HIGH TEMPERATURE FISSION CHAMBERS: STATE-OF-THE-ART. L. Martin J.L. Perrin M. Tixier Centrale PHENIX CNPE Creys-Malville Philips Photonics.

Similar documents
DIRECT EXPERIMENTAL TESTS AND COMPARISON BETWEEN SUB-MINIATURE FISSION CHAMBERS AND SPND FOR FIXED IN-CORE INSTRUMENTATION OF LWR

Lesson 14: Reactivity Variations and Control

Chem 481 Lecture Material 4/22/09

EXPERIENCE IN NEUTRON FLUX MEASUREMENT CHAINS VERIFICATION AT SLOVAK NPPS

Development of education and training programs using ISIS research reactor

He-3 Neutron Detectors

FUEL PERFORMANCE EVALUATION THROUGH IODINE ACTIVITY MONITORING K.ANANTHARAMAN, RAJESH CHANDRA

DETERMINATION OF THE SERVICE LIFE FOR THE EXCORE NEUTRON DETECTOR CABLES IN SEABROOK STATION

MONTE CALRLO MODELLING OF VOID COEFFICIENT OF REACTIVITY EXPERIMENT

Upgrade plans for the ATLAS Forward Calorimeter at the HL-LHC

Gas-filled Detectors

ION Pumps for UHV Systems, Synchrotrons & Particle Accelerators. Mauro Audi, Academic, Government & Research Marketing Manager

SOME ASPECTS OF COOLANT CHEMISTRY SAFETY REGULATIONS AT RUSSIA S NPP WITH FAST REACTORS

Fusion Development Facility (FDF) Mission and Concept

ENGINEERING OF NUCLEAR REACTORS. Fall December 17, 2002 OPEN BOOK FINAL EXAM 3 HOURS

Radioactive Waste Characterization and Management Post-Assessment Answer Key Page 1 of 7

CRITICAL AND SUBCRITICAL EXPERIMENTS USING THE TRAINING NUCLEAR REACTOR OF THE BUDAPEST UNIVERSITY OF TECHNOLOGY AND ECONOMICS

NUCLEAR EDUCATION AND TRAINING COURSES AS A COMMERCIAL PRODUCT OF A LOW POWER RESEARCH REACTOR

SPACE-DEPENDENT DYNAMICS OF PWR. T. Suzudo Japan Atomic Energy Research Institute, JAERI Tokai-Mura, Naka-Gun Japan

Final report on DOE project number DE-FG07-99ID High Pressure Xenon Gamma-Ray Spectrometers for Field Use

Institute of Atomic Energy POLATOM OTWOCK-SWIERK POLAND. Irradiations of HEU targets in MARIA RR for Mo-99 production. G.

A Project for High Fluence 14 MeV Neutron Source

Task 3 Desired Stakeholder Outcomes

ISIS TRAINING REACTOR: A REACTOR DEDICATED TO EDUCATION AND TRAINING FOR STUDENTS AND PROFESSIONALS

HR-Z SERIES Mild Radiation Resistance LVDT

WM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA

A Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations

Materials Science. Fission Chamber Calibration Tests at NRU

Defining quality standards for the analysis of solid samples

HOW ADVANCED PYROMETERS INCREASE THERMAL PROCESS REPEATABILITY AND PRODUCT QUALITY

Boron-based semiconductor solids as thermal neutron detectors

Three-dimensional RAMA Fluence Methodology Benchmarking. TransWare Enterprises Inc., 5450 Thornwood Dr., Suite M, San Jose, CA

ITER DIAGNOSTIC PORT PLUG DESIGN. N H Balshaw, Y Krivchenkov, G Phillips, S Davis, R Pampin-Garcia

INTRODUCTION Strained Silicon Monochromator Magnesium Housing Windows for Monochromator Shutter and Collimator Fission Detector HOPG Monochromator

We are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists. International authors and editors

Excerpt from the Proceedings of the COMSOL Conference 2009 Bangalore

MCNP CALCULATION OF NEUTRON SHIELDING FOR RBMK-1500 SPENT NUCLEAR FUEL CONTAINERS SAFETY ASSESMENT

6. ELECTRODE EXPERIMENT

BUILDING LOW-COST NANO-SATELLITES: THE IMPORTANCE OF A PROPER ENVIRONMENTAL TESTS CAMPAIGN. Jose Sergio Almeida INPE (Brazil)

