I-1 J. C. Kuijper, E. Bomboni, N. Cerullo, G. Lomonaco, G. Mazzini et alii – “PU AND MA MANAGEMENT IN THERMAL HTGRS - IMPACT AT FUEL, REACTOR AND FUEL CYCLE LEVELS”, HTR 2008 – 28

(1)

References

I-1 J. C. Kuijper, E. Bomboni, N. Cerullo, G. Lomonaco, G. Mazzini et alii – “PU AND MA MANAGEMENT IN THERMAL HTGRS - IMPACT AT FUEL, REACTOR AND FUEL CYCLE LEVELS”, HTR 2008 – 28th_{September -1}st

October, 2008, Washington, DC USA

I-2 http://www2.ing.unipi.it/~d0728/GCIR/Igcr.htm

I-3 G. Lomonaco – “I recenti sviluppi dei reattori a gas ad alta temperatura. La collocazione di questi impianti nel futuro piano energetico mondiale. Il programma europeo HTR-N e l'attività di ricerca del DIMNP svolta nel suo ambito” Master Thesis in Nuclear Engineering, Tutors: Prof. N. Cerullo, Prof. G. Forasassi, Prof. B. Montagnini – A. A. 2002/2003

http://www.tesionline.it/default/tesi.asp?idt=10251

I-4 E. Bomboni – “Le scorie nucleari: Analisi della loro possibile riduzione mediante cicli del combustibile innovativi” Master Thesis in Nuclear Engineering, Tutors: Prof. N. Cerullo, Prof. G. Forasassi, Ing. G. Lomonaco, Ing. V. Romanello – A. A. 2005/2006

http://etd.adm.unipi.it/theses/available/etd-06122006-143839/ I-5 http://www.puma-project.eu 1-1 1-2 1-3 1-4 1-5

J.C. Kuijper (NRG), J. Cetnar (AGH), J.B.M. de Haas (NRG), F. Venneri (GA), J. Zakova (KTH) – 20071123_PUMA_D121_final – Selected Reference HTGR Designs and Fuel Cycle Data – September 2007.

OECD-NEA_PBMR-400_Transient_benchmark_description – PBMR COUPLED NEUTRONICS/THERMAL HYDRAULICS TRANSIENT BENCHMARK THE PBMR-400 CORE DESIGN - September 2005

J. Cleveland – Loss of Coolant: ORNL’s Role in a Key Reactor Safety Experiment – Oak Ridge National Laboratory Review 21 n. 4, 79÷87 – 1988

K. Kruger et al. – Preparation, Conduct and Experimental Results of the AVR LOCA Simulation Test – “Nuclear Science and Engineering” – February 1991

http://www.pbmr.com/index.asp?Content=129

1-6

1-7 D.Serbanescu – Personal Communications – May 2008/June 2008 V. Romanello – “Analisi di alcune peculiari potenzialità degli HTR: la produzione dell’idrogeno e il bruciamento degli attinidi” Master Thesis in Nuclear Engineering, Tutors: Prof. N. Cerullo, Prof. G. Forasassi, Prof. B. Montagnini, Ing. G. Lomonaco – A. A. 2003/2004

http://etd.adm.unipi.it/theses/available/etd-10152003-181233/

1-8 G. Lomonaco – “Problematiche di sicurezza nella produzione di idrogeno mediante impianti HTR” Bachelor Thesis in Industrial Safety and Nuclear Engineering, Tutors: Prof. M. N. Carcassi, Prof. N. Cerullo – A. A. 2003/2004 http://www.tesionline.it/default/tesi.asp?idt=10251

(2)

1-9 E. Bomboni, N. Cerullo, G. Lomonaco, and V. Romanello – “A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors” –

