Prediction of neutron source, tritium production and activation for long- pulse operation of the ITER Neutral Beam Test Facility
نویسندگان
چکیده
A Local Mixing Model (LMM) has been utilised to compute the evolution of the hydrogen isotope content within the implantation zone of the CuCrZr target material of the beam-stopping elements of the ITER Neutral Beam Test Facility, together with the beamtarget fusion reaction rate calculated by taking account of the slowing-down of the 1MeV incoming projectile ion within the implantation layer. An important modification of the LMM code is to treat the tritium reaction product ions, resulting from D-D reactions, as a constituent of the incident beam. Although the treatment of tritium in the LMM is not ideal, this and other simplifying assumptions either do not significantly affect the predictions, or ensure conservatism in the results when used as input to the safety analysis of the facility. For example, it is shown that T→D “beam-target” reactions always dominate over those of D→T, which overcomes the problem of uncertainty, in the model, of the distribution of tritium trapped within the implantation layer; in contrast there is little uncertainty that this region will rapidly approach deuterium saturation for long-pulse (≤ 1hr) operation. Using the computed sources as input, neutronics and activation calculations for the NBTF components have been carried out using the MCNP/FISPACT. As expected, long-pulse operational requirements lead to neutron activation and tritium production levels which have non-negligible but manageable radiological consequences. This work was conducted under the European Fusion Development Agreement and funded by Euratom and the UK Engineering and Physical Science Research Council. 1 H-D Falter et al, Proc. 17 Symposium on Fusion Technology, Rome (1992) p 481
منابع مشابه
Radiation safety at the PRIMA facility: a review of shielding solutions and personnel dose assessment
The Neutral Beam Test Facility (NBTF), also called PRIMA (acronym for Padova Research on ITER Megavolt Accelerator) consists of two separate development test beds currently under construction in Padua (Italy): the ion source test facility, named SPIDER (Source for Production of Ion of Deuterium Extracted from Rf plasma) and the megavolt test facility, called MITICA (acronym for Megavolt ITER In...
متن کاملPhysical Performance Analysis And The Progress Of The Development Of The Negative Ion RF Source For The ITER NBI System
For heating and current drive the neutral beam injection system for ITER requires a 1 MeV deuterium beam for up to 1 h pulse length. In order to inject the required 17 MW the large area source (1.9m x 0.9m) has to deliver 40 A of negative ion current at the specified source pressure of 0.3 Pa. In 2007 the IPP RF driven negative hydrogen ion source was chosen as the new reference source for the ...
متن کاملPreliminary Design Concepts for the Control and Data Acquisition Systems of the Iter Neutral Beam Injector and Associated Test Facility
ITER is a joint international research and development project aiming to demonstrate the scientific and technical feasibility of fusion power. The ITER Neutral Beam Injector (negative H or D ion source, 1MV acceleration voltage, 40A ion current, 16.5MW beam power, 1 hour continuous operation) is a major and innovative component of ITER and will be supported by a dedicated Test Facility. The neu...
متن کاملOverview of diagnostics on ITER neutral beam test facility
ITER operation relies on heating neutral beam injectors (HNB) based on negative ion deuterium beams accelerated at 1 MeV, with up to one hour 17 MW power, uniform intensity and low divergence. A neutral beam test facility is being built at Consorzio RFX to demonstrate the feasibility of a prototype injector with such demanding specifications and to optimize its performances. It comprises SPIDER...
متن کاملShielding studies on a total-body neutron activation facility
Background: Prompt gamma neutron activation analysis (PGNAA) is known as a non-invasive technique capable of measuring elemental concentration in voluminous samples in a short period of time. Also it is a valuable diagnostic tool for total body elemental measurements. 252Cf and 241Am-Be sources which are usually used in this method, generate not only neutrons, but also emit high-energy and unwa...
متن کامل