for supporting this work, along with sincere acknowledgment to Idaho National Engineering and Environmental Laboratory, Fusion Safety Program for their support.Great appreciation and recognition goes to Mr. John Phillip Sharpe, the PhD graduate student who worked on the project, carefully did all of the experimentation and data analysis, and worked hard on editing the three main ITER EDF files attached to this report.Indeed, a great deal of appreciation goes to graduate and undergraduate students in the department of nuclear engineering who helped on the experiment during the course of this research, namely, Mr. Huu Ngo who helped in preparation of collection substrates and pre and post shot weight balance, Mr. K.S. Murali
III.2 Stainless Steel Test Results
III.3 Tungsten Test Results
III.4 Aluminum Test Results
IV. Experiments on Carbon materials and Mixed CarbodMetals
IV. 1 Carbon Test Results
IV. 1 .A Lxan Polycarbonate Test Results
IV. 1 .B Graphite Carbon Test Results
IV.2 CarbodCopper Mixture Test Results
IV.3 carbofltainless Steel Mixture Test Results
IV.4 Carboflungsten Mixture Test
ABSTRACTSafety considerations in large future fusion reactors like ITER are important before licensing the reactor. Several scenarios are considered hazardous, which include safety of plasma-facing components during hard disruptions, high heat fluxes and thermal stresses during normal operation, accidental energy release, and aerosol formation and transport. Disruption events, in large tokamaks like ITER, are expected to produce local heat flwres on plasma-facing components, which may exceed 100 GW/m2 over a period of about 0.1 ms. As a result, the surface temperature dramatically increases, which results in surface melting and vaporization, and produces thermal stresses and surface erosion. Plasma-facing components safety issues extends to cover a wide range of possible scenarios, including disruption severity and the impact of plasma-facing components on disruption parameters, accidental energy release and shortflong term LOCA's, and formation of airborne particles by convective current transport during a LOVA (watedair ingress disruption) accident scenario. Study, and evaluation of, disruption-induced aerosol generation and mobilization is essential to characterize database on particulate formation and distribution for large future fusion tokamak reactor like ITER. In order to provide database relevant to ITER, the SIRENS electrothermal plasma facility at NCSU has been modified to closely simulate heat fluxes expected in ITER This report is composed of three parts, each is an ITER EDA file, namely, EDF No. ITER/Us/97/TE/sA-14, June 1997, which describes scoping the SIRENS facility for generating wall material vapors; EDF No. ITER/zJS/97/TE/sA-21, November 1997, which details the results obtained on characterization of ITER disruption-induced particulate for metals; and EDF No. ITER/US/98/TE/SA-11, June 1998, which details the results for carbon-based materials and mixed materials.The SIRENS high heat flux facility at N...