science/py-OpenMC: New port: Monte Carlo neutron and photon transport simulation code (Python)

science/Makefile

@@ -232,6 +232,7 @@
     SUBDIR += py-MDAnalysis
     SUBDIR += py-MDAnalysisTests
     SUBDIR += py-OpenFermion
+    SUBDIR += py-OpenMC
     SUBDIR += py-PubChemPy
     SUBDIR += py-PyFR
     SUBDIR += py-PyNE

science/py-OpenMC/Makefile

+PORTNAME=	OpenMC
+DISTVERSIONPREFIX=	v
+DISTVERSION=	0.12.2
+CATEGORIES=	science
+PKGNAMEPREFIX=	${PYTHON_PKGNAMEPREFIX}
+
+MAINTAINER=	yuri@FreeBSD.org
+COMMENT=	Monte Carlo neutron and photon transport simulation code (Python)
+
+LICENSE=	MIT
+LICENSE_FILE=	${WRKSRC}/LICENSE
+
+PY_DEPENDS=	${PYNUMPY} \
+		${PYTHON_PKGNAMEPREFIX}h5py>0:science/py-h5py@${PY_FLAVOR} \
+		${PYTHON_PKGNAMEPREFIX}ipython>0:devel/ipython@${PY_FLAVOR} \
+		${PYTHON_PKGNAMEPREFIX}lxml>0:devel/py-lxml@${PY_FLAVOR} \
+		${PYTHON_PKGNAMEPREFIX}matplotlib>0:math/py-matplotlib@${PY_FLAVOR} \
+		${PYTHON_PKGNAMEPREFIX}pandas>0:math/py-pandas@${PY_FLAVOR} \
+		${PYTHON_PKGNAMEPREFIX}scipy>0:science/py-scipy@${PY_FLAVOR} \
+		${PYTHON_PKGNAMEPREFIX}uncertainties>0:math/py-uncertainties@${PY_FLAVOR}
+BUILD_DEPENDS=	openmc>0:science/openmc \
+		${PY_DEPENDS}
+RUN_DEPENDS=	openmc>0:science/openmc \
+		${PY_DEPENDS}
+
+USES=		python
+USE_PYTHON=	distutils concurrent autoplist
+
+USE_GITHUB=	yes
+GH_ACCOUNT=	${PORTNAME:tl}-dev
+GH_PROJECT=	${PORTNAME:tl}
+
+PLIST_FILES=	${PYTHON_SITELIBDIR}/openmc/lib/libopenmc.so
+
+post-install:
+	# strip
+	@${STRIP_CMD} ${STAGEDIR}${PYTHON_SITELIBDIR}/openmc/data/*.so
+	# link the library
+	@${LN} -s ${LOCALBASE}/lib/libopenmc.so ${STAGEDIR}${PYTHON_SITELIBDIR}/openmc/lib/libopenmc.so
+
+.include <bsd.port.mk>

science/py-OpenMC/distinfo

+TIMESTAMP = 1633806014
+SHA256 (openmc-dev-openmc-v0.12.2_GH0.tar.gz) = 29ca66d0e7140357d747516807c91cbf1aace0ebc29dfe9650e9da3c2975dd94
+SIZE (openmc-dev-openmc-v0.12.2_GH0.tar.gz) = 8316985

science/py-OpenMC/pkg-descr

+Python bindings for OpenMC.
+
+OpenMC is a community-developed Monte Carlo neutron and photon transport
+simulation code. It is capable of performing fixed source, k-eigenvalue, and
+subcritical multiplication calculations on models built using either a
+constructive solid geometry or CAD representation. OpenMC supports both
+continuous-energy and multigroup transport. The continuous-energy particle
+interaction data is based on a native HDF5 format that can be generated from
+ACE files produced by NJOY. Parallelism is enabled via a hybrid MPI and OpenMP
+programming model.
+
+WWW: https://openmc.org/