Merge branch 'release-v0.5.4' into develop

This commit is contained in:
Bryan Herman 2014-03-25 23:09:41 -04:00
commit df2127f685
14 changed files with 330 additions and 37 deletions

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@ -4,6 +4,296 @@
State Point Binary File Specifications
======================================
-----------
Revision 11
-----------
**integer(4) FILETYPE_STATEPOINT**
Flags whether this file is a statepoint file or a particle restart file.
**integer(4) REVISION_STATEPOINT**
Revision of the binary state point file. Any time a change is made in the
format of the state-point file, this integer is incremented.
**integer(4) VERSION_MAJOR**
Major version number for OpenMC
**integer(4) VERSION_MINOR**
Minor version number for OpenMC
**integer(4) VERSION_RELEASE**
Release version number for OpenMC
**character(19) time_stamp**
Date and time the state point was written.
**character(255) path**
Absolute path to directory containing input files.
**integer(8) seed**
Pseudo-random number generator seed.
**integer(4) run_mode**
run mode used. The modes are described in constants.F90.
**integer(8) n_particles**
Number of particles used per generation.
**integer(4) n_batches**
Total number of batches (active + inactive).
**integer(4) current_batch**
The number of batches already simulated.
if (run_mode == MODE_EIGENVALUE)
**integer(4) n_inactive**
Number of inactive batches
**integer(4) gen_per_batch**
Number of generations per batch for criticality calculations
*do i = 1, current_batch \* gen_per_batch*
**real(8) k_generation(i)**
k-effective for the i-th total generation
*do i = 1, current_batch \* gen_per_batch*
**real(8) entropy(i)**
Shannon entropy for the i-th total generation
**real(8) k_col_abs**
Sum of product of collision/absorption estimates of k-effective
**real(8) k_col_tra**
Sum of product of collision/track-length estimates of k-effective
**real(8) k_abs_tra**
Sum of product of absorption/track-length estimates of k-effective
**real(8) k_combined(2)**
Mean and standard deviation of a combined estimate of k-effective
**integer(4) cmfd_on**
Flag that cmfd is on
if (cmfd_on)
**integer(4) cmfd % indices**
Indices for cmfd mesh (i,j,k,g)
**real(8) cmfd % k_cmfd(1:current_batch)**
CMFD eigenvalues
**real(8) cmfd % src(1:G,1:I,1:J,1:K)**
CMFD fission source
**real(8) cmfd % entropy(1:current_batch)**
CMFD estimate of Shannon entropy
**real(8) cmfd % balance(1:current_batch)**
RMS of the residual neutron balance equation on CMFD mesh
**real(8) cmfd % dom(1:current_batch)**
CMFD estimate of dominance ratio
**real(8) cmfd % scr_cmp(1:current_batch)**
RMS comparison of difference between OpenMC and CMFD fission source
**integer(4) n_meshes**
Number of meshes in tallies.xml file
*do i = 1, n_meshes*
**integer(4) meshes(i) % id**
Unique ID of mesh.
**integer(4) meshes(i) % type**
Type of mesh.
**integer(4) meshes(i) % n_dimension**
Number of dimensions for mesh (2 or 3).
**integer(4) meshes(i) % dimension(:)**
Number of mesh cells in each dimension.
**real(8) meshes(i) % lower_left(:)**
Coordinates of lower-left corner of mesh.
**real(8) meshes(i) % upper_right(:)**
Coordinates of upper-right corner of mesh.
**real(8) meshes(i) % width(:)**
Width of each mesh cell in each dimension.
**integer(4) n_tallies**
*do i = 1, n_tallies*
**integer(4) tallies(i) % id**
Unique ID of tally.
**integer(4) tallies(i) % n_realizations**
Number of realizations for the i-th tally.
**integer(4) size(tallies(i) % scores, 1)**
Total number of score bins for the i-th tally
**integer(4) size(tallies(i) % scores, 2)**
Total number of filter bins for the i-th tally
**integer(4) tallies(i) % n_filters**
*do j = 1, tallies(i) % n_filters*
**integer(4) tallies(i) % filter(j) % type**
Type of tally filter.
**integer(4) tallies(i) % filter(j) % n_bins**
Number of bins for filter.
**integer(4)/real(8) tallies(i) % filter(j) % bins(:)**
Value for each filter bin of this type.
**integer(4) tallies(i) % n_nuclide_bins**
Number of nuclide bins. If none are specified, this is just one.
*do j = 1, tallies(i) % n_nuclide_bins*
**integer(4) tallies(i) % nuclide_bins(j)**
Values of specified nuclide bins
**integer(4) tallies(i) % n_score_bins**
Number of scoring bins.
*do j = 1, tallies(i) % n_score_bins*
**integer(4) tallies(i) % score_bins(j)**
Values of specified scoring bins (e.g. SCORE_FLUX).
*do j = 1, tallies(i) % n_score_bins*
**integer(4) tallies(i) % scatt_order(j)**
Scattering Order specified scoring bins.
**integer(4) tallies(i) % n_score_bins**
Number of scoring bins without accounting for those added by
the scatter-pn command.
**integer(4) source_present**
Flag indicated if source bank is present in the file
**integer(4) n_realizations**
Number of realizations for global tallies.
**integer(4) N_GLOBAL_TALLIES**
Number of global tally scores
*do i = 1, N_GLOBAL_TALLIES*
**real(8) global_tallies(i) % sum**
Accumulated sum for the i-th global tally
**real(8) global_tallies(i) % sum_sq**
Accumulated sum of squares for the i-th global tally
**integer(4) tallies_on**
Flag indicated if tallies are present in the file.
if (tallies_on > 0)
*do i = 1, n_tallies*
*do k = 1, size(tallies(i) % scores, 2)*
*do j = 1, size(tallies(i) % scores, 1)*
**real(8) tallies(i) % scores(j,k) % sum**
Accumulated sum for the j-th score and k-th filter of the
i-th tally
**real(8) tallies(i) % scores(j,k) % sum_sq**
Accumulated sum of squares for the j-th score and k-th
filter of the i-th tally
if (run_mode == MODE_EIGENVALUE and source_present)
*do i = 1, n_particles*
**real(8) source_bank(i) % wgt**
Weight of the i-th source particle
**real(8) source_bank(i) % xyz(1:3)**
Coordinates of the i-th source particle.
**real(8) source_bank(i) % uvw(1:3)**
Direction of the i-th source particle
**real(8) source_bank(i) % E**
Energy of the i-th source particle.
-----------
Revision 10
-----------

