Publication

Integral measurements with a plutonium inert matrix fuel rod in a heterogeneous light water reactor lattice

Rakesh Chawla
2001
Journal Articles

Abstract

As part of PSI's validatory efforts for neutronics calculations pertaining to inert matrix fuel (IMF) deployment in light water reactors, first-of-their-kind integral measurements have been carried out at the PROTEUS facility employing a specially fabricated Pu-Er-Zr IMF rod in a heterogeneous (boiling water reactor) test lattice. Analogous experiments have also been conducted with MOX and 'dummy' IMF rods, providing the basis for a systematic comparison of experimental and calculational results.

Official source

https://infoscience.epfl.ch/entities/publication/7d5060d4-cde0-40b9-b44f-02e271dd5475

About this result

This page is automatically generated and may contain information that is not correct, complete, up-to-date, or relevant to your search query. The same applies to every other page on this website. Please make sure to verify the information with EPFL's official sources.

Graph Chat

Chat with Graph Search

Ask any question about EPFL courses, lectures, exercises, research, news, etc. or try the example questions below.

DISCLAIMER: The Graph Chatbot is not programmed to provide explicit or categorical answers to your questions. Rather, it transforms your questions into API requests that are distributed across the various IT services officially administered by EPFL. Its purpose is solely to collect and recommend relevant references to content that you can explore to help you answer your questions.

Rakesh Chawla
2001
Journal Articles

Abstract

Official source

https://infoscience.epfl.ch/entities/publication/7d5060d4-cde0-40b9-b44f-02e271dd5475

About this result

Related concepts (18)

Nuclear fuel

Nuclear fuel is material used in nuclear power stations to produce heat to power turbines. Heat is created when nuclear fuel undergoes nuclear fission. Most nuclear fuels contain heavy fissile actinide elements that are capable of undergoing and sustaining nuclear fission. The three most relevant fissile isotopes are uranium-233, uranium-235 and plutonium-239. When the unstable nuclei of these atoms are hit by a slow-moving neutron, they frequently split, creating two daughter nuclei and two or three more neutrons.

Advanced heavy-water reactor

The advanced heavy-water reactor (AHWR) or AHWR-300 is the latest Indian design for a next-generation nuclear reactor that burns thorium in its fuel core. It is slated to form the third stage in India's three-stage fuel-cycle plan. This phase of the fuel cycle plan was supposed to be built starting with a 300MWe prototype in 2016. KAMINI is the world's first thorium-based experimental reactor. It is cooled and moderated by light water, fueled with uranium-233 metal produced by the thorium fuel cycle harnessed by the neighbouring FBTR reactor and produces 30 KW of thermal energy at full power.

Nuclear fuel cycle

The nuclear fuel cycle, also called nuclear fuel chain, is the progression of nuclear fuel through a series of differing stages. It consists of steps in the front end, which are the preparation of the fuel, steps in the service period in which the fuel is used during reactor operation, and steps in the back end, which are necessary to safely manage, contain, and either reprocess or dispose of spent nuclear fuel.

Related publications (6)

Integral measurements with a plutonium inert matrix fuel rod in a heterogeneous light water reactor lattice

Chat with Graph Search

The 0E2 benchmarks for PWR UO2 decay heat: an analysis from the NEA WPNCS

Development of an experimental channel in CROCUS

Intensification of highly exothermic fast reaction by multi-injection microstructured reactor