Skip to main content
SpringerLink
Log in
Book cover

Handbook of Nuclear Engineering pp 2053–2184Cite as

Reactor Physics Experiments on Zero Power Reactors

  • Reference work entry

Abstract

The CEA (Commissariat á l’Energie Atomique) is strongly involved in R&D research programs concerning the use of nuclear energy as a clean and reliable source of energy and consequently is working on the present and future generations of reactors on various topics such as ageing plant management, optimisation of the plutonium stockpile, waste management and innovative systems exploration. Core physics studies are an essential part of this comprehensive R&D effort. In particular, the Zero Power Reactors (ZPR) of CEA: EOLE, MINERVE and MASURCA play an important role in the validation of neutron physics calculation tools (codes and nuclear data). Most recent programs notably contributed to: Obtain a very large and accurate experimental database for nuclides arising in plutonium and waste management (heavy nuclides and long lived fission products). Explore long-lived nuclides transmutation. Support the present French PWR fleet and the future reactors such as EPR. Explore innovative systems and new concepts in terms of new materials and fuels (ABWR, new MTR such as the Jules Horowitz Reactor under construction in Cadarache). Improve the physics of hybrid systems, involving a sub-critical reactor coupled with an external accelerator (ADS). A vast majority of theses programs are carried out within the frame of international collaboration. The Zero Power Reactors are also essential tools in the activities of teaching various topics related to experimental reactor physics. In particular, practical work on the operation and control of reactors and the associated methods of experimentation is done by the students enrolled in the “Génie Atomique” French nuclear engineering school. The experimental programs defined in the EOLE, MINERVE and MASURCA facilities aim at improving the calculation routes by reducing the uncertainties of the experimental databases. They also provide accurate data on innovative systems in terms of new materials (moderating and decoupling materials) and new concepts (ADS, ABWR, GEN IV) involving new fuels, absorbers and coolant materials. After a description of the previous experimental programs, an overview of the future experimentation is given in this chapter.

This is a preview of subscription content, log in via an institution.

Chapter
USD   29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD   1,599.99
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Hardcover Book
USD   1,999.99
Price excludes VAT (USA)
  • Durable hardcover edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Learn about institutional subscriptions

References

  • Darrouzet M, Salvatores M (1988) Reactor physics activities in France. In: Proceedings of the international reactor physics conference, vol I, p 1, ANS, Jackson Hole, 18–22 Sept 1988

    Google Scholar 

  • Fougeras P, Chauvin JP, Cabrillat JC, Martini M (1996) The use of the CEA critical facilities for the assessment of the physics. In: ENS class1 topical meeting on research facilities for the future of nuclear energy, Brussels, 4–6 June 1996

    Google Scholar 

  • Bignan G, Rippert D, Fougeras P (2001) The key role of critical mock-up facilities for neutron-physic assessment of advanced reactors: an overview of CEA/CADARACHE tolls. In: ARWIF 2001, Chester, 23–26 Oct 2001

    Google Scholar 

  • Bignan G, Zaetta A, Fougeras P, Jacqmin R, Bosq JC, Klein JC, Lyoussi A, Mellier F, Blaise P, Chabre A, Sacristan P (2008) Experimental reactor physic perspective in France. In: PHYSOR2008 international conference on the physics of reactor, Interlaken, 14–19 Sept 2008

    Google Scholar 

  • Fougeras P, Porracchia A (2006) Les maquettes critiques du CEA. RGN No. 2, March–April 2006

    Google Scholar 

  • Fougeras P, Hudelot JP, Antony M, Mellier F, Destouches C, Cathalau S, Blaise P, Thiollay N (2005a) EOLE, MINERVE and MASURCA facilities and their associated neutron experimental programmes. In: 13th international conference on nuclear engineering ICONE13, Beijing, 16–20 May 2005

    Google Scholar 

  • Fougeras P, Chabre A, Mergui C (2005b) The place of EOLE, MINERVE and MASURCA facilities in the R&D activities of the CEA. In: IGORR 10: international group on research reactors, Gaithersburg, 12–16 Sept 2005

    Google Scholar 

  • Fougeras P, Hudelot JP, Rippert D, Mellier F, Blaise P, Antony M, Huot N (2007) The place of EOLE, MINERVE and MASURCA facilities in the R&D Activities of the CEA. In: PHYTRA 2007, GMTR, Marrakech, 14–16 March 2007

    Google Scholar 

  • International Handbook of Evaluated Reactor Physics Benchmark Experiments. Nuclear Energy Agency, NEA/NSC/DOC(2006)1, March 2007

    Google Scholar 

  • IRPhE – An International Reactor Physics Benchmark Experiments Database. http://www.inel.gov/energy/nuclear/irphep/

