Journal of Fusion Energy

article

Cooling System Design Options for a Fusion Reactor

Antonio Natalizio, Jan Collén, Gottfried Vieider

Journal of Fusion Energy > 1997 > 16 > 1-2 > 149-153

The objective of a fusion power reactor is to produce electricity safely and reliably. Accordingly, the design, objective of the heat transport system is to optimize power production, safety, and reliability. Such an optimization process, however, is constrained by many factors, including, among others: public safety, worker safety, steam cycle efficiency, reliability, and cost. As these factors impose...

article

Fusion Specific Features in ITER Accident Analysis

H.-W. Bartels, C. W. Gordon, S. J. Piet, A. E. Poucet, more

Journal of Fusion Energy > 1997 > 16 > 1-2 > 3-10

Fusion specific features like inherent plasma shutdown, low decay heat densities, cryogenic temperatures, and limited source terms were considered during the safety design process of ITER. Uncertainties in plasma disruptions motivates a robust design to cope with multiple failures of in-vessel cooling piping. A vacuum vessel pressure suppression system mitigates pressure transients and effectively...

article

Overview of the Preliminary Safety Analysis of the National Ignition Facility

S. Brereton, L. McLouth, B. Odell, M. Singh, more

Journal of Fusion Energy > 1997 > 16 > 1-2 > 85-94

The National Ignition Facility (NIF) is a proposed U.S. Department of Energy inertial confinement laser fusion facility. The candidate sites for locating the NIF are: Los Alamos National Laboratory, Sandia National Laboratory, New Mexico, the Nevada Test Site, and Lawrence Livermore National Laboratory (LLNL), the preferred site. The NIF will operate by focusing 192 individual laser beams onto a tiny...

article

Safety Analysis Results for Cryostat Ingress Accidents in ITER

B. J. Merrill, L. C. Cadwallader, D. A. Petti

Journal of Fusion Energy > 1997 > 16 > 1-2 > 119-124

Accidents involving the ingress of air, helium, or water into the cryostat of the International Thermonuclear Experimental Reactor (ITER) tokamak design have been analyzed with a modified version of the MELCOR code for the ITER Non-site Specific Safety Report (NSSR-1). The air ingress accident is the result of a postulated breach of the cryostat boundary into an adjoining room. MELCOR results for...

article

Source Term and Mobilization Assessment in NSSR-1 of ITER

S. J. Piet, L. Di Pace, G. Federici, D. F. Holland, more

Journal of Fusion Energy > 1997 > 16 > 1-2 > 11-17

We describe the radioactive sources in the International Thermonuclear Experimental Reactor (ITER). The most important sources are co-deposited tritium, tritiated water, tokamak dust, and corrosion products. The co-deposited tritium is limited to 1 kg-T; the total on-site tritium inventory in the Basic Performance Phase (BPP) is 4 kg-T. Tritiated water concentrations are kept below 0.2 g-T/m³ in the...

article

Magnet Safety Assessment for ITER

N. Mitchell, A. Alekseev, R. Gallix, D. Holland, more

Journal of Fusion Energy > 1997 > 16 > 1-2 > 25-35

The ITER magnet system consists of structurally linked sets of toroidal (TF) and poloidal (PF) field coils, central solenoid (CS), and various support structures. The coils are superconducting, force flow Helium cooled with a Kapton-Glass-Epoxy multilayer insulation system. The stored magnetic energy is about 100GJ in the TF system and 20GJ in the PF-CS. Coils and structure are maintained at 4 K by...

article

An Overview of INEL Fusion Safety R&D Facilities

K. A. McCarthy, G. R. Smolik, R. A. Anderl, W. J. Carmack, more

Journal of Fusion Energy > 1997 > 16 > 1-2 > 113-118

The Fusion Safety Program at the Idaho National Engineering Laboratory has the lead for fusion safety work in the United States. Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses. We now have four major experimental facilities that provide data for use in safety assessments. The Steam-Reactivity Measurement System measures hydrogen...

article

Fusion Safety Research and Development in JAERI

Tomoaki Kunugi, Yasushi Seki

Journal of Fusion Energy > 1997 > 16 > 1-2 > 181-187

This paper describes the current status and future plans of the fusion safety research and development regarding to the developments of the dust removal system and safety analysis code and the thermofluid experiments in the Japan Atomic Energy Research Institute (JAERI) for a fusion experimental reactor. The containment of the radioactive material is the key to achieve fusion safety. In the event...