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@ -4,10 +4,6 @@
Release Notes for OpenMC 0.5.4
==============================
.. note::
These release notes are for an upcoming release of OpenMC and are still
subject to change.
-------------------
System Requirements
-------------------
@ -21,16 +17,17 @@ the problem at hand (mostly on the number of nuclides in the problem).
New Features
------------
- New XML parsing backend (FoX)
- Source sites outside geometry are resampled
- XML-Fortran backend replaced by FoX XML
- Ability to write particle track files
- Handle lost particles more gracefully (via particle track files)
- Source sites outside geometry are resampled
- Multiple random number generator streams
- plot_mesh_tally.py utility converted to use Tkinter rather than PyQt
- Mesh tally plotting utility converted to use Tkinter rather than PyQt
- Script added to download ACE data from NNDC
- Mixed ASCII/binary cross_sections.xml now allowed
- Expanded options for writing source bank
- Re-enabled ability to use source file as starting source
- S(a,b) recalculation avoided when same nuclide and S(a,b) table are accessed
---------
Bug Fixes
@ -41,12 +38,16 @@ Bug Fixes
- 8884fb_: Check for all ZAIDs for S(a,b) tables
- b38af0_: Fix XML reading on multiple levels of input
- d28750_: Fix bug in convert_xsdir.py
- cf567c_: ENDF/B-VI data checked for compatibility
- 6b9461_: Fix p_valid sampling inside of sample_energy
.. _32c03c: https://github.com/mit-crpg/openmc/commit/32c03c
.. _c71ef5: https://github.com/mit-crpg/openmc/commit/c71ef5
.. _8884fb: https://github.com/mit-crpg/openmc/commit/8884fb
.. _b38af0: https://github.com/mit-crpg/openmc/commit/b38af0
.. _d28750: https://github.com/mit-crpg/openmc/commit/d28750
.. _cf567c: https://github.com/mit-crpg/openmc/commit/cf567c
.. _6b9461: https://github.com/mit-crpg/openmc/commit/6b9461
------------
Contributors

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@ -414,6 +414,8 @@ attributes/sub-elements:
source bank will be available. It should be noted that a user can set both
this element to "true" and specify batches to write a permanent source bank.
*Default*: false
``<survival_biasing>`` Element
------------------------------