  • Soule R, Fougeras P, Assal W, Blaise P, Bompas CA, Cathalau S, Chaussonnet P, Chauvin JP, Granget G, Hudelot JP, Laurens JM, Laval V, Lebrat JF, Martini M, Philibert H, Flamenbaum G, Salvatores M (1999) Neutron integral experiments in support to the Pu utilization and waste incineration. In: Global’99 international conference on the future nuclear systems, Jackson Hole, 29 Aug–3 Sept 1999

    Google Scholar 

  • Blaise P, Fougeras P, Philibert H, Laval V, Perret G (2002) Preliminary analysis of the BASALA-H experimental programme. In: ICONE10, Arlington, 14–18 April 2002

    Google Scholar 

  • Blaise P, Fougeras P, Santamarina A, Cathalau S (2004) Integral needs for MOX powders: state-of-the-art at CEA ∖ Cadarache on MOX fuel experiments. In: OECD/NEA workshop on MOX powders, Paris, 13–14 April 2004

    Google Scholar 

  • Blaise P, Thiollay N, Fougeras P, Pont T, Destouches C, Beretz D, Lee Y-K, Chiron M, Janski S (2006) Neutron vessel fluence assessment in the 1300MWe NPP French Fleet: the FLUOLE program in EOLE. In: ICAPP’06 international congress on advances in nuclear power plants, Reno, 4–8 June 2006

    Google Scholar 

  • Blaise P, Thiollay N, Fougeras P, Huot N, Laval V, Roche A (2007) Full MOX ABWR neutron characterization with void increase: the FUBILA program M&C + SNA 2007: joint international topical meeting on mathematics and computation, supercomputing in nuclear applications, Monterey, 15–19 April 2007

    Google Scholar 

  • Blaise P, Vidal JF, Santamarina A (2009a) Validation of the REL2005 code package on poisoned PWR type assemblies through the CAMELEON experimental program. In: ICAPP 09, Tokyo, 10–14 May 2009

    Google Scholar 

  • Blaise P, Vaglio-Gaudard C, Vidal JF, Ruggieri JM (2009b) Deterministic modeling of 100% MOX ABWR lattices with increasing void fraction: validation of the REL2005 code package on FUBILA experimental program. In: ICAPP 09, international congress on advances in nuclear power plants, Tokyo, 10–14 May 2009

    Google Scholar 

  • Blaise P, Thiollay N, Fougeras P (2010) Monte Carlo modelling of increasing void fraction in 100% MOX ABWR lessons drawn from the FUBILA program. J Nucl Sci Technol

    Google Scholar 

  • Blaise P, Thiollay N, Huot N, Santamarina A, Fougeras P (2010) High-burn up 10 ×10 100% MOX ABWR FUBILA experimental program analysis with APOLLO2.8 and TRIPOLI-4 codes. Ann Nucl Energy

    Google Scholar 

  • Blaise P, Litaize O, Vidal J-F, Santamarina A (2010) Qualification of the French APOLLO2.8/ CEA2005V4 code package on absorber clusters in 17 ×17 PWR type lattices through the CAMELEON program. In: PHYSOR2010, Pittsburgh, 9–14 May 2010

    Google Scholar 

  • Cathalau S (1988) Qualification des propriété neutroniques des réacteurs sous modéré à l’eau légère. PhD thesis, Orsay, 19 June 1988

    Google Scholar 

  • Cathalau S, Chauvin JP, Maghnouj A, Fougeras P (1996a) Calculation of 2D and 3D local void effects in MOX reactors: the EPICURE results. In: International conference on the physics of reactors PHYSOR’96, p C-11, Mito, Japan 16–20 Sept 1996

    Google Scholar 

  • Cathalau S, Cabrillat JC, Chauvin JP, Finck PJ, Fougeras P, Flamenbaum G, Matsu-Ura H, Ueji M, Yamamoto T (1996b) MISTRAL: an experimental programme in the EOLE facility devoted to MOX core physics. In: International conference on the physics of reactors PHYSOR’96, p H-84, Mito, Japan 16–20 Sept 1996

    Google Scholar 

  • Cathalau S, Fougeras P, Santamarina A (1998) First validation of neutronic lattice parameters of overmoderated 100% MOX fueled PWR cores on the basis of the MISTRAL experiment. In: International conference on the physics of nuclear science and technology. Future nuclear systems, p 393, ANS, Long Island, 5–8 Oct 1998

    Google Scholar 

  • Cathalau S, Fougeras P, Blaise P, Thiollay N, Santamarina A, Litaize O, Chabert C, Yamamoto T, Iwata Y, Umano T, Kanda R, Girieud P, Biron D, Tatsumi M, Kan T, Ando Y, Ishii K (2002) Full MOX recycling in ALWR: lessons drawn through the MISTRAL program. In: PHYSOR 2002, Seoul, 7–10 Oct 2002

