ARIES-RS safety design and analysis

[1]  E. Mogahed.  LOSS OF COOLANT ACCIDENT (LOCA) ANALYSIS OF THE ARIES-ST DESIGN , 1998 .

[2]  H. Wienke,et al.  FENDL/MG-2.0 and FENDL/MC-2.0 The Processed Cross-section Libraries for Neutron Photon Transport Calculations Version 1, March 1997 Summary Documentation , 1998 .

[3]  J.-Ch. Sublet,et al.  FENDL/A2.0 Neutron Activation Cross Section Data Library for Fusion Applications Released on March 14, 1997 , 1998 .

[4]  Laila A. El-Guebaly,et al.  Overview of ARIES-RS neutronics and radiation shielding: key issues and main conclusions , 1997 .

[5]  Massimo Zucchetti,et al.  Management Strategy to Reduce the Radioactive Waste Amount in Fusion , 1997 .

[6]  R. Klueh,et al.  Impurity content of reduced-activation ferritic steels and a vanadium alloy , 1997 .

[7]  D. Petti,et al.  Dose due to mobilization of vanadium alloy activation products , 1996 .

[8]  Kazuyuki Takase,et al.  Effects of Breach Area and Length to Exchange Flow Rates Under the Lova Condition in a Fusion Reactor , 1996 .

[9]  R. S. Baker,et al.  DANTSYS: A diffusion accelerated neutral particle transport code system , 1995 .

[10]  O. Schipakin,et al.  Experimental study of 210Po release from 17Li83Pb eutectic , 1995 .

[11]  Richard F. Mattas,et al.  Comparison of lithium and the eutectic lead lithium alloy, two candidate liquid metal breeder materials for self-cooled blankets , 1995 .

[12]  H. Attaya.  Summary report for ITER task - D4: Activation calculations for the lithium vanadium ITER design , 1995 .

[13]  R. L. Klueh,et al.  Proceedings of the IEA working group meeting on ferritic/martensitic steels , 1995 .

[14]  G. R. Smolik,et al.  A summary and assessment of oxidation driven volatility experiments at the INEL and their application to fusion reactor safety assessments , 1994 .

[15]  J. E. Sisolak,et al.  Calculational models for the treatment of pulsed/intermittent activation within fusion energy devices , 1993 .

[16]  Michael L. Corradini,et al.  Lithium alloy chemical reactivity with reactor materials: current state of knowledge , 1991 .

[17]  Steve Fetter,et al.  Long-term radioactive waste from fusion reactors: Part II , 1990 .

[18]  Dai-Kai Sze,et al.  Blanket Comparison and Selection Study , 1985 .

[19]  W. Meier,et al.  Polonium aspects associated with the use of lead-lithium blankets in fusion applications , 1985 .

[20]  Raymond E. Alcouffe,et al.  Revised user's manual for ONEDANT: A code package for One-Dimensional, Diffusion-Accelerated, Neutral-Particle Transport , 1982 .

[21]  Gardner,et al.  ACTL: evaluated neutron activation cross section library-evaluation techniques and reaction index. [Tables, 10/sup -10/ to 20 MeV] , 1978 .

[22]  Farrington Daniels,et al.  The Argonne National Laboratory , 1948 .

[23]  G. Kuhlbörsch,et al.  Physical properties and chemical reaction behaviour of Li17Pb83 related to its use as a fusion reactor blanket material , 1984 .

[24]  John Crank,et al.  The Mathematics Of Diffusion , 1956 .