Present state of Accelerator Driven Subcritical Reactor (ADSR) project in Kyoto Univ. Research Reactor Inst. (KURRI)

Conference · Sat Jul 01 04:00:00 EDT 2006

OSTI ID:22039677

Pyeon, C H; Misawa, T; Unesaki, H; Shiroya, S ^[1]

---

1. Div. of Nuclear Engineering Science, Research Reactor Inst., Kyoto Univ., Asashiro-nishi, Kumatori-cho, Sennan-gun, Osaka 590-0494 (Japan)

The Kyoto Univ. Research Reactor Inst. (KURRI) has a plan to operate the Accelerator Driven Subcritical Reactor (ADSR) by using the Fixed Field Alternating Gradient (Fag) accelerator, which is a synchrotron-type accelerator developed in the High Energy Accelerator Research Organization (KEK) of Japan. In this ADSR, high-energy neutrons generated by interaction of 150 MeV proton beam with heavy metal will be injected into a solid-moderated and -reflected thermal core (A-core) of the Kyoto Univ. Critical Assembly (KUCA) in the KURRI. At the A-core, a series of preliminary experiments had been carried out for examination of neutronic characteristics in the ADSR by using 14 MeV pulsed neutron generator combined with the A-core. The static and dynamic parameters were evaluated in the subcritical systems: neutron multiplication, neutron decay constant, reaction rate distribution, neutron spectrum and subcriticality. The numerical analyses for the experiments had been executed by using Monte Carlo calculation code MCNP-4C3 coupling with nuclear data libraries: ENDF/B-VI.2 and JENDL-3.3. From the comparison between the experiments and the calculations, it was obtained with the results very important and valuable for a new ADSR with the FFAG accelerator. After the injection by the FFAG accelerator, both new experiments and numerical simulations could be conducted for the high-energy neutrons generated by 150 MeV proton beam. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22039677
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ACCELERATOR DRIVEN TRANSMUTATION
COMPUTERIZED SIMULATION
CRITICALITY
HEAVY METALS
KUCA REACTOR
KUR REACTOR
MEV RANGE
MONTE CARLO METHOD
NEUTRON GENERATORS
NEUTRON SPECTRA
NEUTRONS
NUCLEAR DATA COLLECTIONS
NUMERICAL ANALYSIS
PROTON BEAMS
REACTION KINETICS