    Google Scholar 

  • Cathalau S, Fougeras P, Blaise P, Thiollay N, Santamarina A, Litaize O, Yamamoto T, Umano T, Nigon JL (2004) Advanced BWRs fully loaded with MOX fuel: the BASALA experimental program. In: PHYSOR 2004, Chicago, 25–29 April 2004

    Google Scholar 

  • Cerdan C (1984) Qualification du calcul des réseaux modérés à l’eau légère et empoisonnés au Gadolinium. PhD thesis, Orsay, 25 Oct 1984

    Google Scholar 

  • Chauvin JP, Granget G, Martini M, Mondot J, Lefebvre JC, Vallee A (1992) Validation of the experimental methods used in the EPICURE programme and their associated uncertainties. In: ANS topical meeting on advances in reactor physics CHARLESTON 1992

    Google Scholar 

  • Chauvin JP, Cabrillat JC, Fougeras P, Cathalau S, Finck PJ (1996) EPICURE: an experimental program devoted to the validation of the calculation scheme for the pressurized water reactor recycling MOX Fuel. In: International conference on the physics of reactors PHYSOR’96, p E-133, Mito, 16–20 Sept 1996

    Google Scholar 

  • Doutriaux D, Martin-Deidier L, Roshd M, Santamarina A (1983) CRISTO I et II. Expériences de qualification des calculs de criticité des stockages pour des assemblages REP. In: ICNC’83, Dijon, 19–22 Sept 1983

    Google Scholar 

  • Erradi L, Santamarina A, Litaize O (2003) The reactivity temperature coefficient analysis in light water moderated UO2 and UO2-PuO2 lattices. Nucl Sci Eng 144:47–74

    Google Scholar 

  • Fougeras P (1992) Qualification des schémas de calcul pour le recyclage du Plutonium dans les Réacteurs à Eau sous Pression. Expérience EPICURE. PhD thesis No. 2309, Orsay, 10 Nov 1992

    Google Scholar 

  • Fougeras P, Cathalau S, Mondot J, Klenov P (1995) Optimization of a calculation scheme for the treatment of Pu recycling in PWRs. Nucl Sci Eng 121:32–40

    Google Scholar 

  • Fougeras P, Cathalau S, Finck PJ, Klenov P (1996a) Improved calculational scheme for absorber clusters in 30% MOX fueled PWRs. In: International conference on the physics of reactors PHYSOR’96, p A-258, Mito, 16–20 Sept 1996

    Google Scholar 

  • Fougeras P, Garzenne C, Stankovski Z, Aigle R (1996b) Generalised geometry analysis of the EPICURE measurements of the effects of the radial displacement of a MOX or UO2 Fuel pin. In: International conference on the physics of reactors PHYSOR’96, p E-124, Mito, 16–20 Sept 1996

    Google Scholar 

  • Fougeras P, Blaise P, Cathalau S, Philibert H, Laval V, Chauvin JP, Girieud R, Santamarina A, Yamamoto T, Iwata Y, Ueji M (1999) MISTRAL-4: an experimental mockup in the EOLE facility devoted to high moderation 100% MOX core physics. In: Global’99 international conference on the future nuclear systems, Jackson Hole, 29 Aug–3 Sept 1999

    Google Scholar 

  • Klein JC, Thiollay N, Di Salvo J, Bignan G, Bosq JC, Sireta P, Wieryszkov JP, Alexandre P, Garnier D (2009) AMMON: an experimental program in the EOLE Critical facility for the validation of the JHR neutron and photon HORUS3D calculation scheme. In: IGORR12, Beijing, Oct 2009

    Google Scholar 

  • Litaize O, Santamarina A, Hervault M, Cathalau S, Fougeras P, Blaise P, Yamamoto T, Kanda R, Sasgawa M, Kikushi T (2004) Monte Carlo analysis of high moderation 100% MOX BWR cores using JEF2 and JENDL3 nuclear data. In: PHYSOR 2004, Chicago, 25–29 April 2004

    Google Scholar 

  • Martin-Deidier L, Santamarina A (1984) CAME LEON: a benchmark experiment of absorbers and burnable poisons in PWR assemblies. Trans Amer Nucl Soc, vol 1, 46–755

    Google Scholar 

  • Martin-Deidier L, Santamarina A, Cathalau S, Gomit JM, Chauvin JP (1986) ERASME: an extensive experiment for LWHCR design qualification. In: Topical meeting on reactor physics, Saratoga, Sept 1986

    Google Scholar 

  • Martin-Deidier L, Santamarina A, Cathalau S, Gomit JM, Chauvin JP (1987) Undermoderated PWR neutronic qualification through the ERASME experiments. In: Conf Int sur le développement en Physique des Réacteurs et méthodes de calcul, Paris, April 1987

