Calculation and comparison of xenon and samarium reactivities of the HEU, LEU core in the low power research reactor

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.

Section: Resultsmentioning

confidence: 99%

“…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 temperature reactivity coefficient (αT) is defined as the partial derivative of the reactivity to changes in temperature [5]. αT= δρ/δT (2) with, δρ = reactivity changed δT = temperature changed…”

Section: Temperature Reactivity Coefficientmentioning

confidence: 99%

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

Rajagukguk

Bahkri²,

Surbakti³

2022

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.

“…As a result, we started a new set of computational benchmarks to represent these new realities. Using the WIMSD-5B code package and many libraries [4,5], the zero leakage, poison-free pin cells were irradiated to over 70 MWd/kg at constant power. The calculated result will be compared to CASMO-4 and MOCUP [6].…”

Section: Introduction mentioning

confidence: 99%

Analysis of Thorium Pin Cell Burn Up of the PWR Using Wims Code

Panggabean¹,

Rajagukguk

Bakhri³

2022

A thorium-fueled benchmark comparison was made in this study between state-of-the-art codes, WIMSD-5B code to MOCUP (MCNP4B + ORIGEN2), and CASMO-4 for burnup calculations as part of efforts to examine the possible benefits of using thorium in PWR fuel. WIMSD-5B calculations employ the same model as a reference, MOCUP, and CASMO, however, there are some variances in methodology and cross-section libraries. On a PWR pin cell model, eigenvalue and isotope concentrations were examined up to high burnup. The eigenvalue comparison as a function of burnup is good, with a maximum difference of less than 5% and an average absolute difference of less than 1%. The isotope concentration comparisons outperform a set of ThO2-UO2 fuel benchmarks and are comparable to a set of uranium fuel benchmarks previously published in the literature. As a function, the eigenvalue comparison The actinide and fission product data sources for a typical thorium fuel are reported in the WIMSD-5B burnup calculations. The reasons for discrepancies in coding are examined and explored.Keywords: Thorium, PWR Fuel, Burn up, Pin Cell, WIMSD-5B