Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A statistical analysis of thermal limits has been carried out for the research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The objective of this analysis was to update the uncertainties of the hot channel factors with respect to previous analysis for both high-enriched uranium (HEU) and low-enriched uranium (LEU) fuels. Although uncertainties in key parameters which enter into the analysis are not yet known for the LEU core, the current analysis uses reasonable approximations instead of conservative estimates based on HEU values. Cumulative distribution functions (CDFs) were obtained for critical heat flux ratio (CHFR), and onset of flow instability ratio (OFIR). As was done previously, the Sudo-Kaminaga correlation was used for CHF and the Saha-Zuber correlation was used for OFI. Results were obtained for probability levels of 90%, 95%, and 99.9%. As an example of the analysis, the results for both the existing reactor with HEU fuel and the LEU core show that CHFR would have to be above 1.39 to assure with 95% probability that there is no CHF. For the OFIR, the results show that the ratio should be above 1.40 to assure with a 95% probability that OFI is not reached.
Statistical Hot Channel Analysis for the NBSR.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A statistical analysis of thermal limits has been carried out for the research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The objective of this analysis was to update the uncertainties of the hot channel factors with respect to previous analysis for both high-enriched uranium (HEU) and low-enriched uranium (LEU) fuels. Although uncertainties in key parameters which enter into the analysis are not yet known for the LEU core, the current analysis uses reasonable approximations instead of conservative estimates based on HEU values. Cumulative distribution functions (CDFs) were obtained for critical heat flux ratio (CHFR), and onset of flow instability ratio (OFIR). As was done previously, the Sudo-Kaminaga correlation was used for CHF and the Saha-Zuber correlation was used for OFI. Results were obtained for probability levels of 90%, 95%, and 99.9%. As an example of the analysis, the results for both the existing reactor with HEU fuel and the LEU core show that CHFR would have to be above 1.39 to assure with 95% probability that there is no CHF. For the OFIR, the results show that the ratio should be above 1.40 to assure with a 95% probability that OFI is not reached.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A statistical analysis of thermal limits has been carried out for the research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The objective of this analysis was to update the uncertainties of the hot channel factors with respect to previous analysis for both high-enriched uranium (HEU) and low-enriched uranium (LEU) fuels. Although uncertainties in key parameters which enter into the analysis are not yet known for the LEU core, the current analysis uses reasonable approximations instead of conservative estimates based on HEU values. Cumulative distribution functions (CDFs) were obtained for critical heat flux ratio (CHFR), and onset of flow instability ratio (OFIR). As was done previously, the Sudo-Kaminaga correlation was used for CHF and the Saha-Zuber correlation was used for OFI. Results were obtained for probability levels of 90%, 95%, and 99.9%. As an example of the analysis, the results for both the existing reactor with HEU fuel and the LEU core show that CHFR would have to be above 1.39 to assure with 95% probability that there is no CHF. For the OFIR, the results show that the ratio should be above 1.40 to assure with a 95% probability that OFI is not reached.
Statistical Hot Channel Analysis
Author: Donald A. Spong
Publisher:
ISBN:
Category : Water cooled reactors
Languages : en
Pages : 82
Book Description
Publisher:
ISBN:
Category : Water cooled reactors
Languages : en
Pages : 82
Book Description
Statistical Treatment of Hot Channel Factors for Compact Reactors
Author: P. D. Cohn
Publisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 46
Book Description
Publisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 46
Book Description
A New Approach on Engineering Hot Channel and Hot Spot Statistical Analysis
Author: U. L. Businaro
Publisher:
ISBN:
Category :
Languages : en
Pages : 49
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 49
Book Description
Measurement and Detection of Radiation
Author: Nicholas Tsoulfanidis
Publisher: Chem/Mats-Sci/E
ISBN: 9780891165231
Category : Nuclear counters
Languages : en
Pages : 534
Book Description
The fundamentals of nuclear radiation counting for undergraduate and graduate students in nuclear science, engineering, nuclear medicine, and health physics, and for laboratory engineers, scientists, and technicians. Covers statistical errors, different types of radiation detectors, relative and absolute measurements, spectroscopy, analyzing experimental data, activation analysis, and health physics. Annotation copyright by Book News, Inc., Portland, OR
Publisher: Chem/Mats-Sci/E
ISBN: 9780891165231
Category : Nuclear counters
Languages : en
Pages : 534
Book Description
The fundamentals of nuclear radiation counting for undergraduate and graduate students in nuclear science, engineering, nuclear medicine, and health physics, and for laboratory engineers, scientists, and technicians. Covers statistical errors, different types of radiation detectors, relative and absolute measurements, spectroscopy, analyzing experimental data, activation analysis, and health physics. Annotation copyright by Book News, Inc., Portland, OR
Fast Breeder Reactors
Author: Alan Edward Waltar
Publisher: Alan E. Waltar
ISBN: 0080259839
Category : Breeder, reactors
Languages : en
Pages : 877
Book Description
Publisher: Alan E. Waltar
ISBN: 0080259839
Category : Breeder, reactors
Languages : en
Pages : 877
Book Description
Technical Translations
Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 940
Book Description
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 940
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 640
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 640
Book Description
Scientific and Technical Aerospace Reports
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1572
Book Description
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1572
Book Description
Nuclear Systems Volume II
Author: Neil E. Todreas
Publisher: CRC Press
ISBN: 1482239590
Category : Science
Languages : en
Pages : 659
Book Description
Discusses fundamental ideas for various modeling approaches for the macro- and micro-scale flow conditions in the reactor. Covers specific design considerations, such as natural convection and core reliability. Enables the reader to better understand the importance of safety considerations in thermal engineering and analysis of a modern nuclear plant. Features end-of-chapter problems. Includes a Solutions Manual for adopting instructors.
Publisher: CRC Press
ISBN: 1482239590
Category : Science
Languages : en
Pages : 659
Book Description
Discusses fundamental ideas for various modeling approaches for the macro- and micro-scale flow conditions in the reactor. Covers specific design considerations, such as natural convection and core reliability. Enables the reader to better understand the importance of safety considerations in thermal engineering and analysis of a modern nuclear plant. Features end-of-chapter problems. Includes a Solutions Manual for adopting instructors.