    Google Scholar 

  • Mondot J, Gauthier JC, Chaucheprat P, Chauvin JP, Lefebvre JC, Vallee A (1990) EPICURE: an experimental programme devoted to the validation of the calculational schemes for plutonium recycling in PWRs. In: International conference on physics of reactor operation, design and computation (PHYSOR’90), vol 1, p VI-53, Marseille, 23–26 April 1990

    Google Scholar 

  • Porta J, Baldi S, Chauvin JP, Fougeras P (2001) Qualification of the neutronic efficiency of erbium at zero burnup. Nuclear Energy, vol 38, no. 3–4, February 2001

    Google Scholar 

  • Santamarina (1995) A Storage array of 3% LWR assemblies. The CRISTO II experiments in the EOLE reactor. NEA/NSC/DOC(95)03, LEU-COMB-THERM

    Google Scholar 

  • Santamarina A (1987) Temperature effects analysis in light water reactor lattices. Thermal cross-sections shapes and qualification through French integral experiments. In: IAEA-TEC DOC-491 proceedings of an IAEA advisory group meeting, Vienna, 7–10 Dec 1987

    Google Scholar 

  • Santamarina A, Martin-Deidier L (1982) Experimental qualification of the calculated subcriticality in high density fuel storage. In: Meet on advances in reactor physics and core thermal hydraulics, Kiamesha Lake, Sept 1982

    Google Scholar 

  • Santamarina A, Golinelli C, Erradi L (1984) Temperature effects analysis in light water reactor lattices. In: ANS topical meeting on reactor physics and shielding, Chicago, Sept 1984

    Google Scholar 

  • Santamarina A, Venard C, Blaise P, Rippert D, Fouillaud P, Girault E, Duhamel I, Rouyer V (2004) Critical experiments for criticality code validation on low-moderated MOX media with Appareillage-B and EOLE. In: WPNCS-MOX experiment meeting, Prague, 31 August 2004

    Google Scholar 

  • Santamarina A, Vaglio-Gaudard C, Blaise P, Huot N, Litaize O, Thiollay N, Vidal J-F (2008) The PERLE experiment for the qualification of heavy reflector. In: PHYSOR 2008, Interlaken, 14–19 Sept 2008

    Google Scholar 

  • Vidal J-F, Blaise P, Huot N, Guillot G, Litaize O, Santamarina A, Vaglio-Gaudard C (2008) Analysis of the FLUOLE experiment for the APOLLO2 validation of PWR core reflector. In: PHYSOR 2008, Interlaken, 14–19 Sept 2008

    Google Scholar 

  • Yamamoto T, Matsu-Ura H, Ueji M, Cathalau S, Cabrillat JC, Chauvin JP, Finck PJ, Fougeras P, Flamenbaum G (1997) Core physics experiment of 100% MOX core: MISTRAL. In: International conference on future nuclear systems’97 GLOBAL, p 395, Yokohama, 5–10 Oct 1997

    Google Scholar 

  • Yamamoto T, Iwata Y, Ueji M, Cathalau S, Fougeras P, Blaise P, Chauvin JP, Santamarina A (2000) BASALA: advanced BWR MOX core physics experiments. In: 2000 ANS international meeting on advances in reactor physics and mathematics and computation into the next millennium PHYSOR2000, Pittsburg, 7–12 May 2000

    Google Scholar 

  • Yamamoto T, Iwata Y, Umano T, Kanda R, Cathalau S, Fougeras P, Thiollay N, Blaise P, Santamarina A, Nigon JL (2002) BWR MOX core physics experiments and preliminary analysis. In: PHYSOR 2002, Seoul, 7–10 Oct 2002

    Google Scholar 

  • Anno J, Barreau A, Hudelot JP, Girault E, Fouillaud P, Toubon H (2003) French fission products experiments performed in Cadarache and Valduc. In: Results comparison ICNC 2003 conference, Tokai-Mura, Oct 2003

    Google Scholar 

  • Antony M, Pepino A, Di Salvo J, Lyoussi A, Bosq JC, Hudelot JP, Leconte P, Bernard D (2009) Oscillation experiments techniques in CEA MINERVE pool experimental reactor. In: ANIMMA, Marseille, 7–10 June 2009

    Google Scholar 

  • Bernard D, Santamarina A (2003) Doppler calculation challenge in MOX lattices. Qualification on MINERVE oscillation experiment. In: Nuclear mathematical and computational sciences conference, Gatlinburg, 6–11 April 2003

    Google Scholar 

  • Bernard D, Santamarina A, Sargeni A, Antony M, Hudelot JP (2006) Experimental validation of the LWR reactivity loss with burn up: analysis of spent fuel oscillation experiments. In: PHYSOR 2006 advances in nuclear analysis and simulation, Vancouver, 10–14 Sept 2006

