Author: Pham Ngoc Son
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 12
Book Description
An Application Program for Fission Product Decay Heat Calculations
Author: Pham Ngoc Son
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 12
Book Description
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 12
Book Description
An Application Program for Fission Product Decay Heat Calculation
Author: Jun-ichi Katakura
Publisher:
ISBN:
Category :
Languages : en
Pages : 12
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 12
Book Description
Fission Product Inventory and Decay Heat Associated with FTR Fuel
Author: W. L. Bunch
Publisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 90
Book Description
The fission product inventory and the decay heat associated with driver fuel irradiated to goal exposure (45,000 MWd per metric ton) in the Fast Test Reactor is presented, based on calculations using the computer code RIBD with a nuclear data library prepared for the FTR environment. Curie inventories as a function of decay time are given for each of about 350 isotopes or isomeric states generated by the fast-neutron induced fission of either 239Pu or 238U, by down-chain decay, or by subsequent neutron capture. Beta, gamma, and total decay power are given in percent of operating power for decay times from 1 sec to about 10 years. Uncertainty in the decay heat calculations, based on propagation of the uncertainties associated with input nuclear data, is estimated. The uncertainty is calculated to be less than +̲ 10% for the first 10 days, and less than +̲ 20% over a 10-yr decay period.
Publisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 90
Book Description
The fission product inventory and the decay heat associated with driver fuel irradiated to goal exposure (45,000 MWd per metric ton) in the Fast Test Reactor is presented, based on calculations using the computer code RIBD with a nuclear data library prepared for the FTR environment. Curie inventories as a function of decay time are given for each of about 350 isotopes or isomeric states generated by the fast-neutron induced fission of either 239Pu or 238U, by down-chain decay, or by subsequent neutron capture. Beta, gamma, and total decay power are given in percent of operating power for decay times from 1 sec to about 10 years. Uncertainty in the decay heat calculations, based on propagation of the uncertainties associated with input nuclear data, is estimated. The uncertainty is calculated to be less than +̲ 10% for the first 10 days, and less than +̲ 20% over a 10-yr decay period.
Assessment of Fission Product Decay Data for Decay Heat Calculations
Author:
Publisher:
ISBN: 9789264990340
Category : Heat
Languages : en
Pages : 57
Book Description
Publisher:
ISBN: 9789264990340
Category : Heat
Languages : en
Pages : 57
Book Description
Decay Heat Calculations
Author: M. Gupta
Publisher:
ISBN:
Category : Beta decay
Languages : en
Pages : 27
Book Description
Publisher:
ISBN:
Category : Beta decay
Languages : en
Pages : 27
Book Description
Fission Product Decay Heat for Thermal Reactors
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
In the past five years there have been new experimental programs to measure decay heat (i.e., time dependent beta- plus gamma-ray energy release rates from the decay of fission products) following thermal-neutron fission of 235U, 239Pu, and 241Pu for times after fission between 1 and approx. 105 sec. Experimental results from the ORNL program stress the very short times following fission, particularly in the first few hundred sec. Complementing the experimental effort, computer codes have been developed for the computation of decay heat by summation of calculated individual energies released by each one of the fission products. By suitably combining the results of the summation calculations with the recent experimental results, a new Decay Heat Standard has been developed for application to safety analysis of operations of light water reactors. The new standard indicates somewhat smaller energy release rates than those being used at present, and the overall uncertainties assigned to the new standard are much smaller than those being used at present.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
In the past five years there have been new experimental programs to measure decay heat (i.e., time dependent beta- plus gamma-ray energy release rates from the decay of fission products) following thermal-neutron fission of 235U, 239Pu, and 241Pu for times after fission between 1 and approx. 105 sec. Experimental results from the ORNL program stress the very short times following fission, particularly in the first few hundred sec. Complementing the experimental effort, computer codes have been developed for the computation of decay heat by summation of calculated individual energies released by each one of the fission products. By suitably combining the results of the summation calculations with the recent experimental results, a new Decay Heat Standard has been developed for application to safety analysis of operations of light water reactors. The new standard indicates somewhat smaller energy release rates than those being used at present, and the overall uncertainties assigned to the new standard are much smaller than those being used at present.
Calculations of Decay Heat from Basic Nuclear Data
Author: Werner Stein
Publisher:
ISBN:
Category :
Languages : en
Pages : 138
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 138
Book Description
Risø-M.
Author:
Publisher:
ISBN: 9788755005099
Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN: 9788755005099
Category :
Languages : en
Pages :
Book Description
Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations
Author: Kern, Kilian
Publisher: KIT Scientific Publishing
ISBN: 3731508435
Category : Delayed neutrons
Languages : en
Pages : 254
Book Description
Publisher: KIT Scientific Publishing
ISBN: 3731508435
Category : Delayed neutrons
Languages : en
Pages : 254
Book Description
LEAF
Author: Clarence E. Lee
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 0
Book Description
The report describes an analytic containment building model that is used for calculating the leakage into the environment of each isotope of an arbitrary radioactive decay chain. The model accounts for the source, the buildup, the decay, the cleanup, and the leakage of isotopes that are gas-borne inside the containment building.
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 0
Book Description
The report describes an analytic containment building model that is used for calculating the leakage into the environment of each isotope of an arbitrary radioactive decay chain. The model accounts for the source, the buildup, the decay, the cleanup, and the leakage of isotopes that are gas-borne inside the containment building.