illinois – Chicago; 2017. Available from: http://hdl.handle.net/10027/21981

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


RMIT University

30. Dilla, E. Numerical and experimental study of sub cooled boiling flows at low pressures.

Degree: 2007, RMIT University

 The present work builds on current numerical practices and techniques to simulate low pressure subcooled boiling flows. It attempts to improve on previous models for… (more)

Subjects/Keywords: Fields of Research; Subcooled boiling; low pressures; modelling; RELAP5

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Dilla, E. (2007). Numerical and experimental study of sub cooled boiling flows at low pressures. (Thesis). RMIT University. Retrieved from http://researchbank.rmit.edu.au/view/rmit:161687

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Dilla, E. “Numerical and experimental study of sub cooled boiling flows at low pressures.” 2007. Thesis, RMIT University. Accessed March 21, 2019. http://researchbank.rmit.edu.au/view/rmit:161687.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Dilla, E. “Numerical and experimental study of sub cooled boiling flows at low pressures.” 2007. Web. 21 Mar 2019.

Vancouver:

Dilla E. Numerical and experimental study of sub cooled boiling flows at low pressures. [Internet] [Thesis]. RMIT University; 2007. [cited 2019 Mar 21]. Available from: http://researchbank.rmit.edu.au/view/rmit:161687.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Dilla E. Numerical and experimental study of sub cooled boiling flows at low pressures. [Thesis]. RMIT University; 2007. Available from: http://researchbank.rmit.edu.au/view/rmit:161687

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

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