Temperature controlled material irradiation in the advanced test reactor

Ingram, F.W; Palmer, Joe; Stites, Deirdre

doi:10.1016/s0022-3115(98)00366-3

Cited by 3 publications

(2 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…(1) ATR, INL. In order to achieve a high fast (>0.1 MeV) to thermal (here <0.1 eV) neutron flux ratio [16], a 0.25 cm thick neutron screen of Al-B alloy filter has been inserted in the irradiation test vehicle (ITV, Figure 20) in ATR (Figure 8). The ITV is loaded in the central flux trap where the highest neutron flux occurs.…”

Section: Boron Neutron Screens Already In Operationmentioning

confidence: 99%

See 1 more Smart Citation

Compilation of Existing Neutron Screen Technology

Chrysanthopoulou

Savva

Varvayanni

et al. 2014

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

The presence of fast neutron spectra in new reactors is expected to induce a strong impact on the contained materials, including structural materials, nuclear fuels, neutron reflecting materials, and tritium breeding materials. Therefore, introduction of these reactors into operation will require extensive testing of their components, which must be performed under neutronic conditions representative of those expected to prevail inside the reactor cores when in operation. Due to limited availability of fast reactors, testing of future reactor materials will mostly take place in water cooled material test reactors (MTRs) by tailoring the neutron spectrum via neutron screens. The latter rely on the utilization of materials capable of absorbing neutrons at specific energy. A large but fragmented experience is available on that topic. In this work a comprehensive compilation of the existing neutron screen technology is attempted, focusing on neutron screens developed in order to locally enhance the fast over thermal neutron flux ratio in a reactor core.

show abstract

Section: Boron Neutron Screens Already In Operationmentioning

confidence: 99%

“…The following results were derived by this study. Although the results of the study have shown the great thermal neutron absorption capability of B 4 C, its utilization was not considered in practice because of its reactivity effect and Figure 20: Core region ITV cross-section without specimens [16].…”

Section: Boron Neutron Screens Under Development or Studymentioning

confidence: 99%

Compilation of Existing Neutron Screen Technology

Chrysanthopoulou

Savva

Varvayanni

et al. 2014

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

show abstract

Comparison of nuclear irradiation parameters of fusion breeder materials in high flux fission test reactors and a fusion power demonstration reactor

Fischer¹,

Herring

Hogenbirk

et al. 2000

Journal of Nuclear Materials

View full text Add to dashboard Cite

Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum

Chrysanthopoulou

Savva

Varvayanni

et al. 2018

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

The safe introduction of Generation IV (Gen IV) reactor concepts into operation will require extensive testing of their components. This must be performed under neutronic conditions representative of those expected to prevail inside the new reactor cores when in operation. In a thermal Material Testing Reactor (MTR) such neutronic conditions can be achieved by tailoring the prevailing neutron spectrum with the utilization of a device containing appropriate materials. In this work various materials are investigated as candidate components of a device that will be required in case that a thermal MTR neutron energy spectrum must be locally transformed, so as to imitate Sodium cooled Fast Reactor (SFR). Many nuclides have been examined with respect to only their neutronic behavior, providing thus a pool of neutronically appropriate materials for consideration in further investigation, such as regarding reactor safety and fabrication issues. The nuclides have been studied using the neutronics code TRIPOLI-4.8 while the reflector of the Jules Horowitz Reactor (JHR) was considered as the hosting environment of the transforming device. The results obtained suggest that elements with important inelastic neutron scattering could be chosen at a first level as being able to modify the prevailing neutron spectrum towards the desired direction. The factors which are important for an effective inelastic scatterer comprise density and inelastic microscopic cross section, as well as the energy ranges where inelastic scattering occurs. All the above factors have been separately examined in order to suggest potential device materials, able to locally produce SFR neutron spectrum imitation in a thermal MTR.

show abstract

Temperature controlled material irradiation in the advanced test reactor

Cited by 3 publications

References 0 publications

Compilation of Existing Neutron Screen Technology

Compilation of Existing Neutron Screen Technology

Comparison of nuclear irradiation parameters of fusion breeder materials in high flux fission test reactors and a fusion power demonstration reactor

Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum

Contact Info

Product

Resources

About