Author: P. J. Valliant
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Final universal cell examination of bundle te from the dp-10 experiment after power ramp irradiation tests in the u-2 loop
Final universal cells examination of eighteen dme-187 elements after the u2d-47820 power ramp irradiation
Final universal cell examination of bundle acr of the bdl-420 experiment
Final universal cell examination of bundle acl of the bdl-420 experiment
Final universal cells examination of materials test bundle acx of the cor-111 experiment
Final universal cell examination of bundle zx from the bdl-413 experiment
Final universal cell examination of damaged bundle zy from the bdl-413 experiment
Pre-power boost examination of bundles wb, ws, te and ts of the dp-10 experiment
Status of Fast Reactor Research and Technology Development
Author: International Atomic Energy Agency
Publisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0
Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
Publisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0
Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
Improvement of Computer Codes Used for Fuel Behaviour Simulation (Fumex-III)
Author: International Atomic Energy Agency
Publisher: IAEA Tecdoc
ISBN: 9789201386106
Category : Science
Languages : en
Pages : 0
Book Description
The modelling of the performance of nuclear fuel is crucial to the operation of nuclear power plants and comprises a key component of the demonstration of nuclear safety. As the demands on fuel performance increase, fuel modelling codes need to develop and cover a wider range of operational and transient conditions. This publication compares the predictions of current fuel modelling codes with data representing a wide range of fuel operational conditions. The results demonstrate both excellent performance and areas for further development of the codes to support advanced fuel operations.
Publisher: IAEA Tecdoc
ISBN: 9789201386106
Category : Science
Languages : en
Pages : 0
Book Description
The modelling of the performance of nuclear fuel is crucial to the operation of nuclear power plants and comprises a key component of the demonstration of nuclear safety. As the demands on fuel performance increase, fuel modelling codes need to develop and cover a wider range of operational and transient conditions. This publication compares the predictions of current fuel modelling codes with data representing a wide range of fuel operational conditions. The results demonstrate both excellent performance and areas for further development of the codes to support advanced fuel operations.