    Google Scholar 

  • Chaucheprat P, Mondot J (1988) MORGANE S fission product capture measurement in a HCLWR high lattice. In: ANS topical meeting, Jackson Hole, Sept 1988

    Google Scholar 

  • Chaucheprat P, Santamarina A, Bioux P, Perrutel JP (1986) Mixed loading calculation scheme FOR Pu recycling in PWRs. Qualification of the Pu MINERVE experiment. In: International conference on reactor physics, Saratoga Springs, Sept 1986

    Google Scholar 

  • Darrouzet M (1969) Mesure du rapport capture sur fission du 239Pu dans l’assemblage critique thermique-rapide ERMINE. PhD thesis, Orsay, 1969

    Google Scholar 

  • Gruel A (2009) Interpretation of in-pile oscillation experiments in the minerve facility for the improvement of fission product cross sections. In: ANIMMA international conference on advancements in nuclear instrumentation, measurement methods and their applications, Marseille, 7–10 June 2009

    Google Scholar 

  • Hudelot JP, Chauvin JP, Thiollay N, Cathalau S, Fougeras P, Santamarina A, Toubon H (2000) The credit burn up program on the MINERVE facility. In: 2000 ANS annual meeting, San Diego, 4–8 June 2000

    Google Scholar 

  • Hudelot JP, Chabert C, Chauvin JP, Fougeras P, Perret G, Genin X, Leorier C, Moulinier JM (2001) The OSMOSE experimental program for the qualification of the integral cross sections of actinides. In: 2001 nuclear data, Tsukuba, 7–12 Oct 2001

    Google Scholar 

  • Hudelot JP, Chabert C, Chauvin JP, Fougeras P, Perret G, Genin X, Leorier C, Moulinier JM (2002) The OSMOSE experimental program for the qualification of the integral cross sections of actinides. J Nucl Sci Technol 2:1007–1080

    Google Scholar 

  • Hudelot JP, Klann R, Fougeras P, Genin X, Drin N, Donnet L (2004) OSMOSE: An experimental program for the qualification of integral cross sections of actinides. In: PHYSOR 2004, Chicago, 25–29 April 2004

    Google Scholar 

  • Hudelot JP, Döderlein C, Antony M, Girard JM, Laval V, Fougeras P, Willermoz G, Leconte P (2005) The VALMONT program: accurate experimental techniques to support the neutronics qualification of UMo/Al. In: 9th interna- tional topical meeting on research reactor fuel management (RRFM) RRFM 2005, Budapest, 10–13 April 2005

    Google Scholar 

  • Hudelot JP, Antony M, Testaniere S, Fougeras P (2006a) OCEAN: an ambitious experimental program for the qualification of integral capture cross sections of neutron absorbers. In: PHYSOR 2006 advances in nuclear analysis and simulation, Vancouver, 10–14 Sept 2006

    Google Scholar 

  • Hudelot JP, Klann R, Antony M, Testaniere S, Fougeras P, Jorion F, Drin N, Donnet L, Leorier C (2006b) The OSMOSE program for the qualification of integral cross sections of actinides: preliminary experimental results in a PWR-UOX spectrum. In: PHYSOR 2006 advances in nuclear analysis and simulation, Vancouver, 10–14 Sept 2006

    Google Scholar 

  • Laponche B (1970) Méthode de l’échantillon équivalent pour interpréter les expériences d’oscillations d’échantillons fissiles dans une pile à neutrons thermiques. PhD thesis, Orsay, 1970

    Google Scholar 

  • Martin-Deidier L (1979) Mesure intégrale de la capture des produits de fission dans les réacteurs à neutrons rapides. PhD thesis, Orsay, 1979 ORSAY University, Paris XI

    Google Scholar 

  • Mondot J (1990) Synthesis of experimental validation of global fission product capture for PWR’s and advanced reactor lattices. In: Topical meeting ANS Physor’90, Marseille, 23–27 April 1990

    Google Scholar 

  • Santamarina A (1978) Calcul des assemblages PWR. Qualification du système NEPTUNE par les expériences MELODIE dans MINERVE. In: Conférence sur les méthodes d’homogénéisation en Physique des Réacteurs, IAEA TECDOC-231, Lugano, Nov 1978

    Google Scholar 

  • Assal W, Bosq JC, Mellier F (2009) Experimental measurements at the MASURCA facility. In: ANIMMA, Marseille, 7–10 June 2009

    Google Scholar 

  • Barre JY, Boyer J, Mougniot JC, Sicard B (1972) Reactor physics and fast power breeders: MASURCA CORE RZ program. In: Meeting on new developments in reactor physics, Kiamesha Lake

    Google Scholar 

  • Bertrand P (1996) BERENICE – inter laboratory comparison of βeff measurement techniques at MASURCA. In: Proceedings of the international conference on PHYSOR’96, vol 2, pp E190–E199, Mito, Sept 1996

