title: Gamma dose from activation of internal shields in IRIS reactor.
abstract: The International Reactor Innovative and Secure is a modular pressurised water reactor with an integral design. This means that all the primary system components, such as the steam generators, pumps, pressuriser and control rod drive mechanisms, are located inside the reactor vessel, which requires a large diameter. For the sake of better reliability and safety, it is desirable to achieve the reduction of vessel embrittlement as well as the lowering of the dose beyond the vessel. The former can be easily accomplished by the presence of a wide downcomer, filled with water, which surrounds the core region, while the latter needs the presence of additional internal shields. An optimal shielding configuration is under investigation, for reducing the ex-vessel dose due to activated internals and for limiting the amount of the biological shielding. MCNP 4C calculations were performed to evaluate the neutron and the gamma dose during operation and the 60Co activation of various shields configurations. The gamma dose beyond the vessel from activation of its structural components was estimated in a shutdown condition, with the Monte Carlo code FLUKA 2002 and the MicroShield software. The results of the two codes are in agreement and show that the dose is sufficiently low, even without an additional shield.
authors.affiliation: Dipartimento di Ingegneria Nucleare, Politecnico di Milano, via Ponzio 34/3, 20133 Milano, Italy.
authors.forename: Stefano
authors.initials: S
authors.lastname: Agosteo
authors.forename: Antonio
authors.initials: A
authors.lastname: Cammi
authors.forename: Luisella
authors.initials: L
authors.lastname: Garlati
authors.forename: Carlo
authors.initials: C
authors.lastname: Lombardi
authors.forename: Enrico
authors.initials: E
authors.lastname: Padovani
mesh_terms: D000465:Algorithms; D003198:Computer Simulation; D004868:Equipment Failure; D019544:Equipment Failure Analysis / Q000379:methods; D005062:European Union; D005160:Facility Design and Construction / Q000379:methods; D005720:Gamma Rays; D015233:Models, Statistical; D009010:Monte Carlo Method; D009688:Nuclear Reactors; D011829:Radiation Dosage; D011834:Radiation Monitoring / Q000379:methods*; D011835:Radiation Protection / Q000295:instrumentation* / Q000379:methods*; D012984:Software