CHAPTER 4: NUCLEAR INSTRUMENTATION MODULE 2: LOG RANGE DETECTORS

M.Cagnazzo Atominstitut, Vienna University of Technology Stadionallee 2, 1020 Wien, Austria

Neutron irradiation test of Hamamatsu, SensL and AdvanSiD UV-extended SiPMs

Quality control of neutron-absorber materials for the nuclear fuel cycle, Principle of the JEN-3 neutron Backscattering gauge

TEPCO s Activities on the Investigation into Unsolved Issues in the Fukushima Daiichi NPS Accident

SUB-CHAPTER D.1. SUMMARY DESCRIPTION

EVALUATION OF PWR AND BWR CALCULATIONAL BENCHMARKS FROM NUREG/CR-6115 USING THE TRANSFX NUCLEAR ANALYSIS SOFTWARE

(1) SCK CEN, Boeretang 200, B-2400 Mol, Belgium (2) Belgonucléaire, Av. Arianelaan 4, B-1200 Brussels, Belgium

Nuclear Research Facilities in Russia for innovative nuclear development N. Arkhangelskiy, ROSATOM IAEA Consultancy Meeting June 2013

Experience with different methods for on- and off-line detection of small releases of fission products from fuel elements at the HOR

Measurements with the new PHE Neutron Survey Instrument

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 4. Title: Control Rods and Sub-critical Systems

Neutronic Calculations of Ghana Research Reactor-1 LEU Core

Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB

Metropolitan Community College COURSE OUTLINE FORM LAB: 3.0

Neutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations

Development of Microwave Engine

TRANSMUTATION OF AMERICIUM AND CURIUM: REVIEW OF SOLUTIONS AND IMPACTS. Abstract

The Dynamical Loading of the WWER440/V213 Reactor Pressure Vessel Internals during LOCA Accident in Hot and Cold Leg of the Primary Circuit

Profile SFR-64 BFS-2. RUSSIA

Super High AUTO (SHA) Series

ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS

Estimation of accidental environmental release based on containment measurements

New irradiation zones at the CERN-PS

SPentfuel characterisation Program for the Implementation of Repositories

TECHNICAL WORKING GROUP ITWG GUIDELINE ON IN-FIELD APPLICATIONS OF HIGH- RESOLUTION GAMMA SPECTROMETRY FOR ANALYSIS OF SPECIAL NUCLEAR MATERIAL

Nuclear Theory - Course 227 FAILED FUEL MONITORING

USA HTR NEUTRONIC CHARACTERIZATION OF THE SAFARI-1 MATERIAL TESTING REACTOR

JHR PROJECT. IRRADIATION DEVICES IN-SERVICE INSPECTION OF NUCLEAR PRESSURE EQUIPMENT S.

General Overview of Gas Filled Detectors

Introduction. Principle of Operation

CRYOGENIC CONDUCTION COOLING TEST OF REMOVABLE PANEL MOCK-UP FOR ITER CRYOSTAT THERMAL SHIELD

DOE NNSA B&W Y-12, LLC Argonne National Lab University of Missouri INR Pitesti. IAEA Consultancy Meeting Vienna, August 24-27, 2010

Application of the Dynamic Control Rod Reactivity Measurement Method to Korea Standard Nuclear Power Plants

Decay heat calculations. A study of their validation and accuracy.

RADIOLOGICAL IMPACT OF THE TRIGAACCELERATOR-DRIVEN EXPERIMENT (TRADE)

NDT as a tool, for Post-Irradiation Examination.

Reactor Operation with Feedback Effects

DEVELOPMENT OF HIGH RESOLUTION X-RAY CT TECHNIQUE FOR IRRADIATED FUEL ASSEMBLY

Metallized polyester film capacitors MKT 470

Reliability and Traceability in Radiation Calibration

Grounding and Shielding

Gamma and X-Ray Detection

Characterization of waste by R2S methodology: SEACAB system. Candan Töre 25/11/2017, RADKOR2017, ANKARA

Module 2. Measurement Systems. Version 2 EE IIT, Kharagpur 1

Fundamentals of Nuclear Power. Original slides provided by Dr. Daniel Holland

AREP Series Aluminum Solid Electrolytic Capacitors Aluminum Solid Electrolytic Capacitors

