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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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Development of supercritical pressure water cooled solid breeder blanket in JAERI

Air vent in water chamber and surface coating on liner slides concerning auxiliary cooling system for the high temperature engineering test reactor

Development of B $_{4}$ C-carbon fiber composite ceramics as plasma facing materials in nuclear fusion reactor, 3; Heat resistance evaluation by electron beam irradiation and by in situ plasma discharge in JT-60

Proceedings of the JAERI-KAERI Joint Seminar on Post Irradiation Examination; November 9-10, 1992, JAERI Oarai Japan

Estimation of hot streak in core bottom structure of high temperature gas-cooled reactor; Thermal mixing test of coolant in core bottom structure of HENDEL

Data report for ROSA-IV LSTF 10% hot leg break experiment Run SB-HL-04

Annual report on operation, utilization and technical development of research reactors and hot laboratory, from April 1,1989 to March 31,1990

Data report for ROSA-IV LSTF 10% hot leg break experiment; Run SB-HL-02

Data report for ROSA-IV/LSTF 5% hot leg break experiment Run SB-HL-01

Standard method of in-situ testing of HEPA filters in nuclear fuel facilities

Experimental Study on Characteristics of the Hydraulic Behavior in the Standard Fuel Element for the Core Thermal-Hydraulic Design of the Upgraded JRR-3

Thermal performance test of the hot gas ducts of HENDEL

Progress Report on Safety Research of High-Level Waste Management for the Perical April,1981 to May,1982

An Analysis of LOCA Experiment by RELAP-4J; An Analysis of ROSA-II Hot Leg Break Test Run419

Structure and performance of JAERI-type respiration fitting test apparatus

ROSA-II Test Data Report,9; The Largest Hot Leg Breaks(Runs 418,419,420,423)

Leakage test of worn respirators by Sodium-chloride particles

Safety consideration for the introduction of new fuels and materials