Author: Calvin H. Hogg
Publisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 12
Book Description
Gamma Heating Measurements in the MTR
Author: Calvin H. Hogg
Publisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 12
Book Description
Publisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 12
Book Description
MTR Gamma Heat Generation Measurements
Author: L. D. Weber
Publisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 44
Book Description
Publisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 44
Book Description
The Effect of Gamma Heating on the APPR-1 Pressure Shell
Author: H. R. Kroeger
Publisher:
ISBN:
Category : Army package power reactors
Languages : en
Pages : 222
Book Description
Publisher:
ISBN:
Category : Army package power reactors
Languages : en
Pages : 222
Book Description
Brookhaven Reactor Gamma Flux by Calorimetry
Author: J. G. Carroll
Publisher:
ISBN:
Category : Calorimetry
Languages : en
Pages : 44
Book Description
Publisher:
ISBN:
Category : Calorimetry
Languages : en
Pages : 44
Book Description
Materials in Nuclear Applications
TID.
Nuclear Heating Measurements in the Maria Reactor and Implementation of Neutron and Photon Calculation Scheme
Author: Mikolaj Tarchalski
Publisher:
ISBN:
Category :
Languages : en
Pages : 175
Book Description
This thesis work presents a calculation scheme which enables evaluation of heat generation from nuclear reactions in the MARIA nuclear reactor by use French computational codes TRIPOLI-4 © (TRIPOLI-4 is a registered trademark of CEA) and Apollo-2. Particular attention was devoted to the heat induced by gamma radiation. The thesis also presents measurements of nuclear heating in selected locations inside MARIA MTR reactor. This allows reaching first steps of validation and qualification of computer calculations. Research and analysis presented in the thesis allow one to compare the results obtained by using proposed calculation scheme with the experimental measurement methods. Finally, further works and perspectives were proposed on the development of the calculations and experimental measurements of nuclear heating in nuclear reactors.Qualifying the calculations was possible by performing especially dedicated 7-day core measurement campaigns. Nuclear heating measurements were performed with gamma thermometers and specially designed KAROLINA calorimeter. All measurement devices used were mounted in a dedicated probe, designed and built for this purpose, which allowed for the adjustment of instruments position inside the MARIA core. The main scientific hypothesis of this work is that currently available Monte Carlo simulations of neutron and gamma transport can be used to correct and accurate calculations of prompt nuclear heating in nuclear reactor, whereas delayed component of nuclear heating can be determined experimentally. For this purpose new calculation scheme and improvements in nuclear heating measurements were implemented.
Publisher:
ISBN:
Category :
Languages : en
Pages : 175
Book Description
This thesis work presents a calculation scheme which enables evaluation of heat generation from nuclear reactions in the MARIA nuclear reactor by use French computational codes TRIPOLI-4 © (TRIPOLI-4 is a registered trademark of CEA) and Apollo-2. Particular attention was devoted to the heat induced by gamma radiation. The thesis also presents measurements of nuclear heating in selected locations inside MARIA MTR reactor. This allows reaching first steps of validation and qualification of computer calculations. Research and analysis presented in the thesis allow one to compare the results obtained by using proposed calculation scheme with the experimental measurement methods. Finally, further works and perspectives were proposed on the development of the calculations and experimental measurements of nuclear heating in nuclear reactors.Qualifying the calculations was possible by performing especially dedicated 7-day core measurement campaigns. Nuclear heating measurements were performed with gamma thermometers and specially designed KAROLINA calorimeter. All measurement devices used were mounted in a dedicated probe, designed and built for this purpose, which allowed for the adjustment of instruments position inside the MARIA core. The main scientific hypothesis of this work is that currently available Monte Carlo simulations of neutron and gamma transport can be used to correct and accurate calculations of prompt nuclear heating in nuclear reactor, whereas delayed component of nuclear heating can be determined experimentally. For this purpose new calculation scheme and improvements in nuclear heating measurements were implemented.
MTR Thermal Neutron Flux Measurements for Cycle 146
Author: L. D. Weber
Publisher:
ISBN:
Category : Materials testing reactors
Languages : en
Pages : 108
Book Description
Publisher:
ISBN:
Category : Materials testing reactors
Languages : en
Pages : 108
Book Description
Experimental and Theoretical Values of the Gamma Decay Dose Rate and Heating from Spent MTR Fuel Elements
Author: W. C. Francis
Publisher:
ISBN:
Category : Gamma decay
Languages : en
Pages : 84
Book Description
Publisher:
ISBN:
Category : Gamma decay
Languages : en
Pages : 84
Book Description
Radiation Shields and Shielding
Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Shielding (Radiation)
Languages : en
Pages : 112
Book Description
Included are 687 selected references to unclassified reports and scientific journal literature on radiation shields and shielding. Author, report number, and subject indexes are also included.
Publisher:
ISBN:
Category : Shielding (Radiation)
Languages : en
Pages : 112
Book Description
Included are 687 selected references to unclassified reports and scientific journal literature on radiation shields and shielding. Author, report number, and subject indexes are also included.