Reproduction of Fleischmann and Pons experiments

The Silicon-Tungsten Tracker of the DAMPE Mission

A Report On DESIGN OF NEUTRON SOURCES AND INVESTIGATION OF NEUTRON BASED TECHNIQUES FOR THE DETECTION OF EXPLOSIVE MATERIALS

Fukushima Daiichi Nuclear Power Station Unit 2 Primary Containment Vessel Internal Investigation

A SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR

Utilization of Egyptian Research Reactor and modes of collaboration

Design and production of Scintillation Detectors

PWR CONTROL ROD EJECTION ANALYSIS WITH THE MOC CODE DECART

Nordson MARCH Concord, CA, USA

12 Moderator And Moderator System

Radiation Detection and Measurement

Neutron reproduction. factor ε. k eff = Neutron Life Cycle. x η

RS INDUSTRY LIMITED. RS Chip Array ESD Suppressor APPROVAL SHEET. Customer Information. Part No. : Model No. : COMPANY PURCHASE R&D

Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source

Transcription:

HIGH TEMPERATURE FISSION CHAMBERS: STATE-OF-THE-ART J.P. Trapp CEA/DRN/DER S. Haan CEA/DTA/LETI/DEIN L. Martin J.L. Perrin M. Tixier Centrale PHENIX CNPE Creys-Malville Philips Photonics Abstract In the control and the surveillance of fast breeder reactors, high temperature fission chambers able to operate in extremes of temperature and gamma dose perform two essential functions: In-vessel integrated neutronic control; Clad failure detection by integrated detectors. In addition, they can be used for example to: Measure the weight of the control rods; Monitor the insertion of new sub assemblies (SAs) and withdrawal of irradiated SAs; Eventually monitor the neutron flux in Boiling Water Reactors (BWR). Since 1970, a major research development and qualification programme has been undertaken in France by the CEA in very close collaboration with the Philips Photonics France, and the staff of PHENIX and SUPERPHENIX fast breeder reactors. This programme has resulted in the development of: Dedicated manufacturing processes for fission chambers to cope with the specific conditions in fast breeder reactors; A complete range of detectors to cover all other possible applications. This paper reviews: The detectors in their dedicated applications; The main problems encountered, studies made and solutions found; The detector qualification status; The performance of the detectors in the French fast breeder reactors.

Introduction To prevent a main core accident in the reactors, the reactor protection instrumentation must provide fast, continuous and reliable data on the reactor conditions. Some of the best detectors for this purpose are high-temperature fission chambers. Several types of fission chambers have been specially developed for: Neutron monitoring and control in the PHENIX and SUPERPHENIX reactors and also for the European Future Reactor (EFR) project; Surveillance and protection on the clad failures using fission chambers integrated in the vessel; Specific measurements such as reactivity weighting control rods and monitoring the insertion and withdrawal of irradiated material sub assemblies. Such fission chambers could also be used wherever conditions are particularly harsh, for instance as in core detectors in a Boiling Water Reactor (BWR). Since 1970, a major development programme for the French fast breeder reactors has been conducted and managed by the French Atomic Commission (CEA) in close collaboration with Philips Photonics. The programme aimed to develop, manufacture and qualify a new family of high temperature fission chambers and associated electronics able to cover a wide dynamic range. This paper reviews the programme, advances in detector manufacturing technology, and detector performances in the French fast breeder reactors. High temperature fission chambers and associated electronics In fast breeder reactors, the high temperature detectors are used for: Neutron monitoring Start-up system at PHENIX: at shutdown state, the counting rate under the vessel is very low (only the electronic noise); to monitor conditions at shutdown and during the first stage of start-up, a detector integrated in the vessel, near the core, is needed. Auxiliary neutron monitoring system for SPX: during core loading and also during the neutron measurements, an auxiliary neutron detection system in a central channel of the core has been used in view of monitor the reactivity and to protect the reactor; three fission chambers (type CFUX14) were used in this system from 1985 to 1990. Integrated neutron monitoring system for EFR project: a neutron monitoring system in the core cover plug is needed for the EFR reactor project for which no neutron guides are forecast; about nine fission chambers (type CFUC07) would be needed for the reactor protection and surveillance instrumentation to cover the core from shutdown to full power.

