ERROR get_atoms from depletion result

MAKurniwawan · November 22, 2024, 8:29am

Hi, everyone, I get an error when trying to get get atom. Can someone tell me what part I’m having problems with?
`import numpy as np
import matplotlib.pyplot as plt
import openmc.deplete
import openmc
import pandas as pd

time_units=‘d’
results = openmc.deplete.ResultsList.from_hdf5(‘./home/OPENMC/Teras/10%/depletion_results.h5’)
time, k = results.get_keff(time_units)

############# U233 ###########################
data_u233 =
for i in range(1, 8):
for i in id :
_time, u233 = results.get_atoms( str(i),“U233”,“atom/b-cm”)
data_u233.append(u233)
data_U233 = pd.DataFrame(list(map(np.ravel, data_u233)) )
data_U233.to_excel(‘Data U233.xlsx’)
`

I get an error in results = openmc.deplete.ResultsList.from_hdf5(‘./home/OPENMC/Teras/10%/depletion_results.h5’)

TypeError: init() takes 1 positional argument but 2 were given

wahidluthfi · December 4, 2024, 10:47pm

Hai MAKurniawan, welcome to openmc community.
Sorry if I didn’t get to what you want, but I am using openmc.deplete.Results("./depletion_results.h5") when I want to get some info from the depletion results, including the atomic density of each depleteable materials.

This notebook might be helpful for you

github.com

openmc-dev/openmc-notebooks/blob/main/depletion.ipynb

{
 "cells": [
  {
   "cell_type": "markdown",
   "metadata": {},
   "source": [
    "# Pincell Depletion\n",
    "This notebook is intended to introduce the reader to the depletion interface contained in OpenMC. It is recommended that you are moderately familiar with building models using the OpenMC Python API. The earlier examples are excellent starting points, as this notebook will not focus heavily on model building.\n",
    "\n",
    "If you have a real power reactor, the fuel composition is constantly changing as fission events produce energy, remove some fissile isotopes, and produce fission products. Other reactions, like $(n, \\alpha)$ and $(n, \\gamma)$ will alter the composition as well. Furthermore, some nuclides undergo spontaneous decay with widely ranging frequencies. Depletion is the process of modeling this behavior.\n",
    "\n",
    "In this notebook, we will model a simple fuel pin in an infinite lattice using the Python API. We will then build and examine some of the necessary components for performing depletion analysis. Then, we will use the depletion interface in OpenMC to simulate the fuel pin producing power over several months. Lastly, we will wrap up with some helpful tips to improve the fidelity of depletion simulations."
   ]
  },
  {
   "cell_type": "code",
   "execution_count": 1,
   "metadata": {},
   "outputs": [],
   "source": [

This file has been truncated. show original

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ERROR get_atoms from depletion result

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