Study And Assessment Of Generation IV Reactor Nuclear Data With Fast Neutron Spectra

STUDY AND ASSESSMENT OF GENERATION IV REACTOR NUCLEAR DATA WITH FAST NEUTRON SPECTRA

Suwoto
PTRKN-BATAN, Kawasan PUSPIPTEK Gd. 80, Serpong, Tangerang, 15310

ABSTRACT
STUDY AND ASSESSMENT OF GENERATION IV REACTOR NUCLEAR DATA WITH FAST NEUTRON SPECTRA. Generation IV International Forum (GIF) has evaluated and assessed NES of Gen-IV and selected six potential types of reactors to be deployed in the next decade. Those include GFR, LFR, SFR, MSR, SCWR and VHTR. The assessment focused on the nuclear data characteristic parameter and nuclear data uncertainties of Gen-IV reactor with fast neutron spectrum. Until 2008, the accuracy target of nuclear data cross-sections used it in fast reactor spectrum calculation are relatively significant especially for σ-capture, σ-fission, and σ-inelastic. Several differences of nuclear data cross-sections on minor actinide isotopes between expected and targeted parameters are observed such as σfission of Cm-244 isotope up to 10 times larger and σ-capture of 92-U-238 isotope around 1.5-2 times higher than targeted parameters. Uncertainty and accuracy of minor actinide cross-sections for fast spectrum Gen-IV reactors provide relatively significant discrepancies (1.3 to 10 times higher) in term of accuracy between expected and targeted parameters. There are some differences of several evaluated nuclear data files. Some discrepancies on integral parameter of fast spectrum Gen-IV reactors between expected and targeted such k-eff, void reactivity and Doppler effects, peak power and burn-up are clearly observed. Accurate and precise cross-sections data of radiation captured and threshold reaction cross sections such as (n,2n), (n,3n), (n,p), (n,α) are necessary for fast reactors.

Keywords: cross-sections, fast neutron spectrum, GFR, LFR, SFR, uncertainty and target accuracy
Published : Proceeding "SEMINAR NASIONAL PENGEMBANGAN ENERGI NUKLIR II 2009", Jakarta, 25 Juni 2009.

Read more...

Validation of Nuclear Data For Structural Materials By Integral Methods

VALIDATION OF NUCLEAR DATA FOR STRUCTURAL MATERIALS BY INTEGRAL METHODS

Sahala Lumbanraja, Masdin, Ign.Djoko Irianto
Center for Nuclear Technology Assessment - BATAN

ABSTRACT
VALIDATION OF NUCLEAR DATA FOR STRUCTURAL MATERIALS BY INTEGRAL METHODS. Nuclear data for structural materials is needed to ensure the operation safety of nuclear reactors. To avoid some accident of nuclear reactors, so validation of nuclear data is needed continuously. Some methods have developed to increase accuracy of nuclear data, like differential and integral methods. In this paper, we will describe the integral method by energy independent adjoint flux that based only at measurement of reactivity absorption. Different structural material such as Fe, Ni, Mn, Cu and Cr, their nuclear data have been evaluated.

Keywords : Nuclear data, Structural materials, Integral methods,
Published : Proceeding "Seminar Ke-4 Reaktor Temperatur Tinggi dan Teknologi Nuklir", Jakarta, 15-16 February 1999, ISSN 0854-8803

Read more...

DEVELOPMENT OF NUCLEAR DATA MODULE FOR VERIFY THE CRITICALITY OF VHTR CORE CALCULATION

DEVELOPMENT OF NUCLEAR DATA MODULE FOR VERIFY
THE CRITICALITY OF VHTR CORE CALCULATION

Zuhair, Syafarudin, Ign. Djoko Irianto, Hery Adrial, Maman Mulyaman
Center for Reactor Technology and Nuclear Safety – BATAN
Kompleks Puspiptek Serpong, Tangerang Selatan

ABSTRACT
DEVELOPMENT OF NUCLEAR DATA MODULE FOR VERIFY THE CRITICALITY OF VHTR CORE CALCULATION. A data nuclear module interfacing between the MCNP (Monte Carlo N-Particle) transport code input and the cross section spectra resulted from experiments or simulations, was developed to support the core criticality calculation of VHTR (very high temperature reactor). The module was equipped by a sub-module converting experimental spectrum into cross section spectrum, and a sub-module of simulation that consists of a package of calculation codes. In the experimental sub-module, all kinematical steps starting from the state of incident particle colliding with atom target until scattering particle is emitted at a certain angle. The simulation sub-module was constructed by embedding the QMD+SDM Quantum Molecular Dynamics + Statistical Decay Model) into the main module. The module was also equipped by a graphical interface for the parameters of TRISO dimensions and the densities of its elements. By this simulation, energy spectra of elastic and inelastic reaction ratio for three major atoms constructing TRISO particle, i.e. C-12, O-16, and Si-32, were obtained. The results show that the lowest elastic ratio is found at the outgoing energy between 3 to 4 MeV, which is identical for those three atoms. This output is expected to become an essential feedback for MCNP calculation theory. However, more intensive studies for other atoms related to this issue are required.

Keywords: MCNP, QMD, SDM, pebble bed, TRISO, VHTR, elastic neutron reaction ratio.
Published: Technical report of Block Grant 2009

Read more...