Word Count : 268

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Consider a one-speed neutron population in an arbitrary fixed volume $V$ with boundary $\partial V$. Let $n(\mathbf r,t)$ be the neutron density, $ \phi(\mathbf r,t)=v\,n$ the scalar flux for constant speed $v$, $ \mathbf J(\mathbf r,t)$ the neutron current density, $ \Sigma_a$ the macroscopic absorption cross section (including capture and fission absorption), $ ______ ___ ___ ______ ______ _________ _____ ________ ___.
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