THE EFFECT OF CONTROL ROD DISPLACEMENT AGAINST THE SAFETY OF REACTOR CORE OF NUCLEAR BATTERY
Ign. Djoko Irianto, Budi Santoso, Sahala Lumban Raja, Ahmad Syaukat
Center for Nuclear Technology Assessment - BATAN
Email: igndjoko@batan.go.id
ABSTRACT
THE EFFECT OF CONTROL ROD DISPLACEMENT AGAINST THE SAFETY OF REACTOR CORE OF NUCLEAR BATTERY. The Nuclear Battery reactor is small, solid-state passively cooled reactor power supply being developed to produce electricity and/or steam heat in remote locations. A fundamental design principles of the Nuclear Battery is a very high level of safety with no short-term intervention required by either human operators or engineered safety devices. One of the limiting hypothetical accident scenarios for a nuclear reactor is the rapid ejection of a single control rod from and initial state of reactor criticality. This paper presents a safety aspect of reactor core of the Nuclear Battery, and shows that the Nuclear Battery would survive a rapid reactivity insertion of a least 20 mk without compromising fuel integrity.
Keywords : Nuclear Battery, Safety Aspect, Reactor Core, Reactivity
Published : Proceeding "Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan dan Teknologi Nuklir", Yogyakarta, 21-22 Maret 1990, ISSN No.: 0216-3128
THERMAL-HYDRAULIC ANALYSIS OF THE NUCLEAR BATTERY COOLANT SYSTEM
Ign. Djoko Irianto, Budi S., Sarwo D.Danupoyo, Ahmad Syaukat, Budi Santoso
Center for Nuclear Technology Assessment - BATAN
Email: igndjoko@batan.go.id
ABSTRACT
THERMAL-HYDRAULIC ANALYSIS OF THE NUCLEAR BATTERY COOLANT SYSTEM. Thermal-hydraulic analysis has been done for the coolant system of the nuclear battery, which utilizes heat pipes as the primary coolant system for heat removal from the reactor core to the secondary coolant system. This paper analysis the thermal hydraulic aspect of the nuclear battery coolant system by constructing the design model for heat pipe, as the primary coolant system, and analyzing the energy balance on the secondary coolant system. The model refers to the nuclear battery operated at a power of 2400 kW(t) and nominal core graphite temperature of 550 oC. The wrapped screen wick type heat pipe 3 m length and 5 cm diameter with potassium as working fluid has a maximum axial heat flow of 102957 W at operating temperature 482 oC. Using toluene as working fluid at maximum temperature of 370 oC the secondary coolant system equipped with a regenerator has a thermal efficiency of 26 %. The nuclear battery with capacity of 2400 kW(t) requires 24 heat pipes.
Keywords : Thermal-Hydraulic Analysis, Nuclear Battery, Primary coolant System, Heat Pipe, Thermal Efficiency
Published : Proceeding "Seminar Seperempat Abad Reaktor Nuklir Mengabdi Ilmu Pengetahuan dan Teknologi", Bandung, 16-17 Oktober 1989, ISSN No. : 1410-1769
