This report describes the preirradiation thermal analysis of the HRB-22 capsule designed for irradiation in the removable beryllium (RB) position of the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). CACA-2 a heavy isotope and fission product concentration calculational code for experimental irradiation capsules was used to determine time dependent fission power for the fuel compacts. The Heat Engineering and Transfer in Nine Geometries (HEATING) computer code, version 7.2, was used to solve the steady-state heat conduction problem. The diameters of the graphite fuel body that contains the compacts and the primary pressure vessel were selected such that the requirements of running the compacts at an average temper...
Capsules HRB-11 and -12 were irradiated in support of development of weak-acid-resin-derived recycle...
Within the Generation IV International Forum (GIF), considerable efforts are devoted in Europe to re...
The primary objective of this work at the Idaho National Laboratory (INL) is to determine the fuel a...
Irradiation capsule HRB-22 was a test capsule containing advanced Japanese fuel for the High Tempera...
Irradiation capsule HRB-21 is a test capsule designed to provide Modular High-Temperature Gas-Cooled...
Irradiation experiment HRB-21 is the first in a series of test capsules that are designed to provide...
The High Flax lsotope Reactor (HFIR) is being planned for construction at Oak Ridge National Laborat...
AbstractAdvanced core materials and components for nuclear reactors of a new generation are tested i...
A comparison of possible types of research reactors for the production of transplutonium elements an...
Research and development progress specifically directed toward the construction of a 40-Mw(e) protot...
Irradiations of test fuel specimens and experimental fue elements are conducted both in capsules and...
This document describes the coated-particle fuel performance test agreed to under Annex 2 of the arr...
This report describes the design, fabrication, irradiation, and evaluation of two capsule tests cont...
The beryllium permanent reflector of the High Flux Isotope Reactor has the main functions for slowin...
A controlled-temperature irradiation capsule was operated containing small fueled specimens at 160O ...
Capsules HRB-11 and -12 were irradiated in support of development of weak-acid-resin-derived recycle...
Within the Generation IV International Forum (GIF), considerable efforts are devoted in Europe to re...
The primary objective of this work at the Idaho National Laboratory (INL) is to determine the fuel a...
Irradiation capsule HRB-22 was a test capsule containing advanced Japanese fuel for the High Tempera...
Irradiation capsule HRB-21 is a test capsule designed to provide Modular High-Temperature Gas-Cooled...
Irradiation experiment HRB-21 is the first in a series of test capsules that are designed to provide...
The High Flax lsotope Reactor (HFIR) is being planned for construction at Oak Ridge National Laborat...
AbstractAdvanced core materials and components for nuclear reactors of a new generation are tested i...
A comparison of possible types of research reactors for the production of transplutonium elements an...
Research and development progress specifically directed toward the construction of a 40-Mw(e) protot...
Irradiations of test fuel specimens and experimental fue elements are conducted both in capsules and...
This document describes the coated-particle fuel performance test agreed to under Annex 2 of the arr...
This report describes the design, fabrication, irradiation, and evaluation of two capsule tests cont...
The beryllium permanent reflector of the High Flux Isotope Reactor has the main functions for slowin...
A controlled-temperature irradiation capsule was operated containing small fueled specimens at 160O ...
Capsules HRB-11 and -12 were irradiated in support of development of weak-acid-resin-derived recycle...
Within the Generation IV International Forum (GIF), considerable efforts are devoted in Europe to re...
The primary objective of this work at the Idaho National Laboratory (INL) is to determine the fuel a...