Among GEN IV projects for future nuclear power plants, lead-cooled fast reactors (LFRs) seem to be a very interesting solution due to their benefits in terms of fuel cycle, coolant safety, and waste management. The novelty of this matter causes some open issues about coolant chemical aspects, structural aspects, monitoring instrumentation, etc. Particularly, hard neutron flux spectra would make traditional neutron instrumentation unfit to all reactor conditions, i.e., source, intermediate, and power range. Identification of new models of nuclear instrumentation specialized for LFR neutron flux monitoring asks for an accurate evaluation of the environment the sensor will work in. In this study, thermal hydraulics and chemical conditions for the LFR core environment will be assumed, as the neutron flux will be studied extensively by the Monte Carlo transport code MCNPX (Monte Carlo N-Particles X-version). The core coolant’s high temperature drastically reduces the candidate instrumentation because only some kinds of fission chambers and self-powered neutron detectors can be operated in such an environment. This work aims at evaluating the capabilities of the available instrumentation (usually designed and tailored for sodium-cooled fast reactors) when exposed to the neutron spectrum derived from the Advanced Lead Fast Reactor European Demonstrator, a pool-type LFR project to demonstrate the feasibility of this technology into the European framework. This paper shows that such a class of instrumentation does follow the power evolution, but is not completely suitable to detect the whole range of reactor power, due to excessive burnup, damages, or gamma interferences. Some improvements are possible to increase the signal-to-noise ratio by optimizing each instrument in the range of reactor power, so to get the best solution. The design of some new detectors is proposed here together with a possible approach for prototyping and testing them by a fast reactor.
Skip Nav Destination
e-mail: luigi.lepore@uniroma1.it
e-mail: romolo.remetti@uniroma1.it
e-mail: mauro.cappelli@enea.it
Article navigation
October 2016
Research Papers
On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED
Luigi Lepore,
e-mail: luigi.lepore@uniroma1.it
Luigi Lepore
SAPIENZA, University of Rome
, SBAI Department, Via Antonio Scarpa, 14-00161 Rome
, Italy
e-mail: luigi.lepore@uniroma1.it
Search for other works by this author on:
Romolo Remetti,
e-mail: romolo.remetti@uniroma1.it
Romolo Remetti
SAPIENZA, University of Rome
, SBAI Department, Via Antonio Scarpa, 14-00161 Rome
, Italy
e-mail: romolo.remetti@uniroma1.it
Search for other works by this author on:
Mauro Cappelli
e-mail: mauro.cappelli@enea.it
Mauro Cappelli
ENEA FSN-FUSPHY-SCM, Frascati Research Center
, Via Enrico Fermi, 45-00044 Frascati (Rome)
, Italy
e-mail: mauro.cappelli@enea.it
Search for other works by this author on:
Luigi Lepore
SAPIENZA, University of Rome
, SBAI Department, Via Antonio Scarpa, 14-00161 Rome
, Italy
e-mail: luigi.lepore@uniroma1.it
Romolo Remetti
SAPIENZA, University of Rome
, SBAI Department, Via Antonio Scarpa, 14-00161 Rome
, Italy
e-mail: romolo.remetti@uniroma1.it
Mauro Cappelli
ENEA FSN-FUSPHY-SCM, Frascati Research Center
, Via Enrico Fermi, 45-00044 Frascati (Rome)
, Italy
e-mail: mauro.cappelli@enea.it
Manuscript received October 7, 2015; final manuscript received August 30, 2016; published online October 12, 2016. Assoc. Editor: Leon Cizelj.
ASME J of Nuclear Rad Sci. Oct 2016, 2(4): 041002 (8 pages)
Published Online: October 12, 2016
Article history
Received:
October 7, 2015
Revision Received:
August 30, 2016
Accepted:
August 30, 2016
Citation
Lepore, L., Remetti, R., and Cappelli, M. (October 12, 2016). "On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED." ASME. ASME J of Nuclear Rad Sci. October 2016; 2(4): 041002. https://doi.org/10.1115/1.4033697
Download citation file:
Get Email Alerts
Cited By
Greeting From the President-elect of JSME
ASME J of Nuclear Rad Sci
Introduction to Nuclear Forensics Analysis Techniques
ASME J of Nuclear Rad Sci
Related Articles
Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs
ASME J of Nuclear Rad Sci (October,2017)
Design of a Tritium-In-Air Monitor Using Field-Programmable Gate Arrays
ASME J of Nuclear Rad Sci (October,2016)
CANDU Reactor Space-Time Kinetic Model for Load Following Studies
J. Eng. Gas Turbines Power (May,2011)
Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly
ASME J of Nuclear Rad Sci (April,2024)
Related Proceedings Papers
Related Chapters
Regional/Neutron Overpower Protection (ROP/NOP)
Fundamentals of CANDU Reactor Physics
Reactor Shutdown and Reactor Restart
Fundamentals of CANDU Reactor Physics
Constructing Dynamic Event Trees from Markov Models (PSAM-0369)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)