Science and Technology of Nuclear

Installations

, vol. 2008, Article ID 265430, 18 pages, 2008

doi:10.1155/2008/265430 2-1 http://world-nuclear.org

2-2 E. E. Bende –

Plutonium Burning in a Pebble-Bed Type High Temperature

Nuclear Reactor

– PhD thesis Delft University of Technology ISBN

90-9013168 NUGI: 837, supervisor Dr. Ir. J.L. Kloosterman, 1999

2-3 W. F. G. Van Rooijen –

Improving Fuel Cycle Design and Safety

Characteristics of a Gas Cooled Fast Reactor

– PhD thesis Delft University

of Technology ISBN 1-58603-696-3, supervisor Dr. Ir. J. L. Kloosterman, 2006

2-4 IAEA –

Implications of Partitioning and Transmutation in Radioactive

Waste Management

– Technical Report Series No. 435, IAEA, Vienna,

2004

2-5 U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum –

A Technology Roadmap for

Generation IV Nuclear Energy Systems

– December 2002

2-6 OECD/IAEA –

Uranium 2005: Resources, Production and Demand

– 2006

2-7 http://www.cea.fr

2-8 H. W. Wiese –

Actinide transmutation properties of thermal and fast

neutron reactors include multiple recycling

– Journal of Alloys and

Compounds 271-273 (1998) 522-529, Elsevier

2-9 N. Cerullo –

Lezioni di Ingegneria del Nocciolo

–DIMNP, Pisa, 1988

2-10 T. D. Newton and P. J. Smith –

A moderated target sub-assembly design

for minor actinide transmutation

– Proceedings of GLOBAL’03, New

Orleans, Louisiana, 16÷20 November 2003

2-11 D. C. Wade –

Safety considerations in design of fast spectrum ADS for

transuranic or minor actinide burning: a status report on activities of

the OECD/NEA expert group

– OECD/IAEA,

Actinide and fission product

partitioning and transmutation

– 6th_{Information Exchange Meeting –}

Madrid, Spain, 11-13 December 2000

2-12 J. F. Briesmeister (ed.) –

MCNP – A General Monte Carlo Code N-Particle

Transport Code

– LANL report LA-12625-M, version 4B, March 1997

r

2-13 O.R.N.L. –

ORIGEN 2.1 Isotope Generation and Depletion Code Matrix

Exponential Method

– Tennessee, USA, August 1996

2-14 D. I. Poston, H. R. Trellue –

Use 's Manual, Version 2.0 for

MONTEBURNS Version 1.0

– LA-UR-99-4999 PSR-0455/01, September

1999

(3)

2-16 J. Cetnar, W. Gudowski, J. Wallenius –

User Manual for Monte-Carlo

Continuous Energy Burnup (MCB) Code - Version 1C

–

http://www.nea.fr/abs/html/nea-1643.html

2-17 J. Cetnar –

A Method of Transmutation Trajectories Analysis in

Accelerator Driven System

– Proc. IAEA Technical Committee Meeting

on Feasibility and Motivation for Hybrid Concepts for Nuclear Energy Generation and Transmutation, Madrid, 17÷19 September 1997

2-18 ANSWER Software Service –

WIMS-D/5: A Neutronic Code for Standard

Lattice Physics Analysis

– A.E.A. Winfrith – 1995

2-19 T. Iwasaki, N. Hirakawa –

Fast and perfect transmutation of actinide

wastes using A Burner

–Proceedings of GLOBAL’93, Seattle,

Washington, 1993

-2-20 J. M. Adnet, M. Miguirditchian, C. Hill, X. Heres, M. Lecomte, M. Masson, P. Brossard, P. Baron –

Development of New Hydrometallurgical

Processes for Actinide Recovery: GANEX concept

– Proceedings of

GLOBAL 2005, Tsukuba, Japan, 9÷13 October 2005

2-21 OECD/NEA –

Actinide separation chemistry in nuclear waste streams

and materials

– December 1997

2-22 http://www.nea.fr

2-23 E. Bomboni, N. Cerullo, G. Lomonaco, V. Romanello –

Nuclea was e

impact reduction using multiple fuel recycling s rategies

– Proceedings

of PHYTRA-1, Marrakech, Morocco, 14-16 March 2007

r

t

2-24 L.A.N.L. –

MCNPX, VERSION 2.6C

– November 20, 2006 2-25 http://atom.kaeri.re.kr – MCNP Libraries from ENDF/B-6.x

2-26 N. Cerullo, G. Lomonaco, V. Romanello –

Waste Radiotoxicity

Minimization Using Innovative LWR-HTR-GCFR Symbiotic Fuel Cycles

–

Proceedings of ARWIF2005, ORNL (USA), February 2005

2-27 T. A. Taiwo et alii –

Particle-Bed Gas-Cooled Fast Reactor (PB-GCFR)

Design

– Project Final Technical Report, NERI, USA, 24 September 2003

2-28 A. Conti, J. C. Bosq –

600 MW

th

GFR cores containing plates CERCER –

Characteristics

–CEA-Cadarache, France, December 2004

2-29 V. Romanello, G. Lomonaco, N. Cerullo –

CARL 2.2 Code’s user manual

– http://www.nea.fr/abs/html/nea-1735.html

2-30 N. Cerullo, D. Bufalino, G. Forasassi, G. Lomonaco, P. Rocchi, V. Romanello –

The capabilities of HTRs to burn actinides and to optimize

plutonium exploitation.

– Proceedings of ICONE12, April 2004,

Arlington, Virginia, USA.