    Google Scholar 

  • Bouget YH, Cosimi M, Hammer P, Humbert G, Lyon F, Martini M (1979) Physics performances of a heterogeneous fast reactor core concept in MASURCA. Nucl Technol 44:61–75

    Google Scholar 

  • Destouches C, Fruneau M, Belmont JL, Do Pinhal J, Albrand S, Carreta JM, Chaussonnet P, De Conto JM, Fontenille A, Fougeras P, Garrigue A, Guisset M, Laurens JM, Loiseaux JM, Marchand D, Micoud R, Mellier F, Perbet E, Planet M, Ravel JC, Richaud JP (2006) The GENEPI accelerator operation feedback at the MASURCA reactor facility. Nucl Instrum Meth Phys Res A 562:601–609

    Article  Google Scholar 

  • D’orval CC, Engelmann P, Helm F, Jourdan G, Meyer-Heine A, Pilate S, Schmidt AP, Tretiakoff O, Vidal R, Wittek G (1970) Joint experiments on MASURCA, ERMINE and SNEAK in support of fast breeder projects Phenix and SNR. Trans Am Nucl Soc 13:292–293

    Google Scholar 

  • Finck PJ, Cabrillat JC, Martini M, Soule R, Rimpault G, Jacqmin R (1996) The CIRANO experimental programme in support of advanced fast reactor physics. In: Proceedings of the international conference on the physics of reactors PHYSOR’96, Mito, 16–20 Sept 1996

    Google Scholar 

  • Giese H, Caravec C, Granget G, Palmiotti G (1986) The RACINE-1E critical experiments for control rod method and data calculation. Experimental and calculation results. In: Proceedings of the topical management advances in reactor physics and safety, Saratoga Springs, 17–19 Sept 1986

    Google Scholar 

  • Humbert G, Kappler F, Martini M, Norvez G, Rimpault G, Ruelle B, Scholtyssek W, Stanculescu A (1984) Parametric studies on heterogeneous cores for fast breeder reactors: the pre-racine and racine experimental programs. Nucl Sci Eng 87:233–251

    Google Scholar 

  • Improvements of the predicted characteristics for fast power reactor from integral experiments: Cadarache Version III multigroup cross section set. In: International fast reactor physics symposium, Tokyo, 16–19 Oct 1973

    Google Scholar 

  • Integral experiments performed at CEA to improve the Pu higher isotope nuclear data: “PLUTO programme”. In: Specialists meeting on the nuclear data of higher plutonium and americium isotopes for reactor applications, Brookhaven, 20–22 Nov 1978

    Google Scholar 

  • Lebrat JF, Aliberti G, D’Angelo A, Billebaud A, Brissot R, Brockmann H, Carta M, Destouches C, Gabrielli F, Gonzalez E, Hogenbirk A, Klein-Meulenkamp R, Le Brun C, Liatard E, Mellier F, Messaoudi N, Peluso V, Plaschy M, Thomas M, Villamarín D, Vollaire J (2008) Global results from deterministic and stochastic analysis of the MUSE-4 experiments on the neutronics of ADS. Nucl Sci Eng 158(1):49

    Google Scholar 

  • Lyon F, Martini M, Rimpault G (1979) Etude de l’effet vidange sodium dans des milieux représentatifs des centrales à neutrons rapides de type classique ou hétérogène – expériences faites au cours du programme Pré-Racine sur Masurca. In: Proceedings of the international conference on fast reactor physics, Aix, 24–28/09/1979, IAEA-SM-244/23, vol 2, IAEA

    Google Scholar 

  • MASURCA (1963) Maquette critique à neutrons rapides – description fonctionnelle et objectifs. In: Proceedings of the symposium on “Exponential and Critical Experiments” held by the IAEA in Amsterdam, Netherlands, vol I, pp 135–155, 2–6 Sept 1963

    Google Scholar 

  • Mellier F, Billebaud A, Brissot R, Destouches C, Fougeras P, Le Brun C, Liatard E, Jammes C (2006) Conclusions and perspectives after the achievement of the MUSE4 programme at the MASURCA facility. In: 9th IEM on actinide and fission product partitioning and transmutation, Nimes, 25–29 Sept 2006

    Google Scholar 

  • Perret G, Destouches C, Fougeras P, Soule R, Hudelot JP, Jammes C, Assal W, Chaussonnet P, Laurens JM, Bignan G (2002) Determination of reactivity by revised rod-drop technique in the MUSE-4 programme. In: Comparison with dynamic measurements. Actinide and fission product partitioning & transmutation, Jeju, 14–16 Oct 2002

