Materials are evaluated for use as in-core diluents and as peripheral reflectors for Gas-Cooled Fast Reactor (GFR) service, using coupled Monte Carlo (MCNP) and isotopics (ORIGEN) codes. The principal performance indices compared were effects on beginning of irradiation multiplication factor, reactivity-lineated burnup, and coolant (here CO2) void reactivity. While low values of the macroscopic...

regime? What about the Iran-Iraq nuclear entanglement? Can both issues be dealt with under a regional arrangement? Can new global approaches be reconciled with a regional approach in the Middle East? This article attempts to identify and explore some of these issues, examining the Middle Eastern nuclear situation in light of the experience of Iraq, North Korea, South Africa, and Latin America. ...

What if nuclear aspirants get the bomb? How likely are they to use it? Which nuclear strategies might emerging nuclear powers adopt? These may seem like academic questions, but they are loaded with strategic significance. Different nuclear strategies have historically been associated with distinct types of risk. Some nuclear strategies are more likely to deter U.S. freedom of action; some more ...

Neutron coincidence counting is a technique widely used for qualitative and quantitative analysis of nuclear material. Because different isotopes possess different coincident neutron characteristics, the coincident neutron signature can be used to identify and quantify a given material. In an effort to identify unknown nuclear samples in field inspections, a new portable neutron coincidence cou...

To aid in removal of oralloy from the nuclear weapons stockpile, scientists at the Los Alamos National Laboratory Plutonium Facility are decontaminating oralloy parts by electrodissolution in neutral to alkaline electrolytes composed of sodium nitrate and sodium sulfate. To improve the process, electrodissolution experiments were performed with depleted uranium to understand the effects of vari...

Thermal-hydraulic calculations have been conducted with respect to the active part of MAK-2 loop facility VVR-ts research reactor for 99 Mo production. The computational studies were undertaken both case using a highly 235 U enriched target and low-enriched target. calculation was performed actual technical characteristics channel. power density two simulated cases obtained in course preliminar...