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Performance and Fuel-cycle Cost Analysis of One JANUS 30 Conceptual Design for Several Fuel-element-design Options

Performance and Fuel-cycle Cost Analysis of One JANUS 30 Conceptual Design for Several Fuel-element-design Options PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
The performance and fuel cycle costs for a 25 MW, JANUS 30 reactor conceptual design by INTERATOM, Federal Republic of Germany, for BATAN, Republic of Indonesia have been studied using 19.75% enriched uranium in four fuel element design options. All of these fuel element designs have either been proposed by INTERATOM for various reactors or are currently in use with 93% enriched uranium in reactors in the Federal Republic of Germany. Aluminide, oxide, and silicide fuels were studied for selected designs using the range of uranium densities that are either currently qualified or are being developed and demonstrated internationally. To assess the long-term fuel adaptation strategy as well as the present fuel acceptance, reactor performance and annual fuel cycle costs were computed for seventeen cases based on a representative end-of-cycle excess reactivity and duty factor. In addition, a study was made to provide data for evaluating the trade-off between the increased safety associated with thicker cladding and the economic penalty due to increased fuel consumption.

Performance and Fuel-cycle Cost Analysis of One JANUS 30 Conceptual Design for Several Fuel-element-design Options

Performance and Fuel-cycle Cost Analysis of One JANUS 30 Conceptual Design for Several Fuel-element-design Options PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
The performance and fuel cycle costs for a 25 MW, JANUS 30 reactor conceptual design by INTERATOM, Federal Republic of Germany, for BATAN, Republic of Indonesia have been studied using 19.75% enriched uranium in four fuel element design options. All of these fuel element designs have either been proposed by INTERATOM for various reactors or are currently in use with 93% enriched uranium in reactors in the Federal Republic of Germany. Aluminide, oxide, and silicide fuels were studied for selected designs using the range of uranium densities that are either currently qualified or are being developed and demonstrated internationally. To assess the long-term fuel adaptation strategy as well as the present fuel acceptance, reactor performance and annual fuel cycle costs were computed for seventeen cases based on a representative end-of-cycle excess reactivity and duty factor. In addition, a study was made to provide data for evaluating the trade-off between the increased safety associated with thicker cladding and the economic penalty due to increased fuel consumption.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 536

Book Description


INIS Atomindex

INIS Atomindex PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1286

Book Description


Government Reports Annual Index

Government Reports Annual Index PDF Author:
Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 1378

Book Description


Fuel-cycle Cost Comparisons with Oxide and Silicide Fuels

Fuel-cycle Cost Comparisons with Oxide and Silicide Fuels PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
This paper addresses fuel cycle cost comparisons for a generic 10 MW reactor with HEU aluminide fuel and with LEU oxide and silicide fuels in several fuel element geometries. The intention of this study is to provide a consistent assessment of various design options from a cost point of view. Fuel cycle cost benefits could result if a number of reactors were to utilize fuel elements with the same number or different numbers of the same standard fuel plate. Data are presented to quantify these potential cost benefits. This analysis shows that there are a number of fuel element designs using LEU oxide or silicide fuels that have either the same or lower total fuel cycle costs than the HEU design. Use of these fuels with the uranium densities considered requires that they are successfully demonstrated and licensed.

Government Reports Announcements & Index

Government Reports Announcements & Index PDF Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 1434

Book Description


Transmutation Fuel Performance Code Conceptual Design

Transmutation Fuel Performance Code Conceptual Design PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
One of the objectives of the Global Nuclear Energy Partnership (GNEP) is to facilitate the licensing and operation of Advanced Recycle Reactors (ARRs) for transmutation of the transuranic elements (TRU) present in spent fuel. A fuel performance code will be an essential element in the licensing process ensuring that behavior of the transmutation fuel elements in the reactor is understood and predictable. Even more important in the near term, a fuel performance code will assist substantially in the fuels research and development, design, irradiation testing and interpretation of the post-irradiation examination results.

Simple Procedure for Determining Implications of Design Changes on Fast Reactor Fuel Cycle Cost and Breeding Performance

Simple Procedure for Determining Implications of Design Changes on Fast Reactor Fuel Cycle Cost and Breeding Performance PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Recently, analytical sensitivity methods has been applied to obtain fuel cycle cost implications of data uncertainties. To perform exposure dependent sensitivity analysis without repeating expensive spectrum calculations, simple correlations of the spectrum averaged cross sections (SAXS) were constructed. The correlation coefficients were obtained by fitting the SAXS calculated by direct methods over a wide range of LMFBR core designs. In this paper the procedure has been extended to study sensitivity of fuel cycle cost and breeding ratio to design variation. The method involves using the correlations to construct both the SAXS and the sensitivity coefficients. Composition dependent correlations have been found to be accurate for the core while both composition and position have to be included in analysing the blanket.

Digital and Social Media Marketing

Digital and Social Media Marketing PDF Author: Nripendra P. Rana
Publisher: Springer Nature
ISBN: 3030243745
Category : Business & Economics
Languages : en
Pages : 337

Book Description
This book examines issues and implications of digital and social media marketing for emerging markets. These markets necessitate substantial adaptations of developed theories and approaches employed in the Western world. The book investigates problems specific to emerging markets, while identifying new theoretical constructs and practical applications of digital marketing. It addresses topics such as electronic word of mouth (eWOM), demographic differences in digital marketing, mobile marketing, search engine advertising, among others. A radical increase in both temporal and geographical reach is empowering consumers to exert influence on brands, products, and services. Information and Communication Technologies (ICTs) and digital media are having a significant impact on the way people communicate and fulfil their socio-economic, emotional and material needs. These technologies are also being harnessed by businesses for various purposes including distribution and selling of goods, retailing of consumer services, customer relationship management, and influencing consumer behaviour by employing digital marketing practices. This book considers this, as it examines the practice and research related to digital and social media marketing.

Iter fuel cycle systems layout - conceptual design

Iter fuel cycle systems layout - conceptual design PDF Author: O. K. Kveton
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description
Zircaloy-4 fuel sheath specimens 15.2 mm diameter by 0.42 mm wall thickness with beryllium-brazed appendages have been laboratory tested at high temperature with internal gas pressurization and inert gas shielding of the outer surfaces. with sufficient hoop stress at temperatures less than 1073 k cracks, which were due to a beryllium assisted crack penetration mechanism, were found to occur at the appendages. formulae to predict the beryllium penetration and rupture have been derived by westinghouse canada ltd. based on data from direct resistance-heated specimens. the formulae are thought to be able to predict the phenomenon in fuel sheaths with changing temperature/pressure histories. a series of tests was done by canadian general electric to determine the formulae ability to predict the occurrence of beryllium assisted crack penetration in specimens heated indirectly with internal heaters. the tests showed: 1) there is an incubation period before any beryllium assisted crack penetration occurs. 2) at sheath temperatures below approximately equal to 1073 k sheath rupture by excessive mechanical strain will preclude rupture by beryllium assisted crack penetration. 3) the formulae predicted rupture times above and below the braze alloy melting temperature within the previously determined confidence limits. 4) predictions of beryllium assisted crack penetration rupture for specimens with changing temperature/pressure histories were of similar accuracy to predictions of isothermal tests. 5) specimens with an appendage plane of one bearing pad and three spacer pads behaved similarly to the specimens with four spacer pads on which the formulae were based.