    Google Scholar 

  • Rimpault G, Jacqmin R, Matini M, Soule R, Smith P, Ohki S (1998) The CIRANO experimental programme for the characterisation of highly enriched plutonium oxide fuel in fast reactors. In: Proceedings of the international conference on PHYSOR’98, Long Island

    Google Scholar 

  • Soule R, Salvatores M, Bignan G, Jammes C, Destouches C, Fougeras Ph, Lebrat JF, Billebaud A, Brissot R, Fruneau M, Giorni A, Le Brun C, Loiseaux JM, Merle E, Wachtarczyk Ph, Villamarin D, Plaschy M, Seltborg P, Imel G (2001) Experimental validation of the neutronic characteristics of the sub-critical multiplying medium of an ADS: the MUSE programme. In: AccApp’01 & ADTTA’01 nuclear applications in the new millennium, Reno, 11–15 Nov 2001

    Google Scholar 

  • Soule R, Salvatores M The Experimental Balzac Program at Masurca in Support of the design of Super Phenix 2. In: Proceedings of the topical meeting on reactor physics and safety, Saratoga Springs, 17–19 Sept 1986

    Google Scholar 

  • Vaglio-Gaudard C, Lebrat JF, Pénéliau Y, Ruggieri JM, Sublet JC, Tommasi J, Vidal JF, Lyoussi A (2010) Analysis of the gas benchmark in MASURCA facility for the calculation of the steel reflector in fast reactors. Nucl Sci Eng

    Google Scholar 

  • Villamarin D, Perret G, Gonzalez E, Soule R, Jammes C, Imel G, Destouches C, Chaussonnet P, Laurens JM, Thomas GM, Fougeras P, Bignan G (2002) First measurements of the kinetic response of the MUSE-4 fast ADS mock-up to fast neutron pulse. In: Actinide and fission product partitioning & transmutation, Jeju, 14–16 Oct 2002

    Google Scholar 

  • Amharrak H, Di-Salvo J, Thiollay N, Lyoussi A, Bosq J-C, Bignan G (2009) In core measurements using thermo-luminescent detectors (TLD). In: ANIMMA, Marseille, 7–10 June 2009

    Google Scholar 

  • Blaise P, Fougeras P, Cathalau S (2000) New developments in representativity approach to study advanced assembly concepts in the EOLE critical facility. In: 2000 ANS international meeting on advances in reactor physics and mathematics and computation into the next millennium PHYSOR2000, Pittsburg, 7–12 May 2000

    Google Scholar 

  • Blaise P, Cathalau S, Thiollay N, Fougeras P, Laval V, Philibert H, Girard JM, Hudelot JP (2004) Fission products particular peak measurement for UO2-Gd2O3-MOX γ-scanning renormalization in 100% MOX ABWR mock up cores. In: 12th international conference on nuclear engineering (ICONE 12), Arlington, 25–29 April 2004

    Google Scholar 

  • Blaise P, Serviere H, Roche A, Fougeras P, Blanchet D, Huot N (2005a) Recent advances in gamma heating measurement in full MOX cores by using TLD technique: the ADAPh program. In: GLOBAL 2005, Tsukuba, 9–13 Oct 2005

    Google Scholar 

  • Blaise P, Fougeras P, Cathalau S, Laval V, Philibert H, Girard JM, Yamamoto T (2005b) Experimental investigation of isothermal temperature coefficient in ALWR type UOX and full MOX cores. In: GLOBAL 2005, Tsukuba, 9–13 Oct 2005

    Google Scholar 

  • Blaise P, Mellier F, Fougeras P (2009) Application of the modified source multiplication (MSM) technique to subcritical worth measurements in thermal and fast reactors systems. In: ANIMMA international conference on advancements in nuclear instrumentation, measurement methods and their applications, Marseille, 7–10 June 2009

    Google Scholar 

  • Blanc de Lanaute N, Mellier F, Lyoussi A, Chaussonnet P, Bosq JC (2009) Reduction of uncertainties concerning fission chambers measurements through a better understanding of the calibration process and the dead time phenomenon. In: ANIMMA, Marseille, 7–10 June 2009

    Google Scholar 

  • Cabrillat J-C, Martini M (1990) Power and neutron flux distributions in the core and shielding. Nucl Sci Eng 106:37–46

    Google Scholar 

  • Chauvin JP, Cabrillat JC (1995) Validation of one axial γ scanning measurement bench for the determination of the axial fission rate directly on the core pin from the EOLE or MINERVE facilities. In: Annual meeting on nuclear technology 95, Meistersingerhalle Nurnberg, 16–18 May 1995

    Google Scholar 

  • Gauthier J-C, Cabrillat J-C, Palmiotti G, Salvatores M, Giese M, Carta M, West J-P (1990) Measurement and predictions of control rod worth. Nucl Sci Eng 106:18–29

