Desain Inti Reaktor SCWR (Supercritical Water Reactor) Model Teras Silinder (r, z) dengan Bahan Bakar Thorium Hasil Daur Ulang

The Research of the supercritical water reactor (SCWR) core design of the cylindrical core model (r, z) using the SRAC program has been done. The SRAC basic code was PIJ and CITATION. PIJ was used to calculate the fuel level and CITATION was used to calculate the reactor core level. The calculation of the reactor core has been done on the 1/4 cylinder core (r, z) and the geometry of the fuel cell was the cylindrical cell. Reactor fuel material was thorium burned 40 GWd/t and 30 GWd/t. The neutron parameters in this research were fuel enrichment, burn up, reactor core size, reactor core configurations, multiplication factor, and power density distribution. Multiplication factor (k-effective) in this research was 1.000004, which is reactor was in a critical condition. The reactor core in critical condition had the size of radius (r) was 130 cm, height (z) was 270 cm and fuel enrichment 2.8262%. The maximum power density was 130.0808 Watts /cm3 which was located at a radius of 25 cm and 135 cm high. The peak power factor in the radial direction was 1.6063 and the peak power factor in the axial direction was 1.3189.

Download Full-text

Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors

Nuclear Energy and Technology ◽

10.3897/nucet.7.78368 ◽

2021 ◽

Vol 7 (4) ◽

pp. 311-318

Author(s):

Artavazd M. Sujyan ◽

Viktor I. Deev ◽

Vladimir S. Kharitonov

Keyword(s):

Supercritical Water ◽

Nuclear Power ◽

Power Plants ◽

Negative Impact ◽

Reactor Core ◽

Resistance Coefficient ◽

Coolant Flow ◽

Water Reactor ◽

Hydraulic Stability ◽

Supercritical Water Reactor

The paper presents a review of modern studies on the potential types of coolant flow instabilities in the supercritical water reactor core. These instabilities have a negative impact on the operational safety of nuclear power plants. Despite the impressive number of computational works devoted to this topic, there still remain unresolved problems. The main disadvantages of the models are associated with the use of one simulated channel instead of a system of two or more parallel channels, the lack consideration for neutronic feedbacks, and the problem of choosing the design ratios for the heat transfer coefficient and hydraulic resistance coefficient under conditions of supercritical water flow. For this reason, it was decided to conduct an analysis that will make it possible to highlight the indicated problems and, on their basis, to formulate general requirements for a model of a nuclear reactor with a light-water supercritical pressure coolant. Consideration is also given to the features of the coolant flow stability in the supercritical water reactor core. In conclusion, the authors note the importance of further computational work using complex models of neutronic thermal-hydraulic stability built on the basis of modern achievements in the field of neutron physics and thermal physics.

Download Full-text

General Corrosion Properties of Modified PNC1520 Austenitic Stainless Steel in Supercritical Water as a Fuel Cladding Candidate Material for Supercritical Water Reactor

Advances in Science and Technology ◽

10.4028/www.scientific.net/ast.73.72 ◽

2010 ◽

Vol 73 ◽

pp. 72-77

Author(s):

Yoshihisa Nakazono ◽

Takeo Iwai ◽

Hiroaki Abe

Keyword(s):

Stainless Steel ◽

Austenitic Stainless Steel ◽

Supercritical Water ◽

Reactor Core ◽

General Corrosion ◽

Fuel Cladding ◽

Corrosion Properties ◽

Energy Agency ◽

Water Reactor ◽

Supercritical Water Reactor

The Super-Critical Water-cooled Reactor (SCWR) has been designed and investigated because of its high thermal efficiency and plant simplification. As the operating temperature of supercritical water reactor will be between 280°C and 620°C with a pressure of 25MPa, the selection of materials is difficult and important. The PNC1520 austenitic stainless steel developed by Japan Atomic Energy Agency (JAEA) as a nuclear fuel cladding material for a Na-cooled fast breeder reactor. The corrosion data of PNC1520 in supercritical water (SCW) is required but does not exist. The purpose of the present study is to research the corrosion properties for PNC1520 austenitic stainless steel in supercritical water. The supercritical water corrosion test was performed for the standard PNC1520 (1520S), the Ti-additional type of PNC1520 (1520Ti) and the Zr-additional type of PNC1520 (1520Zr) by using a supercritical water autoclave. In view of general corrosion, 1520Zr may have larger possibility than 1520S and 1520Ti to adopt a supercritical water reactor core fuel cladding.

Download Full-text

OS8-4 Reactor core thermal characterization evaluation for the supercritical water reactor using subchannel analysis

The Proceedings of the National Symposium on Power and Energy Systems ◽

10.1299/jsmepes.2006.11.207 ◽

2006 ◽

Vol 2006.11 (0) ◽

pp. 207-210

Author(s):

Kazuaki Kitou ◽

Yoshihiko Ishii ◽

Masayoshi Matsuura ◽

Shungo Sakurai

Keyword(s):

Supercritical Water ◽

Reactor Core ◽

Thermal Characterization ◽

Water Reactor ◽

Subchannel Analysis ◽

Supercritical Water Reactor

Download Full-text

STUDI PERHITUNGAN LAJU REAKSI NEUTRON DALAM REAKTOR SCWR(SUPERCRITICAL WATER REACTOR) MODEL PERANGKAT(ASSEMBLY) HEKSAGONAL BERBAHAN BAKAR THORIUM

Jurnal Teori dan Aplikasi Fisika ◽

10.23960/fjtaf.v6i2.1844 ◽

2018 ◽

Vol 6 (2) ◽

pp. 193-200

Author(s):

Apriliana Apriliana ◽

◽

Yanti Yulianti ◽

Pulung Karo Karo

Keyword(s):

Supercritical Water ◽

Reactor Model ◽

Water Reactor ◽

Supercritical Water Reactor

Download Full-text

Design Study of Gas Cooled Fast Reactor (GFR) with Uranium Plutonium Carbide (UC-PuC) as Fuel with Addition Protactinium (Pa-231)

Computational And Experimental Research In Materials And Renewable Energy ◽

10.19184/cerimre.v3i1.26415 ◽

2020 ◽

Vol 3 (1) ◽

pp. 19

Author(s):

Alvi Nur Sabrina ◽

Arindi Kumala Sari ◽

Laela Nur Janah ◽

M. Rizqi Maulana

Keyword(s):

Fuel Cell ◽

Power Density ◽

Fast Reactor ◽

Critical Condition ◽

Peak Power ◽

Reactor Core ◽

Second Step ◽

Homogeneous Core ◽

Uranium Plutonium ◽

Fuel Fraction

Analysis performance of uranium plutonium carbide (UC-PuC) as fuel in gas cooled fast reactor (GFR) with addition of protactinium as a burnable poisons has been done. Neutronic analysis in this research was carried out using the SRAC code from JAERI with a nuclear library based on JENDL 4.0. The calculation is carried out by two steps, the first step is the PIJ calculation which calculates the fuel cell and the second step is the CITATION calculation which calculates the various configurations of the reactor core. The first calculation determines the k-eff value in a homogeneous core configuration. The results obtained show that the percentage of 10% is the sloping result with a k-eff value of 1%. The second calculation determines the k-eff value in the heterogeneous core configuration. The results obtained indicate that the fuel variation 8% -10% -12% is the most critical percentage with a peak power density value of less than 100 Watt/cc. Furthermore, the addition of protactinium with a variation of 0% to 5%. At a protactinium 4% percentage and 63% fuel fraction, the excess reactivity value is 1.02% or close to 1% which indicates that the reactor is in a critical condition.

Download Full-text