Cladding ruptures detection The design concept of clean sodium adopted in France for FBR reactors demands the immediate detection of a clad failure and to shutdown the reactor before there is any fuel loss in the primary circuit. In addition to the conventional sipping system, an experimental system is used in the SPX reactor, since 1985, to detect the clad failures with integrated detectors: eleven fission chambers (type CFUC06) in the vessel; eight of which are located behind the eight Intermediate Heat Exchangers (IHX). Other applications Reactivity weighting control rods: these measurements are extremely important for safety; the rod drop method can be used as on FBR, using high temperature fission chambers in vessel, as well on PWR reactors, with ex-core detectors. Monitoring sub-assemblies during their insertion / withdrawal to detect any spurious handling. In-core neutron monitoring: the eventual monitoring of the neutron flux in-core of other reactors such as BWRs. Associated electronics The detector is, of course, only one part of a measuring system for one channel. An electronic system is also necessary. Therefore, a considerable effort was devoted to the design of an electronic system that could cover a wide measuring range from start-up to full power, with the fission chambers operating in the three modes: pulse mode, fluctuation (Campbelling) mode and current mode. It is also tested in reactor. Detector challenges and technical solutions The development of high temperature fission chambers started in 1970, from a collaboration between the CEA/DEIN and Philips Photonics. Three detector types were developed, mainly for pulse mode operation: CFUE type (sensitivity 0,01c.s-1/nv =7mm); CFUD type (sensitivity 0,1c.s-1/nv =36mm); CFUC type (sensitivity 1,0 c.s-1/nv =48mm). Several prototypes of each type were manufactured and tested in experimental reactors at Saclay and Fontenay, France.

The goal was to obtain a reliable high sensitivity detector able to operate in very harsh conditions (temperature, neutron and gamma flux) over a wide dynamic range. The signals from these detectors had to be transmitted down cables (cable to withstand the same conditions) to the electronic measuring equipment with no significant signal degradation. For more than ten years, several tests were made in experimental reactors and in PHENIX FBR. These tests enabled us to define the best detector technology, and provided a better understanding of what happens to detectors in severe conditions. This allowed some detector parts to be improved, securing long-term reliability in harsh conditions. Environmental influence on detectors High temperature around 600 C High temperature has a large influence on detector components, causing: A reduction in insulation resistance of ceramic insulator; Produces spurious discharges on the surface of the ceramic insulators at high voltage, generating pulses similar to neutron pulses; Outgassing of the chamber s metal body, which contaminates the filling gas; Combination of some gases such as nitrogen by the materials of the chamber; Weakening of the metal body and electrode support structure, making it difficult to use a small electrode spacing. High neutron and gamma flux The high neutron and gamma flux aggravate the high temperature effects, causing: Increased parasitic current in the cable and on the insulators; Increased outgassing and gas combination. Technical solutions used Designing a low sensitivity fission chamber is fairly straight-forward because only two uranium coated electrodes are required. High temperature fission chambers (filled with pure argon with a sensitivity between 0,01 and 0,1 c.s -1 per nv and a collection time less than 100 nsec should be possible. The difficulties arise with increasing sensitivity; for instance: The area of uranium layer must be increased. In addition, more than two electrodes with are needed and the design of the mechanical assembly starts to become difficult; The electrode spacing must be increased (owing to mechanical considerations), so the detector must be filled with a mixture of argon and nitrogen to maintain a collection time < 100 nsec.

To meet the desired characteristics (see Figure 1): Special alumina ceramic feedthroughs and seals were designed and tested at high temperatures and high gamma flux; Different metals were evaluated. Our final choice was Inconel 600 for the electrodes and detector body. The external cable shield was kept as traditional stainless steel; High immunity parasitic and mineral insulated cable was chosen and tested in pulse mode at high temperature and high gamma flux; the cable was sealed at both ends by specially designed feedthroughs; To avoid spurious breakdown pulses and reduce the leakage current seen by measuring electronics in current mode, a guarded design with two cables (one cable for HV, one cable for signal) was adapted for CFUX14, CFUC06 and CFUC07. However, since 1986, considerable improvements have been made in reducing breakdown pulse noise. For the future, a new design with high sensitivity wide dynamic range fission chambers will use only one cable for both (HV and signal); Special vacuum and gas treatments were developed to reduce outgassing of metal parts and to prevent gas combination. A mixture of argon and nitrogen can be used in our detectors to reduce the collection time in pulse mode. The CFUC07 was filled with this mixture and tests results indicated high reliability and no change in collection time. The nitrogen did not disappear; Special electrode assembly was developed and tested under high temperature and exposed to shocks and vibrations. Tests and qualification To evaluate the performance of the high temperature fission chambers and cable during the development phase, the following tests were made to characterise the prototype detectors. Preliminary laboratory tests These are performed systematically on all detectors before operation in the PHENIX or SPX reactors and comprise: Electrical and thermal tests The insulation resistance and capacitance of each cable were measured over a wide temperature and the absence of breakdown pulses under high voltage confirmed. For example, the CFUC07 and its cables were tested 16 hours at 650 C and no deterioration of its main characteristics were observed.

