Ya. I. Shtrombakh

Bio: Ya. I. Shtrombakh is an academic researcher from Kurchatov Institute. The author has contributed to research in topics: Embrittlement & Reactor pressure vessel. The author has an hindex of 13, co-authored 33 publications receiving 478 citations.

The International Atomic Energy Agency

Abstract: Plant roots perform a myriad of functions right from the anchorage of plants to storage of reserve food material for the adverse weather. Roots forage around the soil for acquisition of ions and water and continually develop new branches. However, very little is known about the molecular mechanisms regulating root development and differentiation. We have endeavoured to decipher the genetic regulation of root formation in tomato by screening mutants defective in root development. We have isolated several mutants with altered morphology of roots. These mutants have been characterized for their phenotypes throughout the life cycle. In this report we show that for few of the mutants the vigour of plant is directly related to modification in the root structure. The potential utility of these mutants in understanding root development and also improving yield of tomato is discussed.

Blue Ribbon Commission on America’s Nuclear Future

Abstract: Memorandum for the Secretary of Energy Expanding our Nation’s capacity to generate clean nuclear energy is crucial to our ability to combat climate change, enhance energy security, and increase economic prosperity. My Administration is undertaking substantial steps to expand the safe, secure, and responsible use of nuclear energy. These efforts are critical to accomplishing many of my Administration’s most significant goals.

Radiation defects in graphite

Abstract: This article discusses the nature of radiation defects in graphite, reviewing past and recent developments in understanding their structure, interactions and effect on physical properties. The principal focus is on behaviour at the atomic and microstructural level, with an interest both in understanding graphite moderator damage in nuclear reactors and building a foundation for the range of emerging technological applications of defect-engineered graphitic materials. It is hoped that this article will both clarify the picture that has emerged over the last 50 years and provide a useful background to ongoing efforts.

Current understanding of radiation-induced degradation in light water reactor structural materials

Abstract: Current phenomenological knowledge and understanding of mechanisms are reviewed for radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted stress corrosion cracking of core internals of stainless steels. Accumulated test data of irradiated materials in light water reactors and microscopic analyses by using state-of-the-art techniques such as a three-dimensional atom probe and electron backscatter diffraction have significantly increased knowledge about microstructural features. Characteristics of solute clusters and deformation microstructures and their contributions to macroscopic material property changes have been clarified to a large extent, which provide keys to understand in the degradation mechanisms. However, there are still fundamental research issues that merit study for long-term operation of reactors that requires reliable quantitative prediction of radiation-induced degradation of component materials in low-dose rate high-dose conditions.