Extending the maximum operation time of the MNSR reactor

The Fuel Temperature Reactivity Coefficient (FTRC) is an important parameter in design, control, and safety, particularly in PWR reactor. It is then very important to validate any new library for an accurate prediction of this parameter. The objective of this work is to determine the value of the FTRC parameter using the new WIMDS library based on ENDF/BVIII.0 nuclear data files. For this purpose, it is used a set of light water moderated lattice experiments as the PWR-1175 MWe experiment critical reactors, the reactor using UO2 fuel pellet. The analysis is used with WIMSD-5B lattice code with original cross-section libraries and WIMSD-5B with ENDF/B-VIII.0 new cross-section libraries. The results showed that the fuel temperatures reactivity coefficients for the PWR reactor using original libraries is – 3.10 pcm/K with enrichment of 3.1% but for ENDF/B-VlII.0 libraries is – 3.00 pcm/K. Compared to the experimental data of the reactor core, the difference is in the range of 6.9 % for ENDF/B-VIII.0 libraries. It can be concluded that for the reactor, it is better to use ENDF/B-VIII.0 libraries because the original library is not accurate anymore.

Section: Reactivity Coefficientmentioning

confidence: 99%

Analysis of Fuel Temperature Reactivity Coefficient of the PWR Using Wims Code

Rajagukguk

Bahkri²,

Surbakti³

2022

“…Since the year 1998, a new loading pattern 5/1 was imposed on the RSG-GAS reactor [17][18][19][20]. According to this pattern, a reactor is operated for a duration of 625 MWD each cycle.…”

Section: Reactor Operationmentioning

confidence: 99%

Assessment of Operation Safety of the RSG-Gas Reactor to Serve Radioisotope Target Irradiation

Kuntoro

Suparlina²,

Purwadi³

2022

The RSG-GAS multipurpose reactor is operated to serve the utilization in the field of radioisotope production and NAA, material research. The reactor actually has power of 30 MW thermal, but upon considerations of efficiency and of most users requirements, the reactor is mostly operated at the power of 15 MW thermal, 5 days a week to produce a primary radioisotope from target of 2 grams U-235. To guarantee the safe operation and optimum utilization, a safety procedure was established. The paper is intended to assesst the operation safety in serving radioisotope target irradiation at its cycle operation. Assessment was carried out for core numbers 102 – 105. The result shows that excess reactivity and shutdown margin reactivity are safe to provide the target irradiation in the core for each cycle operation.

“…Moreover, plate fuel's compact construction makes it possible to reduce the size of the reactor core. For high-flux research reactors and small, highly efficient nuclear power plants, plate-type fuel is a typical fuel configuration [4].…”

Section: Introduction mentioning

confidence: 99%

Neutronic Analysis of the RSG-GAS Fuel Using Burnable Poison

Ridho¹,

Santosa

Surbakti³

et al. 2023

Control and safety of nuclear reactors are significantly influenced by the determination of safety parameters. The three most crucial safety factors for assessing reactor status are the infinite multiplication factor, reactivity coefficients, and power peaking factor. The objective of the present study is to examine how the RSG-GAS fuel safety parameters behave in a typical reactor operation state. A lattice cell fuel model of the fuel lattice of the RSG-GAS reactor core was modeled using WIMSD-5Bwith cross-section library data based on ENDF/B-VIII.0. The value of the infinite multiplication factor with various burnable poison concentrations, as well as the moderator and fuel temperatures, were the variables that were examined. The reactivity coefficient parameters were similarly analyzed. By comparing the WIMSD-5B code results with information from the SAR document, the WIMS model for RSG-GAS fuel was verified, and it was inferred that the parameters are in good agreement. Safe behavior uses the predicted reactivity coefficient values as an example.