Figure 1. Neutron tests with RaBe source These tests were performed to characterise the pulse shapes from a fission chamber exposed to a low neutron flux (4 to 5x10 +3 n.cm 2.s -1 ) and to enable the chamber s sensitivity to be evaluated. Complementary tests High gamma flux tests The influence of gamma radiation was determined in pulse mode operation and the sensitivity to gamma radiation was measured in current and fluctuation (Campbelling) modes. These tests were performed at Saclay in the gamma irradiator PAGURE ( 60 Co), with dose rates up to several kgy.h -1.

Neutron tests in an experimental reactor These tests verified the linearity of the fission chamber response over all three operating modes (pulse, Campbelling, current) and confirmed the overlapping zones between these modes (overlapping zone). For these tests, the ULYSSE experimental reactor at Saclay was chosen because it can deliver a neutron flux, constant over several decades. Experimental qualification tests Several prototypes underwent extensive endurance tests in the laboratory and in experimental reactors to help us in our choice and to confirm the chosen manufacturing technology for the application. For example: one prototype of a CFUC07 fission chamber was tested in the laboratory at 600 C for 10 000 hours with no detectable degradation in its main characteristics (for an earlier prototype, the nitrogen disappeared completely in less than 2000 hours under the same conditions). Another prototype was tested in the MELUSINE reactor at Grenoble during three or four months, at an average temperature of 565 C and under a neutron flux ranging from 8.10 +10 to 1.8.10 +11 n.cm -2.s -1. After a neutron fluence of about 7.10+17 n.cm -2, the charge collection time and the discrimination curve for the new prototype were unchanged. Cables and associated electronics Special coaxial cables manufactured by Thermocoax Company were integrated with the detectors. These cables generally include a mineral insulator (magnesia), a metal sheath (stainless steel, copper and iron) and a copper core (with zirconia). The cable diameter is 4 or 6 mm and the characteristic impedance is 30 or 50 Ω. Several tests were performed to evaluate or to measure breakdown voltage, transfer impedance, attenuation coefficient and insulation resistance as a function of temperature. Similarly, special (organically insulated) cables with high immunity to parasitic signals were used to make the long (150 to 300 m) connection between the detector and its associated electronics. A special electronic system able to operate in all three operation modes (pulse, fluctuation and current) was also developed for the CFUC07 sensor. Particular emphasis was given to: Decreasing the background noise for the Campbelling mode to improve the transition between the pulse and fluctuation modes; Automatic changeover operating modes.

Experience in reactors Several different high temperature fission chambers have been tested and operated in PHENIX and SPX reactors for the purposes indicated in the section entitled High temperature fission chambers and associated electronics. Implementation in reactor PHENIX CFUC06. One chamber in each of the two channels (SS8270-7082) located in the lateral shielding. One in a lateral channel, near one of the intermediate heat exchangers. PHENIX CFUC07, CFUE22 and CFUE42. One of each chamber in channel SS8270, just above the CFUC06. SPX CFUX14. Three chambers located in a movable device in the central channel (30/30) of the SPX core. SPX CFUX06. Eleven chambers: eight located behind the eight intermediate heat exchangers and three surrounding one of the exchangers. Operation in reactor Today, only the three CFUX14 have been withdrawn from the SPX reactor, and this was for maintenance of mechanical support the chambers themselves were still fully operational. All of the other chambers (in or out of core) continue to operate. The neutron fluence received by each chamber depends on its position in the vessel (in or out of core and distance from the core centre).

