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After TEPCO Fukushima-Daiichi NPS accident, new fuels and materials have been developed in the OECD/NEA member countries. The objective of the development is to have new fuels with enhanced accident tolerance, especially for severe accident conditions. For the new fuel development, similar to the conventional ones, many kinds of information are necessary to maintain the safety functions of the fuel. The fuel safety should be confirmed not only for severe accidents, but also for various conditions such as normal operation, design basis accidents, transportation and so on. Preparation of experimental databases with high reliability and analytical tools are also needed to confirm the safety of the new fuels. Therefore, test reactors and hot laboratories play important roles in the acquisition of in-reactor data which are the key information as the technical basis of safety judgement. In this presentation, safety requirements under various plant conditions which are considered in the new fuel development is explained. The importance of experiments using test reactors and laboratories for new fuel development is also explained including examples of JAEA facilities.

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OECD/NEA benchmark on pellet-clad mechanical interaction modelling with fuel performance codes; Influence of pellet geometry and gap size

Report on the stay in Norway as a secondee of OECD Halden Reactor Project

Fuel irradiation research of Japan at Halden reactor; Achievement of cooperative researches between JAERI and several organizations in the period from 1997 to 1999

Fuel irradiation research of Japan at OECD Halden reactor project; Achievement of joint researches between JAERI and other organizations in the period from 1994 to 1996

Enlarged Halden programme group meeting

Gamma-ray spectra measurements for long cooled MOX spent fuels

JOINT RESEARCH ON FUEL IRRADIATION IN HALDEN BOILING WATER REACTOR

Fatigue Analysis of Zircaloy-2 Cladding Under Cyclis Stress Damage; The Result of Pcmi Study in Halden Boiling Water Reactor

Evaluation of Fuel Centerline Temperature of LWR Fuel Rods During Fast Rise to Operating Power - Results from Halden Power Ramp Test

Plans for Irradiation Experiments of IFA's 508 and 515,and Preliminary Data Report for IFA's 508

Analysis of Pellet Center Temperature Measurements for HALDEN IFT-224 Using Program FREG-3

Safety consideration for the introduction of new fuels and materials