This ebook is the first authorized digital version of Kernighan and Ritchie's 1988 classic, The C Programming Language (2nd Ed.). One of the best-selling programming books published in the last fifty years, "K&R" has been called everything from the "bible" to "a landmark in computer science" and it has influenced generations of programmers. Available now for all leading ebook platforms, this concise and beautifully written text is a "must-have" reference for every serious programmers digital library.

As modestly described by the authors in the Preface to the First Edition, this "is not an introductory programming manual; it assumes some familiarity with basic programming concepts like variables, assignment statements, loops, and functions. Nonetheless, a novice programmer should be able to read along and pick up the language, although access to a more knowledgeable colleague will help."

The C programming language

The molten salt reactor (MSR) in generation IV: Overview and perspectives

The Molten Salt Reactor in Generation IV: Overview and Perspectives

Molten salt reactors: A new beginning for an old idea

This paper presented a review on the past, present and the future of thorium fuel cycle The aim of this study is to evaluate the developments in thorium fuel cycle, looking at the prospects and drawbacks on the possibility of thorium-based nuclear fuel for commercial reactors realising the increasing challenges of uranium-based nuclear fuel The initial interest on thorium-based nuclear fuel and why it was abandoned at the early stage of nuclear technology were considered Also, the reasons behind the present renewed interest on the viability of thorium fuel cycle as a valuable alternative to the conventional uranium-based fuel were studied Thorium abundance, its physical, chemical and neutronic properties were evaluated in comparison to the uranium fuel cycle to determine thorium fuel sustainability for next generation nuclear industry In this study, it was found that thorium fuel is three to four times more abundant, has higher conductivity, high melting temperature, low expansivity and more proliferation resistant compared to uranium fuel The possible application and related challenges of thorium fuels in different reactor types and designs such as light water reactors (LWRs), high temperature gas-cooled reactors (HTGRs), heavy water reactors (HWRs), molten salt reactors (MSRs) and accelerator driven system reactors (ADSRs) were reviewed The findings indicate that thorium fuel cycle can be used in the currently dominant LWRs designs in the nuclear industry with little technical modification, and also in other reactor types under investigation for future application especially molten salt breeder reactors, fast reactors and accelerator driven system reactors Finally, this review made some recommendations on the short-term and long–term applications of thorium-based nuclear fuel cycle, and the issues that must be addressed before using thorium fuel for commercial reactor operations

Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects

http://www.ralphmoir.com/media/fur_icenes_2007.pdf

A Road Map for the Realization of Global-scale Thorium Breeding Fuel Cycle by Single Molten-Fluoride Flow

One of the most reliable experimental methods for measuring the subcriticality level of a nuclear fuel assembly is the Sjostrand method applied to the reaction rate generated from a pulsed neutron source. This study developed a new analytical methodology simulating the Sjostrand method, which allows comparing the experimental and analytical reaction rates and the obtained subcriticality levels. In this methodology, the reaction rate is calculated due to a single neutron pulse using MCNP/MCNPX computer code or any other neutron transport code that explicitly simulates the delayed fission neutrons. The calculation simulates a single neutron pulse over a long time period until the delayed neutron contribution to the reaction rate is vanished. The obtained reaction rate is then superimposed to itself, with respect to the time, to simulate the repeated pulse operation until the asymptotic level of the reaction rate, set by the delayed neutrons, is achieved. The superimposition of the pulse to itself was calculated by a simple C computer program. A parallel version of the C program is used due to the large amount of data being processed, e.g. by the Message Passing Interface (MPI). The analytical results of this new calculation methodology have shown an excellent agreement with the experimental data available from the YALINA-Booster facility of Belarus. This methodology can be used to calculate Bell and Glasstone spatial correction factor.

H. Kiyavitskaya

Papers

A Road Map for the Realization of Global-scale Thorium Breeding Fuel Cycle by Single Molten-Fluoride Flow

Pulse superimposition calculational methodology for estimating the subcriticality level of nuclear fuel assemblies

Comparison of calculated and measured reaction rates obtained through foil activation in the subcritical dual spectrum facility YALINA-Booster

YALINA-Booster Subcritical Assembly Conversion

YALINA-Thermal Experiment Analysis with the Deterministic Code System ERANOS