    Google Scholar 

  • Geslot B, Jammes C, Nolibe G, Fougeras P (2005) Multimode acquisition system dedicated to experimental neutronic physics. In: IMTC 2005 – instrumentation and measurement technology conference, Ottawa, 17–19 May 2005

    Google Scholar 

  • Girard JM, Philibert H, Domergue Ch, Beretz D (2009) The MADERE radio-activity measurement Platform: developments for a better address of the experimental needs. In: IGORR12, Beijing, Oct 2009

    Google Scholar 

  • Hudelot J-P (1998) Developpement, Amelioration et calibration des mesures de taux de reaction neutroniques: elaboration d’une base de techniques standards. PhD thesis, June 1998

    Google Scholar 

  • Hudelot JP, Girard JM (2009) An innovating active neutronics interrogation and time-dependent method for calibrating fission chambers in the dedicated celina facility using a pulsed neutron generator. In: ANIMMA, Marseille, 7–10 June 2009

    Google Scholar 

  • Hudelot JP, Fougeras P, Cathalau S (2002) Measurement of the modified conversion ratio of 238U by gamma-ray spectrometry on irradiated fuel pin. In: 11th international symposium on capture γ-ray spectroscopy and related topics, Pruhonice, 2–6 Sept 2002

    Google Scholar 

  • Jammes C, Geslot B, Rosa R, Imel G, Fougeras P (2005) Comparison of reactivity estimations obtained from rod drop and pulsed neutron source experiments. Ann Nucl Energy 32:1131–1145

    Article  Google Scholar 

  • Jammes Ch, Filliatre P, Geslot B, Oriol L, Berhouet F, Villard J-F (2009) Research activities in fission chamber modeling in support of the nuclear energy industry ANIMMA, Marseille, 7–10 June 2009

    Google Scholar 

  • Leconte P (2006) Optimisation et développement de techniques de mesure par spectrométrie g sur combustible irradié. Maîtrise et réduction des incertitudes. PhD thesis, Oct 2006

    Google Scholar 

  • Leconte P, Hudelot JP, Antony M, Bernard D (2006a) An innovating gamma-spectroscopy experimental technique for measuring the integral capture cross section of actinides. In: PHYSOR 2006 advances in nuclear analysis and simulation, Vancouver, 10–14 Sept 2006

    Google Scholar 

  • Leconte P, Hudelot JP, Antony M (2006b) Integral capture rate measurements of neutron poisons and minor actinides by g-ray spectrometry on specific fuel samples. In: IYNC international youth nuclear congress, Stockholm, 18–23 June 2006

    Google Scholar 

  • Lüthi A, Chawla R, Rimpault G (2001) Improved gamma-heating calculational methods for fast reactors and their validation for plutonium-burning configurations. Nucl Sci Eng 138:233–255

    Google Scholar 

  • Pang H (1995) Development of stochastic and deterministic techniques for the determination of delayed neutron yields and β effective. PhD thesis, no. 3634, Orsay, 28 March 1995

    Google Scholar 

  • Perret G (2003) Amélioration et développement des méthodes de détermination de la réactivité –Maîtrise des incertitudes associées. PhD thesis, Orsay, 2003

    Google Scholar 

  • Plaschy M, Destouches C, Chawla R, Beretz D, Mellier F, Serviere H, Fougeras P, Chaussonnet P, Domergue C, Laurens JM, Philibert H (2005) Determination of adjusted neutron spectra in different MUSE configurations by unfolding techniques ISRD12, Gatlinburg, 8–13 May 2005

    Google Scholar 

Download references

Author information

Authors and Affiliations

  1. French Atomic Energy Commission, Reactor Studies Department, Cadarache Research Center, Saint Paul Lez Durance, France

    Gilles Bignan, Philippe Fougeras, Patrick Blaise, Jean-Pascal Hudelot & Frédéric Mellier

Authors
  1. Gilles Bignan
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Philippe Fougeras
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Patrick Blaise
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. Jean-Pascal Hudelot
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. Frédéric Mellier
    View author publications

    You can also search for this author in PubMed Google Scholar

Editor information

Editors and Affiliations

  1. Institute for Nuclear Technology and Reactor Safety, Karlsruher Institut fur Technologie (KIT), Gotthard-Franz-Str. 9, 76131, Karlsruhe, Germany

    Dan Gabriel Cacuci

Rights and permissions

Reprints and permissions

Copyright information

© 2010 Springer Science+Business Media, LLC

About this entry

Cite this entry

Bignan, G., Fougeras, P., Blaise, P., Hudelot, JP., Mellier, F. (2010). Reactor Physics Experiments on Zero Power Reactors. In: Cacuci, D.G. (eds) Handbook of Nuclear Engineering. Springer, Boston, MA. https://doi.org/10.1007/978-0-387-98149-9_18

Download citation

Publish with us

Policies and ethics

Search

Navigation