article

ORE Assessment Due to ACP in the PHTS of the Point Design Phase of the ITER Project

S. Sandri, L. Di Pace

Journal of Fusion Energy > 1997 > 16 > 1-2 > 67-73

The work presented here dealt with the revision and the updating of the ORE (Occupational Radiation Exposure) assessment for the ITER PHTS (Primary Heat Transfer System). The data used come from the Point Design Documents and refers to the ITER design of the first half of 1996. The MCNP computer code was adopted to perform the shielding calculation. In addition, an accurate approach to evaluate the...

article

Exchange Flow Characteristics in a Tokamak Vacuum Vessel of Fusion Reactor Under the Loss-of-Vacuum Conditions

Kazuyuki Takase, Tomoaki Kunugi, Yasushi Seki

Journal of Fusion Energy > 1997 > 16 > 1-2 > 189-194

When a Tokamak vacuum vessel of fusion reactor is broken, buoyancy-driven exchange flows will take place through breaches after the inside pressure of the vacuum vessel (VV) becomes equal to the outside pressure. The exchange flow may bring a mixture of activated dusts and tritium from the inside of the VV to the outside through the breaches. Moreover, the exchange flow may remove decay heat from...

article

Fusion Reactors: Radiation Hazards and Risk

Antonio Natalizio, Ron Matsugu, Tony Tidbury

Journal of Fusion Energy > 1997 > 16 > 1-2 > 155-160

The safety advantage of next-step fusion machines, such as ITER, and of future fusion power reactors, comes not so much from the engineered safety features incorporated into the design, as it does from the inherent, or intrinsic, features of the machine/reactor. The key intrinsic feature is the small quantity of radioactive fuel (tritium) and its low health hazard. The radioactive health hazard is...

article

Decay Heat Removal by Natural Circulation of Vacuum Vessel Coolant for ITER

M. Iseli, H.-W. Bartels, A. Poucet

Journal of Fusion Energy > 1997 > 16 > 1-2 > 37-44

The decay heat-driven temperature transients of the in-vessel components following a postulated loss of all in-vessel cooling have been calculated. The resulting time-dependent heat load to the vacuum vessel is due to radiation from the backplate and convection of postulated steam between backplate and vacuum vessel. It is shown, that even for a failure of all in-vessel cooling and total loss of power,...

article

Analysis of the SEAFP Reactor Fuel Cycle

L. Di Pace, C. Rizzello, A. Natalizio, K. Kalyanam, more

Journal of Fusion Energy > 1997 > 16 > 1-2 > 55-65

The safety aspects of a fusion reactor fuel cycle, which handles substantial quantities of tritium, have been assessed in the framework of the European Programme on Safety and Environmental Assessment of Fusion Power Long Term (SEAL). This study focused on the assessment of the tritium inventory that could be released from interlinked systems in accidental scenarios. A systematic review of the fuel...

article

Development of Safety Assessment Method for Plasma Anomaly Events in Fusion Reactors

T. Honda, H.-W. Bartels, N. A. Uckan, Y. Seki, more

Journal of Fusion Energy > 1997 > 16 > 1-2 > 175-179

The objective of the study is to provide a safety assessment method for plasma transients including thermal response of in-vessel components. We developed a plasma physics model for safety analysis which has been implemented in a safety analysis code (SAFALY). The SAFALY code consists of a 0-D plasma dynamics model and a 1-D thermal behavior model of in-vessel components in the thickness direction...

article

Overview of Safety and Environmental Issues for Inertial Fusion Energy

S. J. Piet, S. J. Brereton, J. M. Perlado, Y. Seki, more

Journal of Fusion Energy > 1997 > 16 > 1-2 > 133-140

This paper summarizes safety and environmental issues of Inertial Fusion Energy (IFE): inventories, effluents, maintenance, accident safety, waste management, and recycling. The fusion confinement approach among inertial and magnetic options affects how the fusion reaction is maintained and which materials surround the reaction chamber. The target fill technology has a major impact on the target factory...

