Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations
- Location
-
Deutsche Nationalbibliothek Frankfurt am Main
- ISBN
-
9783731508434
- Extent
-
Online-Ressource
- Language
-
Englisch
- Notes
-
Karlsruhe, Karlsruher Institut für Technologie (KIT), Dissertation, 2018
- Keyword
-
Nuclear fission
Fuel
Delayed neutrons
Heat
Radioactive decay
- Event
-
Veröffentlichung
- (where)
-
Karlsruhe
- (who)
-
KIT Scientific Publishing
- (when)
-
2019
- Creator
- DOI
-
10.5445/KSP/1000085625
- URN
-
urn:nbn:de:0072-856251
- Rights
-
Der Zugriff auf das Objekt ist unbeschränkt möglich.
- Last update
- 14.08.2025, 10:49 AM CEST
Data provider
This object is provided by:
Deutsche Nationalbibliothek. If you have any questions about the object, please contact the data provider.
Deutsche Nationalbibliothek. If you have any questions about the object, please contact the data provider.
Associated
- Kern, Kilian
- KIT Scientific Publishing
Time of origin
- 2019
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Auxin-inducible protein depletion system in fission yeast
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Search for neutrino oscillations at a fission reactor
Simulation of thorium material properties under fission reactor conditions
TALYS calculations of prompt fission observables and independent fission product yields for the neutron-induced fission of $$^235}$$ 235 U
Fission observables from 4D Langevin calculations with macroscopic transport coefficients
High Fidelity Monte Carlo Based Reactor Physics Calculations
Theoretical calculations and CFD simulations of membrane reactor designs
Improving fission-product decay data for reactor applications: part I—decay heat
EAES-Symposium on Reactor Calculations vom 25.-27.04.1955 in Arnheim/Niederlande
Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations
Reactor with very low fission product inventory
Auxin-inducible protein depletion system in fission yeast
The Impact of Fission on R-Process Calculations
Search for neutrino oscillations at a fission reactor
Simulation of thorium material properties under fission reactor conditions
TALYS calculations of prompt fission observables and independent fission product yields for the neutron-induced fission of $$^235}$$ 235 U
Fission observables from 4D Langevin calculations with macroscopic transport coefficients
High Fidelity Monte Carlo Based Reactor Physics Calculations
Theoretical calculations and CFD simulations of membrane reactor designs
Improving fission-product decay data for reactor applications: part I—decay heat