2-31 J. Kuijper, N. Cerullo, G. Lomonaco, et alii –

“HTGR Reactor Physics and

Fuel Cycle Studies“

– Nuclear Engineering and Design, n. 236, pagg.

615÷634, Marzo 2006

2-32 N. Cerullo, D. Bufalino, G. Forasassi, G. Lomonaco, P. Rocchi, V. Romanello –

“An additional performance of HTRs: the waste

(4)

radiotoxicity minimization”

– Radiaction Protection Dosimetry, volume 115, Oxford Press, December 2005

2-33 http://www.gcfr.org

2-34 S. Massara, P. Tetart, L. Boucher –

A French Scenario for Fast Reactors

Deployment over the XXI

st

_Century

_{– Proceedings of ARWIF2005, ORNL}

(USA), February 2005

2-35 N. M. Greene, L. M. Petrie –

XSDRNPM: a on-dimensional

discrete-ordinates code for transport analysis –

ORNL (USA), March 2000

2-36 http://www.raphael-project.org/index.html

3-1 N. Hfaiedh and A. Santamarina - PROPOSAL FOR AN EUROPEAN OPTIMIZED MULTIGROUP MESH: SHEM-281G – CEA-Cadarache DEN/DER/SPRC – 28-30 November 2005. [JEFDOC-1102]

3-2 N. Hfaiedh – “Nouvelle Méthodologie de Calcul de l’Absorption Résonnante“ Ph.D. thesis – September 2006

3-3 B. Montagnini – APPUNTI DI FISICA DEL REATTORI A FISSIONE – University of Pisa – DIMNP

3-4 http://www.nndc.bnl.gov/

4-1 J. Oppe, J.C. Kuijper, J.B.M. de Haas, E.C. Verkerk, H.T. Klippel – MODELING OF CONTINUOUS RELOAD HTR SYSTEMS BY THE PANTHERMIX CODE SYSTEM – September 2001

4-2 J. Oppe – PANTHERMIX99 reference manual – FEBRARY 2001 4-3 J.C.Kuiper – Personal Comunication – Febrary 2008/August 2008ù

4-4 X-5 Monte Carlo Team – MCNP — A General Monte Carlo N-Particle Transport Code, Version 5 – October 2005

4-5 WIMS8 – WIMS, a Modular Scheme for Neutronics Calculations, User Guide for Version 8, ANSWERS/WIMS (99) – 1999

5-1 J. C. Kuiper – Personal Communication – February 2008/August 2008 5-2 J. C. Kuiper – Personal Communication – CURIE Code model for HFR

(NRG Petten) – May 2008/August 2008

5-3 J. J. Duderstadt, L. J. Hamilton – Nuclear Reactor Analysis – Wiley New York – 1976

5-4 W. Van Lensa – High-Temperature Reactors – Technological Developments & Potential Market – ICAPP 2007, Nice, France – 16th_May

2007

A-1 M. Bredin – PBMR ACCIDENT ANALYSIS – F00000083 – HTR 2006.

A-2 S. Ball – SENSITIVITY STUDIES OF MODULAR HIGH-TEMPERATURE GAS-COOLED REACTOR (MHTGR) POSTULATED ACCIDENTS – Paper F06 – HTR 2004.

A-3 W. Schmitz, A. Koster – AIR INGRESS SIMULATIONS USING CFD – F00000203 – HTR 2006.

A-4 S. Ball, S.J. and D. J. Nypaver –

GRSAC Users Manual

, ORNL/TM-13697 – February 1999.

(5)

A-5 Heat Transport and Afterheat Removal for Gas Cooled Reactors Under Accident Conditions – IAEA-TECDOC-1163, January 2001.

B-1 S. Loubiere, R. Sanchez, M. Coste, A. Hébert, Z. Stankovski, C.

Vandergucht, I. Zmijarevic – “APOLLO2 Twelve Years Later,”

Proc. Int.

Conf. on Mathematics and Computation M&C99

– Madrid,

September,1999

B-2 A. Santamarina, C. Chabert, A. Courcelle, O. Litaize, G. Willermoz, D. Biron, L. Daudin – “Qualification of the APOLLO2.5/CEA93.V6 Code for UOX and MOX Fuelled PWRS,”

Proc. of the Int. Conf. On Reactor Physics

PHYSOR2002

, Seoul (Korea) – 7th_–10th_{October, 2002}

B-3 A. Santamarina, C. Collignon, A. Garat – “French Calculation Schemes for Light Water Reactor Analysis,”

Proc. of the Int. Conf. PHYSOR2004-The

Physics of Fuel Cycles and Advanced Nuclear Systems

– Chicago (USA),