Cumulative Fast Reactor Fission Yields of 233u, 235u, 236u, 238u, 237np, 239pu, 240pu, 241pu, 242pu, 241am PDF Download
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Author: L. Koch
Publisher:
ISBN:
Category :
Languages : en
Pages : 21
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Book Description
Author: L. Koch
Publisher:
ISBN:
Category :
Languages : en
Pages : 21
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Book Description
Author: Kern, Kilian
Publisher: KIT Scientific Publishing
ISBN: 3731508435
Category : Delayed neutrons
Languages : en
Pages : 254
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Book Description
Fission product yield data play an important role in simulations of nuclear fission reactors, aimed at fuel cycle and safety analyses. The respective evaluated data libraries still have shortcomings regarding the treatment of energy dependencies and uncertainty information. This work has been aimed at the development of a fission model for future fission product yield evaluations as well as its validation on the levels of cross-sections, fission product yields and time dependent decay radiation.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 168
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 624
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear physics
Languages : en
Pages : 946
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Book Description
Author: Willem Frederik Geert van Rooijen
Publisher: IOS Press
ISBN: 9781586036966
Category : Technology & Engineering
Languages : en
Pages : 160
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Book Description
The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1692
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Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 120
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Book Description
Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.
Author: Doug Reilly
Publisher:
ISBN: 9780160327247
Category : Non-destructive testing
Languages : en
Pages : 700
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Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 188
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Book Description
Over the past decade significant progress has been achieved in the development of waste characterization and control procedures and equipment as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. -- Publisher's description.
