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Journal : International Journal of Science and Engineering (IJSE)

Modelling of HTR (High Temperature Reactor) Pebble-Bed 10 MW to Determine Criticality as A Variations of Enrichment and Radius of the Fuel (Kernel) With the Monte Carlo Code MCNP4C Hammam Oktajianto; Evi Setiawati; Very Richardina
International Journal of Science and Engineering Vol 8, No 1 (2015)
Publisher : Chemical Engineering Diponegoro University

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (34.27 KB) | DOI: 10.12777/ijse.8.1.42-46

Abstract

Gas-cooled nuclear reactor is a Generation IV reactor which has been receiving significant attention due to many desired characteristics such as inherent safety, modularity, relatively low cost, short construction period, and easy financing. High temperature reactor (HTR) pebble-bed as one of type of gas-cooled reactor concept is getting attention. In HTR pebble-bed design, radius and enrichment of the fuel kernel are the key parameter that can be chosen freely to determine the desired value of criticality. This paper models HTR pebble-bed 10 MW and determines an effective of enrichment and radius of the fuel (Kernel) to get criticality value of reactor. The TRISO particle coated fuel particle which was modelled explicitly and distributed in the fuelled region of the fuel pebbles using a Simple-Cubic (SC) lattice. The pebble-bed balls and moderator balls distributed in the core zone using a Body-Centred Cubic lattice with assumption of a fresh fuel by the fuel enrichment was 7-17% at 1% range and the size of the fuel radius was 175-300 µm at 25 µm ranges. The geometrical model of the full reactor is obtained by using lattice and universe facilities provided by MCNP4C. The details of model are discussed with necessary simplifications. Criticality calculations were conducted by Monte Carlo transport code MCNP4C and continuous energy nuclear data library ENDF/B-VI. From calculation results can be concluded that an effective of enrichment and radius of fuel (Kernel) to achieve a critical condition was the enrichment of 15-17% at a radius of 200 µm, the enrichment of 13-17% at a radius of 225 µm, the enrichments of 12-15% at radius of 250 µm, the enrichments of 11-14% at a radius of 275 µm and the enrichment of 10-13% at a radius of 300 µm, so that the effective of enrichments and radii of fuel (Kernel) can be considered in the HTR 10 MW. Keywords—MCNP4C, HTR, enrichment, radius, criticality 
Analysis Loading Height of HTR (High Temperature Reactor) Core to Obtain Criticlity of Reactor Evi Setiawati
International Journal of Science and Engineering Vol 9, No 2 (2015)
Publisher : Chemical Engineering Diponegoro University

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (274.058 KB) | DOI: 10.12777/ijse.9.2.

Abstract

High temperatur reactor (HTR) attract to be studied due to it has inherent safety characteristics and capabilities to produce energy economically. Design of reactor core in this study is a blend HTR 10 in China with HTR pebble-bed. The reactor has thermal power of 10 MW with inlet and outlet helium temperatures of 250oC and 700oC. HTR design is a cylindrical with helium gas as a coolant and graphite as a moderator. The HTR uses pebble-bed fuel composed a large amount of particles of TRISO in graphite metrics. Kernel radius used to analyse reactor core height in this research is 225 µm with enrichment of 16% in order to achieve critical condition. Reactor criticality is also influenced by the height of active reactor core where pebble-bed fuel is distributed. Calculation of the reactor criticality at any height variations active core is done with MCNP5 modelling techniques. The modelling is done by making the geometry of reactor and pebble-bed which is distributed by using body-centred cubic lattice in the reactor core. From the MCNP5 calculation, the first criticality of HTR can be achieved on the active core height of 150.9012 cm calculated from the bottom active core with criticality value of 1.00312±0.00090. The higher active reactor core is, the more increasing the reactor criticality is. This is occured due to there are many fuel balls of pebble-bed used, so that activity of fission in reactor increases. However, reactor criticality is still in stable condition in each the rise of active core height from critical core height even though reactor reactivity increases 0.01 Δk/k. The minimum of fuel needed to achieve initial criticality (critical core height) is 11,805 pebbles and 8,906 moderators.
Co-Authors Agus Margiantoro Ahadiyah, Naeli Ni'matin Ana Aprilia Anak Agung Gede Sugianthara Ardiansyah, Mustofa Ariyanti Nur Anisa Asep Yoyo Wardaya Awwalin, Aufi Rizqiatul Binu Soesanto, Qidir Maulana Bunawas Bunawas Choirul Anam Choirul Anam AM Diponegoro Cicilia Artitin Cory Amelia Dessy Dian Monita Pardede Djoko Heru Pamungkas Dodi Junaedi Dortua Helena Sidabutar Eko Hidayanto Elvira Situmorang Erna Mariani Evi Handriani Bertua Simamora F Arianto Fajar Arianto Galih Puspa Saraswati Gede Sutresna Wijaya Gutji, Nelyahardi Hammam Oktajianto Hammam Oktajianto Handini Devi Yunitasari Harahap, Nur Hasanah Ifa Istighfaroh Indras Marhaendrajaya Intan Andriani Jatmiko Endro Suseno K Sofjan Firdausi K. Sofjan Firdausi Kusworo Adi Maria Theresia Darini Masdi Masdi Maulana, Alsa Putra Mochammad Facta Mohammad Afif Rachmatulloh Much. Azam Muchammad Azam, Muchammad Mursiyatun Mursiyatun Nanang Suriansyah Ngurah Ayu Ketut Umiati Nina GInanto Putri Nur Indah Lestari Nurul Laili Khoirut Tabi’atin Pandji Triadyaksa Poppy Intan Thahaja Rahmadi Setyawan Rahmaningtyas, Avivah Riana Anis Safitri Ridwan Eko Susanto Rinarto Subroto S Juliawan S. Suryono Sanggam Ramantisa Sanggam Ramantisan Sanggam Ramantisan Sari, Devi Artika Setiyono Setiyono Stefani, Eska Sudrajat, Ignasius Suprih Sumariyah M.Si Sumariyah Sumariyah Suroto Suroto Susilo Hadi, Susilo Suwardi Suwardi Syahria Syahria Trisna Budiwati Verry Richardina, Verry Very Richardina Very Richardina Wijianto Wijianto Windarta, Jaka Yunianta Yusup Hidayat Zaenal Arifin Zaenul Muhlisin Zainul Muhlisin