IRPhE Handbook 2019 Edition - Contents
A sodium-cooled fast reactor (SFR) is a fast neutron reactor that uses molten sodium metal as a coolant. Sodium-cooled Fast Reactors (SFRs) are the most promising type of reactors to achieve Generati...
The expert group critically reviewed integral experiments for validating minor actinide (MA) nuclear data, recommended additional integral experiments needed for validating MA nuclear data and invest...
Fluoride salt-cooled high-temperature reactors (FHRs), cooled with liquid (molten) salt, fueled with TRISO-based fuel are a potential molten salt reactor (MSR) design.
Neutron noise analysis can be defined as the direct measurement of the kinetics of a nuclear core. This page describes some of the NEA's previous activities on neutron noise analysis in nuclear power...
For nuclear utility companies that opt to reprocess spent fuel, recycle it or do both, one of the main pertinent issues is plutonium recycling.
Helium-cooled very high-temperature gas reactors are highlighted as a key technology with the potential to improve the competitiveness of nuclear energy within the Generation IV International Forum (...
The expert group provided advice to the Working Party on Scientific Issues of Reactor Systems (WPRS) on the scientific development needs (data and methods, validation experiments, scenario studies) o...
The 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) is tentatively planned to be held in East Lansing, Michigan, USA, on 20-23 September 2022. The SATI...
The Expert Group on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF) dealt with the various aspects of the modelling and design of accelerator shield systems and radiatio...
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) workshops, 7-15 December 2020.
Under the guidance of the Nuclear Science Committee (NSC) , the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, ...
The IRPhEP Database and Analysis Tool (IDAT) was first released in 2013 and is included on the IRPhE Handbook DVD. This database and corresponding user interface allows easy access to handbook inform...
The aim of the benchmark is to improve understanding and modelling of pellet-cladding mechanical interaction (PCMI) amongst NEA member organisations. This is achieved by comparing PCMI predictions of...
Collected sources of primary documentation for reactor physics benchmarks.
High-temperature gas-cooled reactors (HTGRs), also known as very-high-temperature reactors (VHTR) are Generation IV reactors that can operate at very high temperatures and use a graphite-moderated ga...
The annual Benchmark Workshop of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems was hosted by CEA Cadarache in Aix-en-Provence. During the week of 30 May to 3 June...
The Boiling Water Reactor Turbine Trip (BWRTT) Benchmark was established to challenge the coupled system thermal-hydraulic/neutron kinetics codes against a Peach-Bottom-2 (a GE-designed BWR/4) turbin...
This benchmark was a continuation of the V1000CT activities and defined a coupled code problem for further validation of thermal-hydraulics system codes for application with Russian-designed VVER-100...
To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neu...