article

Safety Analysis of ITER EDA Design by GEMSAFE

Mitsuhiro Arika, Masaki Saito, Tetsuo Sawada, Yoichi Fujii-e

Journal of Fusion Energy > 1997 > 16 > 1-2 > 195-203

General Methodology of Safety Analysis and Evaluation for Fusion Systems (GEMSAFE) was applied to the International Thermonuclear Experimental Reactor (ITER) design in the stage of Engineering Design Activities (EDA) to identify Design Basis Events (DBEs) and the related safety features, which were compared with those of the ITER design in the stage of Conceptual Design Activities (CDA). As a result,...

article

Multiple Failure Accident Sequences for SEAFP Reactor

R. Caporali, T. Pinna

Journal of Fusion Energy > 1997 > 16 > 1-2 > 45-53

This paper summarizes several investigations on the identification of possible multiple failure accidents relevant in terms of consequences for the SEAFP reactor. Particularly, on those sequences of events that could induce a risk of radioactive materials bypass through the SEAFP confinement barriers. The analyses here reported are related to the Heat Transfer Systems of both reactor models 1 and...

article

Management Strategy to Reduce the Radioactive Waste Amount in Fusion

Paolo Rocco, Massimo Zucchetti

Journal of Fusion Energy > 1997 > 16 > 1-2 > 141-148

A waste management strategy for fusion activated materials aimed at reducing the amount of permanent nuclear waste is described. Three options are investigated: (1) clearance (declassification to nonactive waste). (2) recycling, (3) disposal as radioactive waste. Conditions allowing recycling are based on surface dose rates, those allowing clearance depend on the residual radioactivity, both after...

article

Radiation Safety Considerations for LHD Experiments

T. Uda, H. Yamanishi, H. Miyake, J. Kodaira, more

Journal of Fusion Energy > 1997 > 16 > 1-2 > 167-173

For experiments with the Large Helical Device (LHD) which is now under construction at the Toki site in Japan, radiation safety issues were discussed. In the course of plasma experiments, radiations such as X-rays, induced γ-rays, and neutrons increase. From a safety point of view, these radiation exposures to the environment should be controlled to limit the annual dose to less than 50 μSv at the...

article

Steam-Chemical Reactivity Studies for Irradiated Beryllium

R. A. Anderl, R. J. Pawelko, M. A. Oates, G. R. Smolik, more

Journal of Fusion Energy > 1997 > 16 > 1-2 > 101-108

This paper reports the results of an experimental study to determine the influence of neutron irradiation effects on the chemical reactivity of beryllium exposed to steam. The study entailed measurements of the following: (1) swelling of irradiated Be specimens annealed at temperatures ranging from 450°C to 1200°C, (2) hydrogen generation rates for unirradiated Be control specimens exposed to steam...

INFONA - science communication portal

Journal of Fusion Energy

Cooling System Design Options for a Fusion Reactor

Fusion Specific Features in ITER Accident Analysis

Overview of the Preliminary Safety Analysis of the National Ignition Facility

Safety Analysis Results for Cryostat Ingress Accidents in ITER

Source Term and Mobilization Assessment in NSSR-1 of ITER

Magnet Safety Assessment for ITER

An Overview of INEL Fusion Safety R&D Facilities

Fusion Safety Research and Development in JAERI

ORE Assessment Due to ACP in the PHTS of the Point Design Phase of the ITER Project

Exchange Flow Characteristics in a Tokamak Vacuum Vessel of Fusion Reactor Under the Loss-of-Vacuum Conditions

Fusion Reactors: Radiation Hazards and Risk

Decay Heat Removal by Natural Circulation of Vacuum Vessel Coolant for ITER

Analysis of the SEAFP Reactor Fuel Cycle

Development of Safety Assessment Method for Plasma Anomaly Events in Fusion Reactors

Overview of Safety and Environmental Issues for Inertial Fusion Energy

Safety Analysis of ITER EDA Design by GEMSAFE

Multiple Failure Accident Sequences for SEAFP Reactor

Management Strategy to Reduce the Radioactive Waste Amount in Fusion

Radiation Safety Considerations for LHD Experiments

Steam-Chemical Reactivity Studies for Irradiated Beryllium

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