So far, the detectors have been operated between five and fifteen years depending on the chamber type. The operating temperature ranges between 180 C (when reactor is shutdown) and 550 C (when reactor is at full power). The following table shows the main parameters of this reactor experience. Integrated neutron flux (n.cm -2 ) t x T (sec x C) High temperature fission chambers: Operational conditions CFU PHENIX 2 x 10 +13 to 3 x 10 +18 (*) C06 SPX 5 x 10 +8 to 2 x 10 +11 (*) 1 to 2 x 10 +11 1,5 x 10 +11 (*) Following the position or regard to the centre of the core. CFUX14 SPX CFUC07 - CFUE22 and CFUE42 PHENIX 6 to 15 x 10 +17 3 to 4 x 10 +16 8 to 11 x 10 +10 7 to 9 x 10 +9 Operational characteristics Generally, the operational behaviour of a fission chamber is characterised by two main parameters: a) The slope and the length for the high voltage plateau [N(c/s)=f(HV)] in pulse or Campbelling mode and for the saturation plateau [I(mA) = f(hv)] in current mode; b) The discrimination curves of counting rate as a function of discrimination voltage [N(c/s) = f(hv)] in pulse mode. CFUC06 at PHENIX a) Plateau gradient [(DN/N) / DV] (% / volt) CFUC06 at SPX 1981 1987 1995 1984 1996 P(Mw) 588 100 350 Factory with a neutron source 1500 Pulse mode 0,021 0,03 0,060 0,037 ± 0,0043 (*) 0,0363 ± 0,0180(*) CFUX14 at SPX CFUC07 at PHENIX 1986 1986 1989 1989 1991 1993 1995 1995 P(Mw) 3000 307 490 1470 10KW 350 350 10 KW Pulse mode 0,019 0,022 Campbelling 0,047 0,055 0,018 0,047 Current mode 0,037 0,042 0,032 0,042 0,012 0,012 0,014 0,013 In each case, the length of the plateau is equal to or higher than 250 volts.

b) Discrimination or saturation curves - reactor shutdown (P=0 Mw) These curves describe the conditions in the measurement channel (sensor, cable and electronics) as a function of the time and indicate possible operational problems. (*) Average value on 11 detectors: the statistical fluctuations of the counting rate explains the spread between the two results ( #900 c/s in factory and 1 to 100 c/s in reactor). Over the indicated period, the main characteristics of these fission chambers have remained constant.

c) Discrimination or saturation curves in operation In operation, the discrimination curve (in pulse mode) or saturation curve (in current or Campbelling mode) indicate a possible change of the condition of the measurement channel and especially the in the behaviour of the detectors. Throughout the long test period and operating in real conditions, no problems have occurred. The operational parameters such as the slope of the current plateau (or Campbelling plateau) have remained constant.

Particularly in pulse mode operation, no spurious pulses or breakdowns were observed, even at high temperature (>500 C). during a voluntary scram, the counting rate immediately assumed its proper shutdown value; for the high dynamic fission chamber with the three operation modes, the automatic reversal to pulse mode from current mode (via the Campbelling mode) occurred perfectly. Conclusion Now, this twenty-year programme has been fully completed, except for the CFUC07 endurance qualification test in the PHENIX reactor. Today, reactor instrumentation designers have at their disposal a complete range of sensors able to operate in very harsh conditions (high temperature and high gamma dose) with a large range of sensitivity. Such detectors are now in operation in the French fast breeders, but could be also used in BWR or HTR reactors for in-core neutron monitoring, handling operations, control, surveillance and many other operations. A future development programme could complete these studies; for example, the development of a CFUC08 chamber (similar to the CFUC07 with only one integrated cable); the initial results of the first development phase of a such detector, driven by Philips Photonics, were quite positive. However the development of a new prototype is presently postponed. REFERENCES [1] High Temperature Fission Chambers: Research and Development Programme for LFBRs. Third International Conference on Liquid Metals Technology for Energy Production. Oxford, UK. April 1984. C. BERLIN, J.C. PERRIGUEUR, J. DUCHENE CEA France. M. TIXIER Société RTC-Hyperelec France. [2] High Temperature and Sensitivity Fission Chambers for LMFBRs Neutronic Control. NEACRP Specialists Meeting on In-core Instrumentation and Reactor Core Assessment. Pittsburgh, USA. October 1991. J.P. TRAPP, E. BACCONNET, T. DOMENECH CEA France. M. TIXIER Philips Photonics. [3] High Temperature and Sensitivity Fission Chambers: Qualification of the CFUC07 in Reactor. Specialists Meeting on Improvements in Nuclear Radiation for Nuclear Power Plants. Paris, October 1993. J.P. TRAPP, A. BOURGERETTE, C. VUILLEMIN, C. VAUX CEA France. L. MARTIN Centrale Phénix. M. TXIER, M. LAUB Philips Photonics.