Gamma heating calculations for the HFR
Creators
- 1. Nuclear Research and Consultancy NRG, Westerduinweg 3, Petten (Netherlands)
Description
In the design of an irradiation experiment one needs to know the amount of heat generated in it. When photons are the main source of heating, as is the case in experimental positions in a materials test reactor, this poses a problem. The photon source in this case consists of two parts: prompt photons and photons emitted by decaying fission products (delayed photons). The prompt photons are commonly taken into account in particle transport codes, but the photons from fission product decay are not. Here we propose to incorporate the delayed photons by means of a simple engineering correlation, which can easily be implemented in e.g. a Monte Carlo transport code such as MCNP. Our results compare well with data for all experimental positions in the High Flux Reactor (HFR) in Petten, the Netherlands. We also discuss the reduction in heating levels when converting the HFR to LEU. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 5 p.
Conference
- Title
- American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
- Acronym
- PHYSOR-2006
- Dates
- 10-14 Sep 2006
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 43130123
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPARATIVE EVALUATIONS; EXPERIMENTAL DATA; FISSION PRODUCTS; GAMMA RADIATION; HFR REACTOR; HIGHLY ENRICHED URANIUM; IRRADIATION; MONTE CARLO METHOD; PHOTON TRANSPORT; RADIATION HEATING; SLIGHTLY ENRICHED URANIUM
- Descriptors DEC
- ACTINIDES; CALCULATION METHODS; DATA; ELECTROMAGNETIC RADIATION; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EVALUATION; HEATING; INFORMATION; IONIZING RADIATIONS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPES; MATERIALS; MATERIALS TESTING REACTORS; METALS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL DATA; RADIATION TRANSPORT; RADIATIONS; RADIOACTIVE MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs.