# Calculation of the composition of reactor-irradiated heavy nuclides

## Abstract

Calculations were made of the compositions of reactorIrradiated Th ^{230}. Th ^{232}, U ^{233}, U ^{235}, U ^{236}, U ^{238}, Pu ^{239}, Pu ^{242}, and Cm ^{244}. Pile fluxes with resonance flux per 1n E interval equal to 1/12 (typical of MTR fuel) or 1/30 (typical of MTR beryllium pieces) of the thermal flux were used for the calculations; thermal fluxes of 5 x 10 ^{13}, 2 x 10 ^{14}, and 1 x 10 ^{13n}cm ^{2} sec were assumed. Calculation methods, assumptions concerning cross sections, and possible methods of producing specific nuclides are discussed.

- Authors:

- Phillips Petroleum Co., Idaho Falls, ID (United States)

- Publication Date:

- Research Org.:
- Phillips Petroleum Co., Idaho Falls, ID (United States). Atomic Energy Division

- Sponsoring Org.:
- USDOE

- OSTI Identifier:
- 4178593

- Report Number(s):
- IDO-16571

- NSA Number:
- NSA-14-011048

- DOE Contract Number:
- AT(10-1)-205

- Resource Type:
- Technical Report

- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60

- Country of Publication:
- United States

- Language:
- English

- Subject:
- 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; BERYLLIUM; CROSS SECTIONS; CURIUM 244; ENERGY; FUELS; IRRADIATION; MTR; NEUTRON FLUX; NUCLEI; NUMERICALS; PLUTONIUM 239; PLUTONIUM 242; PRODUCTION; REACTORS; RESONANCE; THERMAL NEUTRONS; THORIUM 230; THORIUM 232; URANIUM 233; URANIUM 235; URANIUM 236; URANIUM 238

### Citation Formats

```
Schuman, R. P., and Tromp, R. L.
```*Calculation of the composition of reactor-irradiated heavy nuclides*. United States: N. p., 1959.
Web. doi:10.2172/4178593.

```
Schuman, R. P., & Tromp, R. L.
```*Calculation of the composition of reactor-irradiated heavy nuclides*. United States. doi:10.2172/4178593.

```
Schuman, R. P., and Tromp, R. L. Thu .
"Calculation of the composition of reactor-irradiated heavy nuclides". United States. doi:10.2172/4178593. https://www.osti.gov/servlets/purl/4178593.
```

```
@article{osti_4178593,
```

title = {Calculation of the composition of reactor-irradiated heavy nuclides},

author = {Schuman, R. P. and Tromp, R. L.},

abstractNote = {Calculations were made of the compositions of reactorIrradiated Th230. Th232, U233, U235, U236, U238, Pu239, Pu242, and Cm244. Pile fluxes with resonance flux per 1n E interval equal to 1/12 (typical of MTR fuel) or 1/30 (typical of MTR beryllium pieces) of the thermal flux were used for the calculations; thermal fluxes of 5 x 1013, 2 x 1014, and 1 x 1013ncm2 sec were assumed. Calculation methods, assumptions concerning cross sections, and possible methods of producing specific nuclides are discussed.},

doi = {10.2172/4178593},

journal = {},

number = ,

volume = ,

place = {United States},

year = {1959},

month = {12}

}

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