Control rod worth

This paper presents the development and verification of a deterministic model using the SRAC code system for analysing the criticality and control rod worth of the Dalat Nuclear Research Reactor (DNRR). Numerical calculations were performed based on seven core configurations established experimentally during the startup period of the DNRR.

7p vicedric 08-02-2023 4 3   Download

The GUINEVERE project was launched in 2006, within the 6th Euratom Framework Program IP-EUROTRANS, in order to study the feasibility of transmutation in Accelerator Driven subcritical Systems (ADS).

9p christabelhuynh 31-05-2020 11 0   Download

In this paper, three types of operational and industrial absorbers used at research reactors, including Ag-In-Cd alloy, B4C, and Hf are selected for sensitivity analyses. Their integral effects on the main neutronic core parameters important to safety issues are investigated. These parameters are core excess reactivity, shutdown margin, total reactivity worth of control rods, thermal neutron flux, power density distribution, and Power Peaking Factor (PPF). The IAEA 10 MW benchmark core is selected as the case study to verify calculations.

8p minhxaminhyeu5 30-06-2019 22 0   Download

Within the framework of the ASTRID project, core design studies are being conducted by the CEA with support from AREVA and EDF. The pre-conceptual design studies are being conducted in accordance with the GEN IV reactor objectives, particularly in terms of improving safety. This involves limiting the consequences of 1) a hypothetical control rod withdrawal accident (by minimizing the core reactivity loss during the irradiation cycle), and 2) an hypothetical loss-of-flow accident (by reducing the sodium void worth).

10p minhxaminhyeu5 30-06-2019 12 2   Download

This article presents clean core criticality calculations and control rod worth calculations for TRIGA (Training, Research, Isotope production-General Atomics) Mark II research reactor benchmark cores using Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4) and Program for Reactor In-core Analysis using Diffusion Equation (PRIDE) codes. Cores 133 and 134 were analyzed in 2-D (r, q) and 3-D (r, q, z), using WIMS-D/4 and PRIDE codes.

8p minhxaminhyeu3 25-06-2019 14 0   Download

The purpose of this study is to investigate whether an SMR would have enough control rod worth to compensate for large reactivity feedback. The investigation begins with classification of reactivity and completes an analysis of the reactivity balance in each reactor state for the SMR model.

6p minhxaminhyeu3 25-06-2019 9 1   Download

The present study aims to assess the excess induced reactivity in a Miniature Neutron Source Reactor (MNSR) for a Beyond Design Basis Accident (BDBA) scenario. The BDBA scenario as defined in the Safety Analysis Report (SAR) of the reactor involves sticking of the control rod and filling of the inner and outer irradiation sites with water. At the end of the MNSR core life, 10.

6p minhxaminhyeu3 25-06-2019 15 0   Download

In this paper, three-dimensional neutronic calculations were performed in order to calculate the dependency of CRW on the temperature of fuel and moderator and the moderator void. Calculations were performed using the known MTR_PC computer codes in the core configuration 61 of TRR. The dependency of CRW on the fuel temperature in the range of 20e340
C and the moderator temperature of each control rods were studied.

11p minhxaminhyeu3 25-06-2019 14 1   Download